CNL-15-033, License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use

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License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use
ML15043A323
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/12/2015
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-15-033
Download: ML15043A323 (19)
v • d • e


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-033 February 12, 2015 10 CFR 50.90 10 CFR 50.91 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units, 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

License Amendment Request under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 XM NRC Safety Evaluation Approval in Technical Specification 5.6.5.b for Browns Ferry 1, 2, and 3 in Support of ATRIUM-10 XM Fuel Use at Browns Ferry References 1. Letter from TVA to NRC, "Technical Specification Change TS-478 -

Addition of Analytical Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, and 3, and Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 XM Fuel Use at Browns Ferry," dated February 28, 2013 (ML13070A307)

2. Letter from TVA to NRC, "Revised Pages to Technical Specification Change TS-478 - Addition of Analytical. Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, and 3, and Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 XM Fuel Use at Browns Ferry," dated May 16, 2014 (ML14139A180)
3. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 -

Issuance of Amendments Regarding Technical Specification (TS) Change TS-478 Addition of Analytical Methodologies to TS 5.6.5 and Revision of TS 2.1.1.2 for Unit 2 (TAC Nos. MF0877, MF0878, and MF0879)," dated July 31, 2014 (ML14108A334)

4. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Unit 1 - Issuance of Amendments Regarding The Transition to AREVA fuel (TAC No. ME3775)

(TS-473)," dated April 27, 2012 (ML12129A149) 1230

U.S. Nuclear Regulatory Commission Page 2 February 12, 2015

5. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 2 and 3 -

Issuance of Amendments Regarding Deletion of Low Pressure Coolant Injection Motor-Generator Sets for Browns Ferry Plant, Units 2 and 3 (TAC Nos. ME9176 and ME9177)," dated February 15, 2013 (ML13018A342)

In accordance with the provisions of Title 10 of the Code of FederalRegulations (10 CFR) 50.90, "Application for amendment of license, construction permit, or early site permit," Tennessee Valley Authority (TVA) is submitting a request for an amendment to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68, for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3.

In Reference 1 and supplemented by Reference 2, TVA submitted a license amendment request (LAR) to revise the BFN Units 1, 2, and 3, Technical Specifications (TS) for the addition of analytical methodologies to TS 5.6.5.b, in support of ATRIUM-10 XM fuel use.

The Nuclear Regulatory Commission (NRC) approved that amendment request in a safety evaluation (SE) dated July 31, 2014 (Reference 3), which stated that three new analytical methodologies could be added to the BFN TS 5.6.5.b for use in determining the core operating limits in the Core Operating Limits Report (COLR) in support of transition to AREVA ATRIUM-10 XM fuel.

The SE also approved a Loss of Coolant Accident (LOCA) methodology change used to show compliance with 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors." However, this LOCA methodology change associated with the ATRIUM-1 0 XM fuel is slightly different from the LOCA methodology for which TVA had previously received approval with respect to ATRIUM-1 0 (References 4 and 5). NRC approval of the earlier LOCA methodology for ATRIUM-10 fuel (References 4 and 5) required revision of the TS 5.6.5.b to include specific reference to the approved modified LOCA methodology. Accordingly, the TS 5.6.5.b reference for the EXEM BWR-2000 ECCS Evaluation Model included a notation to the site-specific approval in NRC safety evaluation dated April 27, 2012 (for Unit 1) and February 15, 2013 (for Units 2 and 3).

This proposed change supplements the reference to EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model contained in TS 5.6.5.b for BFN, Units 1, 2, and 3, to reflect receipt of the latest approved LOCA methodology SE (Reference 3) by including that notation in the EXEM BWR-2000 reference.

BFN Unit 2 is entering an outage on March 14, 2015, and is scheduled to commence loading ATRIUM-10 XM fuel on March 17, 2015. Due to this discrepancy in referenced documentation, BFN Unit 2 will be unable to issue a Core Operating Limits Report (COLR) for the Unit 2 transition cycle unless the notation to the latest NRC SE (Reference 3) is added.

Accordingly, TVA is requesting this proposed change under exigent circumstances in accordance with 10 CFR 50.91(a)(6), and requests that the NRC expedite their review of the requested change to support approval by March 2, 2015. TVA intends to transition BFN Unit 2 to the XM fuel design starting with Cycle 19 in the spring of 2015, BFN Unit 3 in the spring of 2016, and BFN Unit I in the fall of 2016.

The enclosure to this letter provides the basis for the exigent request, a description, technical evaluation, regulatory evaluation, and environmental consideration of the proposed change. to the enclosure provides the existing TS pages marked-up to show the proposed changes. Attachment 2 to the enclosure provides the existing TS pages retyped with the proposed changes incorporated.

U.S. Nuclear Regulatory Commission Page 3 February 12, 2015 Based on the enclosed evaluation, TVA has determined that there are no significant hazards considerations associated with the proposed changes and that the change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). Additionally, in accordance with 10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and the enclosure to the Alabama State Department of Public Health.

There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Edward D. Schrull at (423) 751-3850.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 12th day of February 2015.

Resp~ec ly, J. .Shea Vic President, Nuclear Licensing

Enclosure:

Addition of a Reference to the ATRIUM-10 XM NRC Safety Evaluation Approval in Technical Specification 5.6.5.b for Browns Ferry Units 1, 2, and 3 Attachment 1 Proposed Technical Specification Page Markups Attachment 2 Retyped Proposed Technical Specifications Pages cc (Enclosures):

NRC Regional Administrator, Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health

Enclosure 1 Browns Ferry Nuclear Plant (BFN)

Technical Specifications (TS) Change TS-503 Addition of a Reference to the ATRIUM-10 XM NRC Safety Evaluation Approval in Technical Specification 5.6.5.b for Browns Ferry Units 1, 2, and 3 1.0

SUMMARY

DESCRIPTION This evaluation supports a request to amend the Operating Licenses for Browns Ferry Nuclear Plant (BFN) Unit 1 (DPR-33), Unit 2 (DPR-52), and Unit 3 (DPR-68). The proposed change would revise Technical Specification (TS) 5.6,5.b, "Core Operating Limits Report (COLR)," for all three units to add the approval date of the Nuclear Regulatory Commission (NRC) Safety Evaluation (SE) (Reference 3) to the reference for EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model.

The proposed change adds the July 31, 2014, SE approval date to BFN Unit 1, Unit 2, and Unit 3 TS 5.6.5.b in order to reflect an enhanced methodology related to the treatment of top down core spray cooling, that was utilized in the NRC approved Loss of Coolant Accident (LOCA) analysis supporting the transition to ATRIUM-10 XM fuel.

2.0 DETAILED DESCRIPTION 2.1 Proposed Changes As approved by NRC for BFN, Unit 1, TS 5.6.5.b Reference 16 states:

"EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation dated April 27, 2012."

As approved by NRC for BFN, Units 2 and 3, TS 5.6.5.b Reference 15 states:

"EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation dated February 15, 2013."

The proposed change supplements the above TS 5.6.5.b references with the approval of the XM Fuel SE (Reference 3) dated July 31, 2014.

For BFN, Unit 1, the proposed change for TS 5.6.5.b Reference 16 is:

"EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluations dated April 27, 2012, and July 31, 2014."

For BFN, Units 2 and 3, the proposed change for TS 5.6.5.b Reference 15 is:

"EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluations dated February 15, 2013, and July 31, 2014."

CNL-1 5-033 El1of 6

2.2 NeedlBasis for Proposed Exigent Changes In Reference 1 and supplemented by Reference 2, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to revise the BFN, Units 1, 2, and 3, Technical Specifications (TS) for the addition of analytical methodologies to TS 5.6.5.b for BFN Units 1, 2, and 3, in support of ATRIUM-1 0 XM fuel use. The NRC approved that LAR in an SE dated July 31, 2014 (Reference 3), which stated that three new analytical methodologies could be added to the BFN TS 5.6.5.b for use in determining the core operating limits in the Core Operating Limits Report (COLR) in support of transition to AREVA ATRIUM-10 XM fuel. In addition, the SE approved a LOCA methodology change used to show compliance with Title 10 of the Code of Federal Regulations (10 CFR) 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors." However, this LOCA methodology change associated with the ATRIUM-10 XM fuel is slightly different from the LOCA methodology for which TVA had previously received approval with respect to ATRIUM-10 fuel (References 4 and 5). NRC approval of the earlier LOCA methodology for ATRIUM-10 fuel (References 4 and 5) required revision of the TS 5.6.5.b to include specific reference to the approved modified LOCA methodology. Accordingly, the TS 5.6.5.b reference for the EXEM BWR-2000 ECCS Evaluation Model (Reference 6) included a notation to the site-specific approval in NRC safety evaluation dated April 27, 2012 (for Unit 1) and February 15, 2013 (for Units 2 and 3). Therefore, prior to use of the NRC-approved Loss of Coolant Accident (LOCA) analysis for determining the core operating limits in the COLR supporting the transition to ATRIUM-10 XM fuel, reference to the new SE must be included with the TS 5.6.5.b EXEM BWR-2000 ECCS Evaluation Model reference.

BFN Unit 2 is entering an outage on March 14, 2015, and is scheduled to commence loading ATRIUM-10 XM fuel on March 17, 2015. Accordingly, TVA is requesting this proposed change under exigent circumstances in accordance with 10 CFR 50.91(a)(6), and requests that the NRC expedite their review of the requested change to support the upcoming BFN Unit 2 Cycle 19 operation.

3.0 TECHNICAL EVALUATION

During the review of TVA's ATRIUM-10 transition LAR at BFN Unit 1 (Reference 7), the NRC issued a Request for Additional Information (RAI) raising a concern regarding the availability of top down cooling (countercurrent flow) used in AREVA's break spectrum methodology (Reference 6) relative to the initiation of core spray. To address the NRC's concern, TVA submitted a response to the RAI (Reference 8) that included an updated AREVA site-specific report (Reference 9) implementing a model that restricted top down cooling at the initiation of the core spray. The NRC found this model adequately addressed its concern.

Subsequently, the NRC provided SEs to TVA for Unit 1 (Reference 4) and Units 2 and 3 (Reference 5) which included this modification to the EXEM BWR methodology.

As part of AREVA's discussion with the NRC, the need to address this issue generically was recognized. AREVA developed a more refined top down cooling restriction model and presented this model and a subsequent summary to the NRC (Reference 10). AREVA recommended that this model be used for all future break spectrum analyses but that the current break spectrum analyses of record would not require reevaluation. The NRC acknowledged that AREVA's model was a conservative application of the EXEM BWR-2000 methodology and agreed with the recommended approach of implementing the model on all new analyses (Reference 11).

CNL-1 5-033 E 2 of 6

The ATRIUM-10 XM break spectrum analysis (Reference 12) performed in support of the ATRIUM-10 XM transition LAR at BFN implemented the "future-analysis" model AREVA presented to the NRC in August 2011, and not the model used for the ATRIUM-10 break spectrum report.

The slight differences in the Reference 9 model implemented for ATRIUM-10 at BFN and the ATRIUM-10 XM break spectrum (Reference 12) have the potential to affect the analysis results (i.e., Peak Clad Temperature (PCT)) for large break accidents but does not affect small break accidents at BFN. BFN is small break limited; therefore, the limiting PCT and PCTs around the limiting break are identical with either model.

No plant hardware or operational changes are required as a result of the proposed license amendment.

4.0 REGULATORY EVALUATION

4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA 10 CFR 50.46 requires that the fuel be protected in the event of a design basis LOCA such that peak clad temperature, cladding oxidation, hydrogen generation, coolable geometry, and long term cooling be maintained within limits specified by the regulation.

4.2 PRECEDENT The NRC has previously reviewed and approved the application of modified LOCA methods for AREVA, to address concerns related to top down core spray cooling.

Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Unit 1 - Issuance of Amendments Regarding the Transition to AREVA fuel (TAC No. ME3775) (TS-473),"

dated April 27, 2012 (ML12129A149)

Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 2 and 3 - Issuance of Amendments Regarding Deletion of Low Pressure Coolant Injection Motor-Generator Sets for Browns Ferry Plant, Units 2 and 3 (TAC Nos. ME9176 and ME9177)," dated February 15, 2013 (ML13018A342)

Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Technical Specification (TS) Change TS-478 Addition of Analytical Methodologies to TS 5.6.5 and Revision of TS 2.1.1.2 for Unit 2 (TAC Nos.

MF0877, MF0878, and MF0879)," dated July 31, 2014 (ML14108A334) 4.3 NO SIGNIFICANT HAZARDS CONSIDERATION This analysis addresses the proposed change to amend the TS 5.6.5.b reference related to the EXEM BWR-2000 LOCA methodology for all three BFN units. The change would add an annotation to note the approval of an enhanced top down core spray treatment agreed upon between AREVA and the NRC in August 2011, approved by NRC for BFN, Units 1, 2, and 3 by Safety Evaluation (SE) dated July 31, 2014 (ML14108A334).

CNL-15-033 E 3of 6

Tennessee Valley Authority (TVA) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below.

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed amendment changes Technical Specification 5.6.5.b to reflect the NRC approval of an updated method of treating top down core spray in LOCA analysis. As such, it involves no changes to the operation of any system or component during normal, accident, or transient operating conditions. The change does not affect the initiators of any accident.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed amendment adds a recent NRC Safety Evaluation (SE) to existing annotation on the AREVA LOCA method listed in the TS 5.6.5.b. As such, the amendment does not involve physical changes to plant hardware or its operating characteristics. No new failure modes are introduced. Therefore, the change does not introduce a new or different kind of accident from those previously evaluated.

3. Does the proposed amendment involve a significant reduction in the margin of safety?

Response: No The amendment makes changes to the Technical Specifications, to reflect the NRC SE related to the ATRIUM-10 XM fuel transition. The margin of safety will not be altered by the amendment, as the NRC has reviewed the LOCA analysis associated with that amendment and determined the results to be acceptable. No plant system, structure, or component is affected, and the behavior of plant equipment is not affected.

Based on the above, TVA concludes the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92 (c), and, accordingly, a finding of "no significant hazards consideration" is justified.

4.4 CONCLUSION

S The proposed addition of the date of the TS-478 SE to the TS 5.6.5.b reference pertaining to the EXEM BWR-2000 LOCA methodology is acceptable based on the following:

> The NRC reviewed the LOCA analysis associated with TS-478, which utilized the updated treatment of top down core spray cooling. The Reference 1 SE noted the analysis was acceptable for use at BFN.

CNL-15-033 E 4of 6

> The change to the Technical Specifications annotates a reference to an already approved and issued SE.

> This change to the Technical Specifications does not require any plant modifications that could affect the behavior of the plant during normal, transient, or accident conditions.

Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

A review has determined the proposed amendment would change a requirement with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, but would not change an inspection or surveillance requirement. The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

CNL-15-033 E 5of 6

6.0 REFERENCES

1. Letter from TVA to NRC, "Technical Specification Change TS-478 - Addition of Analytical Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, and 3, and Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-1O XM Fuel Use at Browns Ferry," dated February 28, 2013 (ML13070A307)
2. Letter from TVA to NRC, "Revised Pages to Technical Specification Change TS-478 -

Addition of Analytical Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, and 3, and Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 XM Fuel Use at Browns Ferry," dated May 16, 2014 (ML14139A180)

3. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Technical Specifications (TS) Change TS-478 Addition of Analytical Methodologies .to TS 5.6.5 and Revision of TS 2.1.1.2 for Unit 2 (TAC NOS. MF0877, MF0878, and MF0879)," dated July 31, 2014 (ML14108A334)
4. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Unit 1 - Issuance of Amendments Regarding The Transition to AREVA fuel (TAC No. ME3775) (TS-473)," dated April 27, 2012 (ML12129A149)
5. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 2 and 3 - Issuance of Amendments Regarding Deletion of Low Pressure Coolant Injection Motor-Generator Sets for Browns Ferry Plant, Units 2 and 3 (TAC Nos. ME9176 and ME9177)," dated February 15, 2013 (ML13018A342)
6. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome, ANP, May 2001.
7. Letter from TVA to NRC, "Technical Specification Change TS-473 - AREVA Fuel Transition," dated April 16, 2010 (ML101160153)
8. Letter from TVA NRC, "Browns Ferry Unit 1 - Response to NRC Request for Additional Information Regarding Amendment Request to Transition to AREVA Fuel (TAC No.

ME3775)." October 7, 2011. (ML11286A109).

9. ANP-3015(NP), "Browns Ferry Units 1, 2, and 3 LOCA Break Spectrum Analysis,"

Revision 0, September 2011 (ML11286A109).

10. Presentation from AREVA to NRC, "AREVA BWR LOCA Methods Applicability," dated August 16, 2011 and Letter from AREVA to NRC, "Summary of NRC meeting on August 16, 2011 and Proposed Implementation Strategy for Modified Analysis Approach for the EXEM BWR-2000 ECCS Evaluation Model," dated September 22, 2011.

(ML11270A008)

11. Letter from NRC to AREVA, "Response to AREVA NP, Inc. (AREVA) Proposed Analysis Approach for its EXEM Boiling Water Reactor (BWR)-2000 Emergency Core Cooling System (ECCS) Evaluation Model," dated July 5, 2012. (ML12138A206)
12. ANP-3152P, "Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis for ATRIUM-IO XM Fuel," Revision 0, AREVA NP, Inc., October 2012. (ML13070A307)

CNL-15-033 E 6of 6

ATTACHMENT I Browns Ferry Nuclear Plant (BFN)

Units 1, 2, and 3 Technical Specifications (TS) Change 503 Proposed Technical Specifications Changes (Mark-up)

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

10. XN-NF-84-105(P)(A) Volume 1 and Volume I Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
11. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
12. ANF-913(P)(A) Volume 1 Revision I and Volume I Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
13. ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
14. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
15. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000. , and July 31, 2014. [
16. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation dated April 27, 2012-
17. EMF-2292(P)(A) Revision 0, ATRIUM*-10:. Appenft K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

(continued)

BFN-UNIT 1 5.0-24b Amendment No. 2-K4, 23, 2A2, 2"8., 285

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

14. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
15. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluation dated February 15, 2013 E--,and July 31, 2014.
16. EMF-2292(P)(A) Revision 0, ATRIUM"-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
17. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
18. BAW-1 0255(P)(A), Revision 2, Cyde-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.
19. BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.

20.ANP-10298PA Revision 0, ACE/ATRIUM iOXM Critical Power Correlation, AREVA NP, March 2010.

21 .ANP-3140(P) Revision 0, Browns Ferry Units 1, 2, and 3 Improved K-factor Model for ACE/ATRIUM IOXM Critical Power Correlation, AREVA NP, August 2012.

BFN-UNIT 2 5.0-24b Amendment No. W, W9, 311

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 12.ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.

13. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, I AREVA NP, September 2009.
14. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
15. EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluatio dated February 15, 2013 . J 3
16. EMF-2292(P)(A) Revision 0 ATRIUM  : pendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
17. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis:

Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

18. BAW-1 0255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.
19. BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.

20.ANP-10298PA Revision 0, ACE/ATRIUM 1OXM Critical Power Correlation, AREVA NP, March 2010.

(continued)

BFN-UNIT 3 5.0-24b Amendment No. 24-1, M, 246, 2*, 268,270

ATTACHMENT 2 Browns Ferry Nuclear Plant (BFN)

Units 1, 2, and 3 Technical Specifications (TS) Change 603 Proposed Technical Specifications Pages (Retyped)

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

10. XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
11. ANF-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
12. ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
13. ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
14. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
15. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
16. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluations dated April 27, 2012, and July 31, 2014.
17. EMF-2292(P)(A) Revision 0, ATRIUM TM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

(continued)

BFN-UNIT 1 5.0-24b Amendment No. 234, 239, 2-2, 2-4, 285,

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

14. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
15. EMF-2361(P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluations dated February 15, 2013, and July 31, 2014.
16. EMF-2292(P)(A) Revision 0, ATRIUM TM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
17. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
18. BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.
19. BAW-10247PA Revision 0, RealisticThermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.
20. ANP-10298PA Revision 0, ACE/ATRIUM 1OXM Critical Power Correlation, AREVA NP, March 2010.
21. ANP-3140(P) Revision 0, Browns Ferry Units 1,2, and 3 Improved K-factor Model for ACE/ATRIUM 1OXM Critical Power Correlation, AREVA NP, August 2012.

(continued)

BFN-UNIT 2 5.0-24b Amendment No. 28-i, =3W, 344,

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

12. ANF-1358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
13. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
14. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
15. EMF-2361(P)(A) Revision 0, EXEM BWR--2000 ECCS Evaluation Model, Framatome ANP Inc., May 2001 as supplemented by the site-specific approval in NRC safety evaluations dated February 15, 2013, and July 31, 2014.
16. EMF-2292(P)(A) Revision 0, ATRIUMm-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
17. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis:

Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

18. BAW-10255(P)(A), Revision 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-FA Code, AREVA NP, May 2008.

19 BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February2008.

20. ANP-1 0298PA Revision 0, ACE/ATRIUM 1OXM Critical Power Correlation, AREVA NP, March 2010.

(continued)

BFN-UNIT 3 5.0-24b Amendment No. 24-2, 226, 24-4, 2-0, 2-6", 2-7-0,

PROCESS FOR PUBLISHING A PUBLIC NOTICE IN LOCAL MEDIA TO SUPPORT ISSUANCE OF AN EXIGENT LICENSE AMENDMENT The following describes the process of placing an advertisement in a local newspaper to support issuance of an exigent license amendment in accordance with Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-101 and the requirements in 10 CFR 50.91 (a)(6)

The following steps are performed by the NRR Division of Operating Licensing (DORL) Project Manager (PM).

1. Coordinate with the Office of Public Affairs (in the specific Regional office) to determine which local media (e.g., newspaper) will be used to publish the notice.
2. Prepare the public notice. See ADAMS Accession No. ML082120592 for a template of the notice.
3. Contact the local media where you want the ad to run.

a) Ask for the "classifieds," "public notices," or "legal notices" section of the newspaper. The names will vary depending on the newspaper.

b) Forward the public notice to them by fax, e-mail, or both (they need to see the notice so that they can estimate the cost).

c) Give the newspaper the specific date(s) and how long you want the ad to run.

There is no guidance specifically stating a required length of time the ad must run (it is suggested that the ad run for 2 to 3 days).

d) Ask the newspaper for the cost of the ad and have them e-mail or fax a quote to eyou.

4. Prepare an NRC Form 30 (ADAMS Accession No. ML13083A015) as follows:

a) Box 1 (Date of Request): Enter today's date.

b) Box 2 (Date Due): Due to the urgency of the request, enter the same date entered in Box 1 or the next day if time allows.

c) Box 4 (Type of Service): Check the "Other" box and enter "Purchase Action."

d) Box 6 (Requester): Enter name of DORL PM.

e) Box 7 (Office): Enter "NRR" f) Box 8 (Telephone): Enter phone number for DORL PM.

g) Box 9 (Fax Number): Enter DORL fax number "301-415-2102" h) Box 10 (Mail Stop): Enter Mail Stop for DORL PM.

ADAMS Accession No. ML113080514

Box 11 (Special Instructions): Explain that this request is to publish a public notice in the "Name" newspaper and that the notice will run for "X" dates. Also include a contact name at the newspaper and their phone number and/or email address for the person who can accept a credit card. Attach the quote on the cost from step 3d above. Note, you may put requests to multiple newspapers on one Form 30 if they are all under $3,000 each. Actions over $3,000 each must be on separate Form 30s.

j) Box 5b (Division Director/Designee): Obtain the signature of the DORL Division Director, Deputy Director, or Acting Director.

k) Take the completed NRC Form 30 to the Division Financial Certifying Official (FCO), Sylvia Valencia (301-415-7570), in NRR/PMDA. The Division FCO will review the request for approval and forward to the purchase credit card holder to pay for the ad.

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