Text

ANP-3035(NP), Revision 0, Areva Responses to August 2011 RAIs for Browns Ferry, Unit 1 Fuel Transition - LOCA, Enclosure 3
	ML11286A108
Person / Time
Site:	Browns Ferry
Issue date:	09/30/2011
From:	; AREVA NP
To:	; Office of Nuclear Reactor Regulation
References
	ANP-3035(NP), Rev 0
	Download: ML11286A108 (79)
	v • d • e

ENCLOSURE 3 Browns Ferry Nuclear Plant Unit I Technical Specifications Change TS - 473 - AREVA Fuel Transition ANP-3035(NP), Revision 0, "AREVA Responses to August 2011 RAIs for Browns Ferry Unit I Fuel Transition - LOCA", Non-Proprietary

ANP-3035(NP)

Revision 0 AREVA Responses to August 2011 RAIs for Browns Ferry Unit 1 Fuel Transition - LOCA September 2011 A

AREVA AREVA NP Inc.

AREVA NP Inc.

ANP-3035(NP)

Revision 0 AREVA Responses to August 2011 RAIs for Browns Ferry Unit I Fuel Transition - LOCA

AREVA NP Inc.

ANP-3035(NP)

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page i Nature of Changes Item Page Description and Justification

1. All This is the initial issue.

AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAls for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page ii Contents 1 .0 Introd uctio n ..................................................................................................................... 1 2.0 NRC Requests for Additional Information and the AREVA Response......................... 1 2.1 NRC Request 1 .................................................................................................... 1 2.2 NRC Request 2 ................................................................................................ 1 2.3 NRC Request 3 ................................................................................................ 2 2.4 NRC Request 4 ................................................................................................... 6 2.5 NRC Request 5 ................................................................................................ 6 2.6 NRC Request 6 .............................................................................................. 12 2.7 NRC Request 7 .............................................................................................. 15 3 .0 R efe re n ce s ..................................................................................................................... 16 Appendix A TLO Recirculation Line Break With [ ] 0.21 ft 2 Split Supplemental Information .................................................................. A-1 2

Appendix B TLO Recirculation Line Break With 10.05 ft Split Supplemental Information .................................................................. B-1 2

Appendix C TLO Recirculation Line Break With [ ] 0.05 ft Split Supplemental Information .................................................................. C-1 Appendix D Bottom Head Drain Line Break Supplemental Information ............................. D-1 AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page iii Tables 2.3.1 Sensitivity Results for Pressure Control for 102% Power [ I I SF-BATTIBA Top-Peaked Pump Discharge ............................................................. 3 2.3.2 Event Times for Limiting TLO Recirculation Line Break 0.21 ft2 Split Pump Discharge SF-BATTIBA Top-Peaked Axial 102% Power [

............................................................................................................................ 4 2.3.3 Event Times for TLO Recirculation Line Break 0.05 ft2 Split Pump Discharge SF-BATTIBA Top-Peaked Axial 102% Power [ ].......... 5 2.5.4 Senstivity Study W ith EM Flag .................................................................................. 7 Figures 2.5.1 102% Power [ 105% Flow ] SF-BATTIBA Liquid Mass in the Bottom Core Volume [ ]................ 8 2.5.2 102% Power [ ] SF-BATTIBA Liquid Mass in the Bottom Core Volume [ 0.19 ft /PD and 0.18 ft2/PD Cases EM Flag Off (System Calculation O n ly ))) ............................................................................................. *............................ .9 2.5.3 102% Power[

I........................................................... . . 10 2.5.4 102% Power[ ] SF-BATTIBA Cladding Temperatures [

I ................................. 11 2.6.1 102% Power[ ] SF-BATTIBA Cladding Temperatures [

] .............................................. . . 13 2.6.2 102% Power[ ] SF-BATTIBA Cladding Temperatures

................................. 14 AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 1 1.0 Introduction Tennessee Valley Authority (TVA) submitted a License Amendment Request (LAR) to change the Browns Ferry Unit 1 Technical Specifications in support of reload fuel transition to AREVA NP. In response to the LAR, the Nuclear Regulatory Commission (NRC) has issued a Request for Additional Information (RAI) (Reference 1) following a July 2011 audit at AREVA's Richland, Washington facilities.

The information provided in the report provides the responses to the RAIs.

2.0 NRC Requests for Additional Information and the AREVA Response The NRC requests listed below are according to Reference 1.

2.1 NRC Request I Please provide a revised Emergency Core Cooling System (ECCS) Evaluation Summary that provides a detailed description of the most severe loss-of-coolant accident (LOCA) analysis, along with a description of other break sizes, locations and other properties that were evaluated to support the determination that the most severe postulatedLOCA has been calculated.

The new break spectrum report, ANP-3015(P), Browns Ferry Units 1, 2, and 3, LOCA Break Spectrum Analysis, provides the requested summary (Reference 2).

2.2 NRC Request 2 Please provide a detailed description of the model changes made to addressthe staff's concern with the evaluation model's application.

The description of the model change to address the staffs concerns [

] is provided in Section 4.4 of ANP-3015(P) (Reference 2).

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AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 2 2.3 NRC Request 3 Please provide the results of a sensitivity study demonstratingthe effect of the EXEM-BWR 2000 pressurecontrol assumptions on the break spectrum. Please include results for the limiting break size as determined using the modified EXEM-BWR 2000 analyses (0.21 ft2) and for a smaller break size that would result in a delayed pressurization following a level-driven main streamline isolation.

The following new analyses were performed to address the request:

SF-BATTIBA, 0.21 ft2 recirculation discharge pipe break, 102% power/ [

], top-peaked axial power shape

SF-BATTIBA, 0.05 ft 2 recirculation discharge pipe break, 102% power/ [

], top-peaked axial power shape The 0.05 ft 2 break size was chosen to maximize the delay in pressurization.

Analysis modifications consisted of:

The PCT was [ ] for both cases using the [ ], as shown in 2

Table 2.3.1. Table 2.3.2 shows event times for the 0.21 ft break. Table 2.3.3 shows event times for the 0.05 ft2 break. For the 0.21 ft 2 break, more detailed results are provided in Reference 2 Section 6 (Tables 6.1 and 6.2 and Figures 6.1 - 6.19) for the original analysis [ ] and in Appendix A for the [ I 2

analysis. For the 0.05 ft break, more detailed results are provided in Appendix B for the

[ ] analysis and Appendix C for the [ ] analysis. The analyses demonstrate that the EXEM BWR-2000 method for [

I]

AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 3 Table 2.3.1 Sensitivity Results for Pressure Control for 102% Power [ ] SF-BATTIBA Top-Peaked Pump Discharge AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 4 Table 2.3.2 Event Times for Limiting TLO Recirculation Line Break 0.21 ft2 Split Pump Discharge SF-BATTIBA Top-Peaked Axial 102% Power [ I AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit I Revision 0 Fuel Transition - LOCA Page 5 Table 2.3.3 Event Times for TLO Recirculation Line Break 0.05 ft2 Split Pump Discharge SF-BATTIBA Top-Peaked Axial 102% Power [ ]

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AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 6 2.4 NRC Request 4 Pleaseprovide a summary of the break spectrum results that include sufficient detail to compare the break spectra for each combination of power shape, core flow state point, single failure, and break geometry.

Appendices B, C, and D were added to the break spectrum report (Reference 2) to provide sufficient detail to compare spectra.

2.5 NRC Request 5 Please explain why the break spectrum results exhibit slightly discontinuousbehavior in the intermediaterange of break sizes. Identify the significantmodel aspects that are causing the behaviorand provide an estimate or descriptionof the impact on the evaluation.

Table B.1 of Reference 2 provides the PCTs in question for the intermediate break sizes.

The behavior over the range of breaks in question is best described by focusing on the results for the [

] An extensive review was performed to determine the cause of the discontinuous behavior in PCT. Numerically, the solutions were converged since changes to the calculation time steps did not result in a significant change to PCT, nor change the shape of the PCT plot. The review determined that the significant difference between the cases was liquid in the bottom of the average core in the RELAX system analysis. Specifically, the discontinuous behavior was attributed to differences in steam generation and counter current flow limitation (CCFL) at the assembly inlet. [

], the [ ] break has much less liquid mass than the [ ] break, which leads to the higher PCT.

Scoping analyses determined that the CCFL phenomenon was sensitive to [

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RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 7 I

I I

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RAls for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 8 Figure 2.5.1 102% Power [ ] SF-BATTIBA Liquid Mass in the Bottom Core Volume

[

I AREVA NP Inc.

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RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 9 Figure 2.5.2 102% Power [ I SF-BATTIBA Liquid Mass in the Bottom Core Volume

[I I]

[

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RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 10 Figure 2.5.3 102% Power [ ] SF-BATTIBA Cladding Temperatures I

]

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AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 11 K

Figure 2.5.4 102% Power [ ] SF-BATTIBA Cladding Temperatures

[

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RAls for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 12 2.6 NRC Request 6 Please determine the cause of the intermediatetemperature transientobservable in the plots of peak cladding temperature vs. time for the intermediatebreak size cases and provide a summary explanation. Justify the validity of the results, given the temperature trends depicted.

For the break sizes in question, the RELAX hot channel analyses shows the temperature of the peak node turning over near the end of the event due to [

]. Analyses discussed in response to RAI 5 are used to demonstrate the timing of events. As shown in Figure 2.6.1, the PCT for the [ ] break just starts to [

]. As shown for the

[ ] break, the differences in timing results in a bigger "hump" in the PCT plot.

The analyses of Figure 2.6.1 were repeated with the end of blowdown changed to the end time of the analysis; this change eliminates the use of the Appendix K spray heat transfer coefficients. Figure 2.6.2 shows the [

]. The difference in shapes is attributed to the phenomenon discussed in response to RAI 5. As shown in Figure 2.5.4, [

] It is concluded that the PCT plots are valid based on the EXEM BWR-2000 Appendix K methodology which dictates a [

AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 13 Figure 2.6.1 102% Power [ ] SF-BATTIBA Cladding Temperatures

[

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RAls for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 14 Figure 2.6.2 102% Power [ ] SF-BATTIBA Cladding Temperatures

[

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RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 15 2.7 NRC Request 7 Title 10 of the Code of FederalRegulations, Section 50.46, requires ECCS cooling performance to be calculatedfor a number of postulated LOCAs of different sizes, locations, and other propertiessufficient to provide assurancethat the most severe postulatedLOCAs are calculated. At the time EXEM-BWR 2000 was approved, ECCS researchsuggested that the large-breakLOCA was generally limiting for boiling-water reactors,and there appears to be little considerationof post-power uprate plant operation.

Since the ECCS research was compiled and documented in NUREG-12301 "Compendium of ECCS Research for Realistic LOCA Analysis," operatingexperience has shown that the small break scenario can in fact result in a more limiting event.

Because the small-break accident is limiting, AREVA Topical Report ANP-2908(P) includes a number of explicitly analyzed ancillary line breaks, since these breaks are smaller in size. The general trend is a liquid blow down at high pressure until the break uncovers, followed by a depressurizationof the reactorcoolant system caused by steam exiting the break. The analysis results indicate that, absent any emergency core cooling, the steam flow pressurereduction is a dominant mechanism in the event.

Please provide an analysis of the rupture of the bottom head drain line (which would not include the pressurereduction associated with break uncover) to demonstrate that the initial heatup would not contribute to the limiting peak cladding temperature. This analysis should considerthe most limiting of the Battery Board B failure and the high-pressure coolantinjection failure.

For the Battery Board B failure (SF-BATTIBB), the available ECCS is 4 ADS, HPCI, 1 LPCS, and 2 LPCI. With both HPCI and ADS active, the rupture of the bottom head drain line will result in a very mild event. To demonstrate this, two analyses were performed. One analysis assumed the inventory was lost from the rupture of the bottom head drain line, check valves were assumed to eliminate any inventory loss from the reactor water cleanup line connected to the recirculation suction line. The other analysis assumed no check valves in the cleanup line; therefore, inventory was lost from both the bottom head drain line and cleanup line (see Reference 2, Figure 4.3). [

] For both cases, the break was assumed to be the full diameter of the pipe. The core did not uncover and PCT remained below 1000OF for both analyses; therefore, this single failure does not challenge the limiting recirculation line break PCT.

When HPCI is available, a rupture of the bottom head drain line (with or without break flow through the cleanup line) results in a mild event, since HPCI is able to maintain a water level in the vessel.

In terms of available ECCS, a single failure of the HPCI (SF-HPCI) is bound by a single failure of Battery Board A (SF-BATTIBA). SF-HPCI has 6 ADS, 2 LPCS, and 4 LPCI AREVA NP Inc.

AREVA Responses to August 2011 ANP-3035(NP)

RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page 16 ECCS systems remaining. SF-BATTIBA has 6 ADS, 1 LPCS, and 2 LPCI ECCS systems remaining. For this scenario, ADS will depressurize the vessel allowing low pressure systems to maintain coolant inventory. The event will experience a mild heatup. As before, one analysis assumed the inventory was lost from the bottom head drain line, the other analysis assumed inventory lost from both the bottom head drain line and the cleanup line. The PCT for the SF-BATTIBA for both analyses was less than 1000 0 F. Only the analysis where inventory was lost from both the bottom head drain line and the cleanup line showed a mild heatup, which makes it the limiting scenario. The other analysis where inventory was lost only from the bottom head drain line did not have a heatup. Figures for the limiting scenario are presented in Appendix D. This single failure does not challenge the limiting recirculation line break PCT.

In regards to response to RAI 3, the .limiting scenario was repeated with [

] . The analysis did not result in a higher PCT.

Based on the results of the analyses presented above, rupturing the bottom head drain line does not result in a limiting PCT.

3.0 References

1. Letter, C. Gratton (USNRC) to R.M. Krich (TVA), "Browns Ferry Nuclear Plant, Unit 1 -

Request for Additional Information Regarding Technical Specification TS-473, AREVA Fuel Transition (TAC NO. ME3775)," August 23, 2011.

2. ANP-3015(P) Revision 0, Browns Ferry Units 1, 2, and 3 LOCA Break Spectrum Analysis, AREVA NP, September 2011.

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RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page A-1 Appendix A TLO Recirculation Line Break With [ ]

0.21 ft 2 Split Supplemental Information AREVA NP Inc.

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RAIs for Browns Ferry Unit.1 Revision 0 Fuel Transition - LOCA Page C-1 Appendix C TLO Recirculation Line Break With [ ]

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RAIs for Browns Ferry Unit 1 Revision 0 Fuel Transition - LOCA Page D-1 Appendix D Bottom Head Drain Line Break Supplemental Information

[

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ENCLOSURE 4 Browns Ferry Nuclear Plant Unit I Technical Specifications Change TS - 473 - AREVA Fuel Transition Affidavit for ANP-3035(P), Revision 0, "AREVA Responses to August 2011 RAIs for Browns Ferry Unit I Fuel Transition - LOCA", Proprietary

AFFIDAVIT STATE OF WASHINGTON )

) ss.

COUNTY OF BENTON )

1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.

3. I am familiar with the AREVA NP information contained in the report ANP-3035(P) Revision 0, entitled, "AREVA Responses to August 2011 RAIs for Browns Ferry Unit I Fuel Transition - LOCA," dated September 2011 and referred to herein as "Document."

Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is

requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."

6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:

(a) The information reveals details of AREVA NP's research and development plans and programs or their results.

(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.

(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.

(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.

The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.

7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.

SUBSCRIBED before me this 3d day of_ --

__ _ 2011 Susan K. McCoy NOTARY PUBLIC, STATE OF WASHINGTON MY COMMISSION EXPIRES: 1/10/12

ENCLOSURE 7 Browns Ferry Nuclear Plant Unit I Technical Specifications Change TS - 473 - AREVA Fuel Transition Affidavit for ANP-3015(P), Revision 0, "Browns Ferry Units 1, 2, and 3, LOCA Break Spectrum Analysis", Proprietary

AFF IDAVIT STATE OF WASHINGTON )

) ss.

COUNTY OF BENTON

1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.

3. I am familiar with the AREVA NP information contained in the report ANP-3015(P) Revision 0, entitled, "Browns Ferry Units 1, 2, and 3 LOCA Break Spectrum Analysis," dated September 2011 and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection.of proprietary and confidential information.