BSEP 04-0127, Calculation No. 0B21-0112, Rev. 11, 10 CFR 50.46 SAFER/GESTR-LOCA ECCS Analysis Update.

Calculation No. 0B21-0112, Rev. 11, 10 CFR 50.46 SAFER/GESTR-LOCA ECCS Analysis Update.

ML042610127
Person / Time
Site:	Brunswick
Issue date:	08/11/2004
From:	Dresser T Progress Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
-RFPFR, BSEP 04-0127 0B21-0112, Rev 11
Download: ML042610127 (43)

Text

BSEP 04-0127 Enclosure Brunswick Steam Electric Plant, Units 1 and 2, Calculation Number OB21-0112, Revision 11, 10 CFR 50.46 SAFER/GESTR-LOCA ECCS Analysis Update

r- V C0 702 e& 3 Title and Approval Cover Sheet SYSTEM# 1005 CALC. SUB-TYPE, NUF PRIORITY CODE- 4 QUALITY CLASS_ A NUCLEAR GENERATION GROUP OB21-0112 -

1 CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update (Title including structures, systems, components)

Z BNP UNIT 0 M CR3 LM HNP E RNP a NES [1 ALL APPROVAL REV PREPARED BY REVIEWED BY SUPERVISOR Signature Signature Signature 10 Name Name Name Tom Dresser Mourad Aissa George Smith Date Date Date

/Q128/03 6/28/03 6/28/03 lSinature St/

11 - NameNameN Tom Dresser Mourad Aissa George Smith Date Date Date 8/11/04 8/11/04 8/11/04 Vendor Vendor Document No.

Owner's Review By Date

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 2of 18 Calculation

Title:

10CFR50.46 SAFERIGESTR-LOCA ECCS Analysis Update LIST OF EFFECTIVE PAGES PAGE REV PAGE REV AiTACHMEIENTS 1-18 11 Number Rev .Number of Pages 0 11 2 1 11 4 2 11 18 3 .11 2 4 1 2 AMENDMENTS Letter Rev Number of Pages

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 3 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Revision Summary Rev. Date Revision Summary 0 1/6/98 Original documentation 1 8/31/98 Revised to include 6/30/98 annual Reporting of Changes and Errors and to create/save electronic copy of design calculation OB21-0112 2 2/8/99 Revised to incorporate 1/27/99 GE notification WHH:99-007 of failure to include in 1996 LOCA calculation the known sensitivity to small input parameter changes (up to +/-50 0F error). This error is in addition to the 10 0F BHD error already being tracked and requires 30 day 10CFR50.46 report to NRC. Revision 2 independently reviews entire 10CFR50.46 error reporting table since inception and verifies/revises table as necessary. Formats OB21-0112 per OENP-303 Rev. 3.

3 8/12/99 Revised to incorporate 6125199 GE letter WHH:99-044 "10 CFR50.46 Notification Letter" (with associated letter NF-99A-0145) and 6/30/99 annual notice MFN-004-99 "Summary of Changes and Errors in ECCS Evaluation Models".

4 9121/99 Update Revision 3 oversight: headers of section 4.1 Tables 2 and 3 to show "Change Summary Through 06/30/99" 5 8/11/00 Revised to incorporate 6/30/00 GE letter WHH:2000-044 "Summary of Changes and Errors in ECCS Evaluation Models" (with associated 6/30/00 annual notice FLN-2000-06 "Summary of Changes and Errors in ECCS Evaluation Models").

Also revised to reflect 7/31/00 telephone conference between Dresser, Kremer of PGN and Thacker, Stott of GE during which PGN was informed that GE had identified and verified four previously unreported errors in the GE13 LOCA

__ analysis for BNP (AR 2226, see also Reference 2.4.20).

6 11/17/00 Revised to incorporate 11/7/00 GE letter WHH:2000-073 "Revised 10 CFR 50.46 Error Report for Brunswick 1&2 SAFER/GESTR Analysis" (with associated 11/7/00 10 CFR 50.46 notification letter "Brunswick 1&2 SAFER/GESTR Analysis Errors -Rev. 1"). Also revised to incorporate NEDC-31624P Supplement 3 Revision 1 (the warranty reanalysis report for the work which identified the changes made in Revision 5 to this calculation).

7 3/17/01 Revised to incorporate GE-NE-J I103781-09-02P, "Brunswick Steam Electric Plant Units 1 and 2 ECCS-LOCA Evaluation for GE14," February 2001.

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET - Revision 11 Supervisor: George E. Smith Page 4of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Rev. Date {Revision Summary 8 6/7/01 Revised to incorporate 5/24/01 GNF letter WHH:2001-010 "10 CFR 50.46 Notifications for Brunswick 1&2," received 5/28/01. Letter transmits three notices: 2001-01, 2001-02, 2001-03. 1 9 5/15/02 Revised to incorporate GE-NE-A22-00113-27-01, "Brunswick Nuclear Plant Unit 1 and 2 Extended Power Uprate - Task T0407: ECCS-LOCA SAFER

/GESTR". This report documents the impact of EPU operation on PCT values.

10 6/23/03 Revised to incorporate seven notices: 2002-01 through 2002-05, 2003-01, and

._ 2003-03.

11 8/12/04 Revised to incorporate one notice 2003-05 (received May 14, 2004).

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith_ Page 5of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Table of Contents Page No.

List of Effective Pages ............................. 2 Revision Summary ............................ .3 Table of Contents7 List of Attachments .5 1 Purpose.6 2 References.7 3 Body of Calculation.11 3.1 Design Inputs.11 3.2Assurnptions.11 3.3 Computer Codes Used.11 3.4 Computers Used.11 3.5 Calculations.12 4 Conclusions.16 4.1 Summary of Results.16 4.2Precautions.Limitations.19..........................6 5 Scope of Verification .2 Attachments Title 0 Document Indexing Table 1 GE 1DCFR5..46 Analysis Information Transmittals 2 BNP SAFERIGESTR-LOCA ECCS Analysis Change/Error Summary 3 Design Verification 4 User Production and Controlled Library Maintenance Request

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 6 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 1 Purpose 1.1 Function The function of this design calculation is to document the BNP SAFER/GESTR-LOCA ECCS Analysis Change and Error Summary based upon information received from General Electric (GE) and the status of design changes implemented for Brunswick Units 1 and 2 through August 10, 2004.

The summary tables included in Attachment 2 document - in addition to PCT changes - the most recent information regarding maximum cladding oxidation, maximum hydrogen generation, coolable geometry, and long term cooling conditions. These parameters will not change appreciably unless PCT increases significantly. Each reload SRLR documents that the maximum cladding oxidation remains <1% and the maximum hydrogen generation <0.1%. This calculation is prepared in accordance with References 2.1.1 through 2.1.3 to satisfy 10CFR50.46 requirements and contains appropriate information for inclusion in the 10CFR50.46-required annual or 30-day NRC report.

This calculation applies the accumulated absolute value of PCT changes to the licensing PCT to satisfy 10CFR50.46 reporting requirements, and also applies the accumulated PCT change to the Upper Bound PCT (not a 10CFR50.46 requirement) to ensure that the conditions of the SER for GE's SAFERIGESTR are maintained. This Upper Bound PCT requirement serves as reasonableness test to ensure that the Appendix K assumptions remain bounding for the LOCA.

1.2 Background Although GE provided ECCS error notifications to PGN in 1990, 1991, 1992, and then ceased, PGN did not recognize its obligation to track and report the effect of changes or errors in LOCA methodology and application until 1996. GE provided the backlog of notices in response to PGN's request in July 1996, and the cumulative errors were evaluated by PGN to be less than 25 'F for BNPl-and 23 'F for BNP2. This evaluation was documented as a corrective action in Condition Report BNP 96-02802, initiated in September 1996. Note that the evaluation was not performed and verified as a design calculation. Annual reports from GE have been incorporated into the database since that time by Revisions 0 and 1 to this design calculation OB21-0112. Revision 2 incorporated an error notification and also included an expanded scope to incorporate the notices which were received prior to OB21-0112 into the design calculation. Revision 2 therefore includes References 2.4.1 through 2.4.15 in its Attachment 1. Revision 2 also includes Reference 2.3.7 as its Attachment 5. The scope of all subsequent revisions need therefore include only changes since the previous revision of.

OB21-0112 and any supporting change and error report references.

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith ___ Page 7of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 1.3 Current Notices The current revision of OB21-0112 incorporates one notice received from GE since the last calculation revision to support the annual report for the NRC (Reference 2.2.1). This design calculation, 0B21-0112, is being transmitted to BNP Licensing/Regulatory Programs to support the normal annual 10 CFR 50.46 report.

2 References 2.1 Procedures 2.1:1 REG-NGGC-0006, "Identification of Changes to (or Errors in) LOCA Evaluation Models or Applications According tolO CFR 50.46", Revision 2 2.1.2 EGR-NGGC-0003, "Design Review Requirements", Revision 9 2.1.3 EGR-NGGC-0017, "Preparation and Control of Design Analyses and Calculations",

Revision 1 2.1.4 NGGS-NFP-0009, "Nuclear Fuels Management and Safety Analysis Controlled Location File Transfer", Revision 0 2.2 Regulatorv 2.2.1 Letter from Edward T. O'Neil to U.S. Nuclear Regulatory Commission Document Control Desk, "BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS.

50-325 AND 50-324/LICENSE NbS. DPR-71 AND DPR-62 ANNUAL REPORT OF CHANGES AND ERRORS IN EMERGENCY CORE COOLING SYSTEM EVALUATION MODELS", Serial: BSEP 03-0107, July 9, 2003.

2.3 LOCA Analysis References 2.3.1 NEDC-31624P, "Brunswick Steam Electric Plant Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis (Revision 0)", September 1988.

2.3.2 Letter from E. G. Tourigny to L. W. Eury, "SAFER/GESTR-LOCA Analysis, Brunswick Steam Electric Plant, Units I and 2 (TAC Nos. 72854/72855)", June 1, 1989 (NRC-89401).

Transmitted NRC SER for NEDC-31624P, Revision 0.

2.3.3 NEDC-31624P, "Brunswick Steam Electric Plant Units I and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis (Revision 1)", February 1990. This report was not submitted to the NRC.

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith ___ Page 8of 18 Calculation

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10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 2.3.4 NEDC-31624P, "Brunswick Steam Electric Plant Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis (Revision 2)", July 1990.

2.3.5 Letter from Ngoc B. Le to L. W. Eury, "Revision of SAFER/GESTR-LOCA Analysis -

Brunswick Steam Electric Plant, Units 1 and 2 (TAC Nos. 77585 and 77586)", January 10, 1991 (NRC-91-018). Transmitted NRC SER for NEDC-31624P, Revision 2.

2.3.6 NEDC-31624P, Supplement 3, Revision 0, "Brunswick Steam Electric Plant Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis: Application to GE13 Fuel",

January 1996. Transmitted to NRC with B2C12 COLR. NRC SER not required since this is an application of an approved methodology, not a methodology change.

2.3.7 GE-NE-208-05-0393 (DRF-AOO-05316), "Low Pressure Core Spray Out-Of-Service for BSEP Units I and 2", September 1993. Not sent to the NRC, but is included as Attachment 5 to OB21-0112 Revision 2. Contains a comparison between SAFER02 and SAFER04 results.

2.3.8 NEDC-31624P, Supplement 3, Revision 1, "Brunswick Steam Electric Plant Units I and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis: Application to GE13 Fuel",

November 2000 (see calculation OB21-0199 for Reference 2.3.8 & its Owner Review).

2.3.9 GE-NE-J1 103781-09-02P, "Brunswick Steam Electric Plant Units 1 and 2 ECCS-LOCA Evaluation for GE14," February 2001 (see calculation OB21-0199 for Reference 2.3.9 & its Owner Review).

2.3.10 GE-NE-A22-00113-27-01, "Brunswick Nuclear Plant Unit 1 and 2 Extended Power Uprate -

Task Report T0407: ECCS-LOCA SAFER /GESTR", Revision 0, Class m, June 2001. The NRC SER for Tech Spec amendment 222 (transmitted May 31, 2002) indicated the NRC review & acceptance of this document.

2.4 Change and Error Report References 2.4.1 Letter from R. C. Mitchell to Director of Nuclear Reactor Regulation, "Reporting of Changes and Errors in ECCS Evaluation Models", June 13, 1990 (MFN 023-90).

2.4.2 Letter from P. W. Marriot to Office of Nuclear Reactor Regulation, "Reporting of Changes and Errors in ECCS Evaluation Models", March 12, 1991 (MFN 025-91).

2.4.3 Letter from S. J. Stark to Office of Nuclear Reactor Regulation, "Reporting of Changes and Errors in ECCS Evaluation Models", June 26, 1992 (MFN 058-92).

2.4.4 Letter from R. C. Mitchel I to Office of Nuclear Reactor Regulation, "Reporting of Changes and Errors in ECCS Evaluation Models", June 30, 1993 (MFN 090-93).

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 9 of 18 Calculation

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10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 2.4.5 Letter from R. C. Mitchell to Office of Nuclear Reactor Regulation, "Reporting of Changes and Errors in ECCS Evaluation Models", July 1, 1994 (MFN 088-94).

2.4.6 Letter from J. F. Klapproth to Document Control Desk (R.C. Jones, Jr.),"Reporting of Changes and Errors in ECCS Evaluation Models", June 24, 1995 (ME1N 087-95).

2.4.7 Letter from R. J. Reda to Document Control Desk (R.C. Jones, Jr.),"Reporting of Changes and Errors in ECCS Evaluation Models", December 15, 1995 (MNEN 278-95).

2.4.8 Letter from R. J. Reda to Document Control Desk (R.C. Jones, Jr.),"Reporting of Changes and Errors in ECCS Evaluation Models", February 20, 1996 (MFN 020-96).

2.4.9 Letter from R. J. Reda to Document Control Desk (R.C. Jones, Jr.),"Reporting of Changes and Errors in ECCS Evaluation Models", June 28, 1996 (MEN 088-96).

2.4.10 Letter from G. R. Hull to Mike DeVoe," Reporting of Changes and Errors in ECCS Evaluation Models", July 16, 1996. (GRH:96-088).

2.4.11 Letter from G. R. Hull to Mike DeVoe, "Reporting of Changes and Errors in ECCS Evaluation Models", July 22, 1997. (GRH:97-073).

2.4.12 Letter from R. J. Reda to Document Control Desk (J.E. Lyons),"Reporting of Changes and Errors in ECCS Evaluation Models", June 27, 1997 (MFN 029-97).

2.4.13 Letter from G. A. Watford to Document Control Desk (T.E. Collins),"Reporting of Changes and Errors in ECCS Evaluation Models", June 30, 1998 (MFN 032-98).

2.4.14 Letter from W. H. Hetzel to A. T. Kremer,"IOCFR50.46 Error Notification - Brunswick Units 1 and 2", January 27, 1999 (WHH:99-007).

2.4.15 Letter from W. H. Hetzel to A. T. Kremer, "10CFR50.46 Error Notification - Brunswick Units 1 and 2", February 10, 1999 (WHH:99-011).

2.4.16 Letter from William H. Hetzel to A. T. Kremer, "10 CFR 50.46 Notification Letter", June 25, 1999 (WHH:99-044).

2.4.17 Letter from Ann T. Kremer to Dan Pappone, "50.46 GE Notification Letter on Licensing Basis PCTs and Applicability to Brunswick Nuclear Plant", July 26, 1999 (NF-99A-0145).

2.4.18 Letter from G. A. Watford to Document Control Desk (J. L. Wermiel), "Summary of Changes and Errors in ECCS Evaluation Models", June 30, 1999 (MFN-004-99) [cover letter from William H. Hetzel to A. T. Kremer, July 28, 1999 (WHH:99-053)].

Preparer: Tom Dresser J Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 10 of 18 Calculation

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10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 2.4.19 Letter from G. A. Watford to Document Control Desk (J. L. Wermiel), "Summary of Changes and Errors in ECCS Evaluation Models", June 30, 2000 (FLN-2000-06)

[cover letter from William H. Hetzel to A. T. Kremer, June 30, 2000 (WHH:2000-044)].

2.4.20 Letter from W. H. Hetzel to A. T. Kremer, "IOCFR50.46 Error Report for Brunswick 1 & 2 SAFER/GESTR Analysis", August 9,2000 (WHH:2000-053).

2.4.21 Letter from W. H. Hetzel to Mike Blom, "Revised 10 CFR 50.46 Error Report for Brunswick 1&2 SAFER/GESTR Analysis", November 7, 2000 (WHH:2000-073) 2.4.22 Letter from W. H. Hetzel to Mike Blom, "10 CFR 50.46 Notifications for Brunswick 1&2",

May 24, 2001 (WHH:2001-010). Letter transmits 10 CFR 50.46 Notification Letters 2001-01, 2001-02, and 2001-03.

2.4.23 Email from Glenn A. Watford to Michael Blom,

Subject:

"10 CFR 50.46 Notification --2002-01 - SAFER Core Spray Injection Elevation /2002 SAFER Bulk Water Level Error -

Brunswick", 6/13/2002 8:46 P.M.

2.4.24 Email from Glenn A. Watford to Michael Blom,

Subject:

"10 CFR 50.46 Notification - 2002-03, 2002-04, 2002-05", 8/26/2002 7:13 P.M.

2.4.25 Email from Margaret Harding to Michael Blom,

Subject:

"RE: 10 CFR 50.46 Notification -

2003 Progress Energy", 5/16/2003 3:26 P.M.

2.4.26 Email from Margaret Harding to Michael Blom,

Subject:

"10 CFER 50.46 Notification -

2003 Progress Energy", 5/16/2003 3:36 P.M.

2.4.27 Email from Michael Blom to Tom Dresser et al,

Subject:

"Emailing:

IOCFR5046_2003-05-Progress Energy.pdf", 5/14/2004 2:28 P.M

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 11 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 3 Bodv of Calculation 3.1 Design Inputs 3.1.1 The cumulative PCT impact (including estimated licensing PCT) is currently not tracked by break size or phase of accident, but is considered to be cumulative to the limiting break and phase documented in the base analysis. This practice will not be changed unless separate PCT errors/changes tracking become appropriate in the future (for example, to track errors in portions of the LOCA analysis not bounding at BNP).

3.1.2 The current error notice (References 2.4.27) was received May 14, 2004. The PCT impact of this error is insignificant such that 10CFR50.46 does not require its reporting until the next scheduled annbal NRC report. Error notice 2003-02 was specific to TVA plants and 2003-04 was specific to Vermont Yankee, and so the correct sequence of notices tracked for BNP is 2003-01, 2003-03, 2003-05. There have not been any notices issued to date in the 2004-xx sequence.

3.1.3 This calculation is prepared in accordance with References 2.1.1, 2.1.3 and 2.1.4, and verified in accordance with Reference 2.1.2.

3.2 Assumptions None 3.3 Computer Codes Used None 3.4 Computers Used None

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith . Page 12of 18 Calculation

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10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 3.5 Calculations 3.5.1 Records Storage The historical information for the BNP SAFER/GESTR-LOCA ECCS Analysis Change and Error Summary is compiled as two linked tables, because the number of columns of data associated with each analysis/error notice is large. Each analysis/error notice is described in the same row in either table. This data is maintained in the NFM&SA DOS Controlled Library as:

PROGRAMS on 'NT000229'P:\site\HNP Apps\ControI\data\bwr\barf\ DC OB21-0112 Rev. OJune_2003.doc The pertinent information from this file and supporting references were most recently reported by BNP to the Nuclear Regulatory Commission in Reference 2.2.1.

The same general format is preserved for the update of the historical summary with the current analysis. The information received from GE through Reference 2.4.27 was incorporated into the historical file and an entry was added for the specific change on the summary tables. There were no design changes to Brunswick Units 1 and 2 which had an impact on the Change and Error Summary at the time of this update (the UB PCT limit change from 16000 F to 2200F will be associated with the licensing of MELLLA+). The revised summary including the current analysis result change (Entry No. 36) is provided in Attachment 2 and electronically stored as part of the file containing this design calculation in:

NGGSHARE on 'NT000230'N:\fuels\BNP LOCA\IOCFR50.46\DC OB21-0112 Rev.1 lAugust 2004.doc prior to transfer to the same controlled library. Attachment 4 illustrates the form (User Production and controlled Library Maintenance Request) to effect this transfer, which may be approved, completed and/or verified subsequent to the completion of this calculation.

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 13 of 18 Calculation

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10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 3.5.2 10CFR50.46 Notification: 2003-05 This error correction results in no (0 0F) PCT increase for GE13 and GE14 at BNP.

A new heat source during the LOCA event has been postulated. This heat source involves the recombination of hydrogen and oxygen within the fuel bundle during the core heatup. The additional heat will raise the temperature of the steam heat sink in the bundle, resulting inma potential increase in the peak cladding temperature and local oxidation. This recombination is spontaneous at temperatures above approximately 900'F. The hydrogen is generated by the steam-zirconium reaction during heatup. The oxygen enters the vessel either as a dissolved gas in the ECCS water or through the break when the vessel fully depressurizes and draws the containment noncondensible gases back into the vessel. The current LOCA evaluation models do not include this new heat source.

The impact of hydrogen-oxygen recombination was incorporated by increasing the heat generated due to metal water reaction. The evaluations were performed assuming that recombination occurs within the fuel channels at the cladding surface. The additional source of oxygen from the containment will only contribute to increasing the PCT.for the non-jet pump plants. This is due to the fact that the oxygen from the containment enters the vessel late in LOCA event, after the core has reflooded for jet pump plants.

Preparer: Tom Dresser . Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith . Page 14 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update

4. Conclusions 4.1 Summary of Results Tables 1, 2 and 3 contain pertinent results from the current analysis to support a BNP 10CFR50.46 annual NRC report. The 2002 annual report included only the impact of extended power uprate, an analysis that included all outstanding changes & errors then reported, that was reviewed and accepted by the NRC (Reference 2.3.10). Therefore the accumulated absolute value of errors was reset at zero prior to Revision 10 of OB21-0112 in 2003. Table 1 lists the error notices, tracks the estimated Licensing PCT, and accumulates the cumulative absolute value of all errors since the most recent NRC report (i.e., only notice 2003-05). Table 2 presents the most recent analyzed Licensing PCT, the most recent reported (evaluated) Licensing PCT, the current evaluated Licensing PCT and the change in FICT since the last report. Table 3 presents an Upper Bound PCT summary corresponding to Table 2.

The estimated Upper Bound PCT is being tracked by PGN not directly in support of 10CFR50.46, but to ensure the SAFER/GESTR-LOCA SER conditions are being met. Unless specific direction to the contrary is provided by GE, the tracking is conservatively performed in exactly the same manner as the licensing basis PCT is tracked. The absolute value of Appendix K DBA APCT is cumulatively summed for Upper Bound PCT as well as Licensing Basis PCT impact assessment. The SAFER/GESTR SER limit remains 1600 0 F until the MELLLA+ license amendment is approved, at which time it will become 2200'F.

The UFSAR was updated per LDCR 02FSAR-031 (EPU Changes) to reflect reference updates. The table in UFSAR 6.3.3.5.3 should be updated if the evaluated Licensing PCT approaches a significant difference (50 0F) from the temperatures reported in the UFSAR (currently 1710 0 F for GE13, 1580 0 F for GE14).

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith . Page 15 of 18 Calculation

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10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Table I BNP SAFER/GESTR-LOCA ECCS Analysis Change/Error Summary Estimated BNP Cumulative BNP Change Notice Period Change or GEBWR Licensing PCT Licensing PCT Is BNP Licensing PCT or Error Or Covered Error Estimated Impact and Change Change Greater than 50'F?

Notice Docu- Description Licensing Estimated PCT ment . . PCT Impact Date GE13 GE14 GE13 GE14 Incremental Cumulative 50.46 May, througb Additional generically 0'F 00F 15°F 20 0 F No No Notice 2004 8/10/04 beat source not reported Ul <U2 UI <U2 2003-05 from Oxygen and Hydrogen <17329F <1567OF recombination Table 2 BNP Licensing PCT Change Summary Through 8110/04*

Fuel Type Most Recent Licensing (most recent LOCA PCT Reported in a Current Estimated Change from reported analysis Licensing PCT) LOCA Document Licensing PCT Licensing PCT Submitted to the NRC (Analysis or Notice)

GE13 <1717OF <1732oF 15°F (Ref. 2.3.8: 1710*F) (Ref. 2.3.10)

GE14 <1557oF <1567oF 100F (Ref. 2.3.9: 15800F) (Ref. 2.3.10)

Preparer: Tom Dresser ., Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E.Smith Page 16 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Table 3 BNP Upper Bound PCT Chan e,Summary Through 8/10/04*

Upper Bound PCT Fuel Type Corresponding to Current Estimated. Change from Previous (most recent LOCA analysis Table 2 Most Recent Upper Bound PCT Upper Bound PCT Upper Bound ACT) Submitted to the NRC GE13 <1567oF <1582°F 15SF (Ref. 2.3.8: 1560*F) (Ref. 2.3.10)

GE14 <1487oF <14970F 10OF (Ref. 2.3.9: 14900F) (Ref. 2.3.10)

• BNP LOCA Results presented for Unit 2, which bounds Unit 1

Preparer: Tom Dresser . Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 17 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 4.2 Precautions/Limitations 4.2.1 The results provided in this design calculation apply to the period ending August 8, 2004.

4.2.2 Once accumulated change/error exceeds 50'F, each new error or change in the SAFERIGESTR-LOCA model will continue to require a 30-day NRC notification under 10CFR50.46 while the accumulated absolute value of reported errors remains above 50'F (that is, until results are reported from a new calculation performed with an acceptable evaluation model). The accumulated error can be re-baselined to zero once the new calculation has been submitted to the NRC.

4.2.3 The UFSAR should be updated when its value differs by a "significant" amount (50'F) from the evaluated licensing basis PCT. Once the UFSAR is updated to remove references to the PCT of fuel types no longer in use at BNP, tracking of those fuel types in this calculation should be discontinued (although their history will remain in the Attachment 2 tables).

4.2.4 The Upper Bound PCT must be monitored against its acceptance criterion of 16000 F to ensure that the conditions of the SAFER/GESTR-LOCA SER are satisfied. Remaining margin to this criterion is much less than that to the 10CFR50.46 Licensing Basis PCT, however the NRC has approved and BNP will implement with MELLLA+ a new criterion of 22000 F.

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 18 of 18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update 5 Scope of Verification The following is a suggested minimum verification scope for this calculation:

5.1 Verify the accuracy of any hand calculations used to incorporate errors from the current reporting period into the historical summary.

5.2 Perform a Design Verification Review of this calculation in accordance with Reference 2.1.2.

Document all findings and resolutions on the EGR-NGGC-0003 Record of Lead Review form (current form included in Attachment 3).

Preparer: Tom Dresser J Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 0-1 of 0-2 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Attachment 0 Document Indexing Table C

DOCUMENT INDEXING TABLE CALCULATION NO. OB21-0112 PAGENO. lof 1 REVISION 11 Document ID Number Function Relationship to Type (e.g., Caic. No., (i.e., INfor Design Inputs or References, Caic.

(i.e. Caic Dwg. No., Equip. OUT for affected Documents) (e.g., Design Tag No., Procedure Input, Dwg, Tag, No., Software Name Input, Procedure, & Version) Assumption Software). Basis, Reference, Document Affected by Result)

Federal 10CFR50.46 IN- "Acceptance Criteria For Emergency Core Controlling Regulation Cooling Systems For Light-Water Nuclear Regulation Power Reactors" FSAR UFSAR 6.3.3.5.3 OUT- "Confirmation of Emergency Core Documents Cooling Systems with 10CFR50.46"/ "Liquid License Basis Line Breaks" PCT Results Design NEDC-31624P, IN- "Brunswick Steam Electric Plant Units 1 Input Document Revision 2 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis (Revision 2)"

Design NEDC-31624P, IN- "Brunswick Steam Electric Plant Units 1 Input Document Supplement 3, and 2 SAFER/GESTR-LOCA Loss-of-Coolant Revision 1 Accident Analysis: Application to GE13 Fuel" Design GE-NE-208-05-0393 IN- "Low Pressure Core Spray Out-Of-Service Input Document (DRF-AQO-05316) for BSEP Units 1 and 2" Calculation OB21-0112 (previous IN- "10CFR50.46 SAFER/GESTR-LOCA ECCS Input revisions) Anaysis Update" Calculation OB21-0199 IN- 'ECCS Analysis Results" Input (subsequent to (Revision 1 consolidates the design basis Revision 0) documentation which provides input to this calculation. It contains NEDC-31624P, Supplement 3, Revision 1 and the associated Owners Review).

Design GE-NE-J1103781 IN- "Brunswick Steam Electric Plant Units 1 Input Document 02P, Revision 0 and 2 ECCS-LOCA Evaluation for GE14,"

February 2001" Design GE-NE-A22-00113- IN- "Brunswick Nuclear Plant Unit 1 and 2 Input Document 27-01, Revision 0 Extended Power Uprate - Task Report T0407:

ECCS-LOCA SAFER /GESTR"

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET . Revision 11 Supervisor: George E. Smith Page 2-1 of 2-18 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update Attachment 2 BNP SAFER/GESTR-LOCA ECCS Analysis Change/Error Summary

OB21-01 12 Revision I I Page 2-2 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change in Error In Change In Error In Other?

No. Document Covered Model? Model? Application? Application? (See Date Note 4) 1 Base LOCA Analysis (9/88) NMA Change to SAFER/GESTR-LOCA Methodology (NEDE 23785, Yes Not Yes No N/A SAFER02)

NEDC 31624P Rev 0 Calculated results:

Unit I Unit 2 LUcensing Basis PCT 1533 OF (GE7) 1537 °F (GE7)

Peak Local Oxidation 0.299% (GE7) 0.306% (GE7)

Metal-Water Reaction 0.046% (GE7) 0.036% (GE7)

Upper Bound PCT 13530 F (GE7) 1390 0 F (GE?)

2 NEDC 31624P Rev 1 (2/90) N/A This revision was to correct documentation errors (the reported value No No No No N/A of an input parameter) found in Revision 0. However, Revision I contained publication errors and was never distributed for use. NO CALCULATIONS-WERE MADE.

3 NIFN 023-90 6/13/90 10/17/88 Codingerrors in SAFER -energybalance in unheated bottom node, No Yes No No N/A modeling Or steam quenching by the LPCI system, calculation or the 6/13190 bypass void profile.

4 NEDC 31624P Rev 2. (7/90) N/A Corrected publication errors in Revision 0. NO CALCULATIONS No No No No N/A WERE MADE.

5 MFN 025-91 3/12/91 6/13/90- No errors or changes. GE notified NRC that they are in the process Or No No No No N/A 3/12/91 adapting SAFER1GESTR methodology to accommodate GEl I.

6 MFN 058-92 6/26/92 3/12/91- Considered N/A prior to Revision 2 orOB21-01 12, currently No No Yes No Yes 6261/92 considered change in application.

See Nnte 5.

OB21-0112 Revision I11 Page 2-3 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change In Error In Change In Error In Other?

No. Document Covered Model? Model? Application? Application? (See Date Note 4) 7 MFN 090-93 6/30/93 6t26192- Two minor coding erors; improper upper plenum now initialization No Yes Yes No Yes 6/30/93 and sign error in a pressure drop calculation for the top of the hot channel.

Noted that model sensitivity to small input parameter changes could be greater than that originally reported in NFM 058-92. Variation could be greater than +A-5O IF for some BWR/4 plants with LPCI injection into the lower plenum (total variation of less than 85 OF for most cases but with one case showing a range oa102 IF).

Also noted Ihat the identified sensitivity is related to the explicit numerical treatment in SAFER combined with rapid and simultaneous variations Of multiple parameters. Sensitivity will be limited through better control Oatime steps in the computations.

PGN IOCFR50.46 evaluations prior to OB21-0112 Rev. 2 concluded that "The second and third paragraphs above do not apply to BNP because BNP analyses have not been rerun." It is currently recognized that this notice is stating that better computational controls were implemented to maintain the sensitivity described in notice MFN 058-92 to +/1 50 "F.

(see note 5)

OB21-01 12 Revision I11 Page 2-4 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change in Error In Change In Error In Other?

No. Document Covered Model?

M Model? Application? Application? (See Date Note 4) 8 LPCS-OOS Report Sept. 1993 N/A GE Document GE-NE-208-05-0393, DRF-AO0-05316, 'Low Yes No Yes, No N/A Pressure Core Spray Out-of-Service for BSEP Units I and 2. Water Level Section 3.2 establishes a baseline between the current version of SAFER (SAFER04) and the original BSEP licensing basis version of SAFER (SAFER02). SAFEER04 includes several modeling improvements relative to SAFERO2.

This baseline comparison also includes several ECCS parameter relaxations relative to the licensing basis (L3=LLI changed from 519.5 to 517 and LI=LL3 changed form 369.5 to 358.0). These water level setpoint changes impact the PCT by only approximately I TF and therefore this baseline calculation gives a very good indication of the effect of modeling changes and errors on the licensing basis PCTs.

The results indicate that with the updated version of SAFER, the licensing basis PCT for BNP2 GE7 fuel increases from 1537 T to 1550 IF. (Approximately I IF of this increase is due to the reduced water level setpoints assumed.)

The results indicate that with the updated version of SAFER, the upper bound PCT for BNP2 GE7 fuel increases from 1390 "F to 1440

.F. (Approximately I 'P of this increase is due to the reduced water level setpoints assumed.)

9 MIFN 088-94 7/1/94 6/30/93- No changes or errors. No No No No N/A 7/1/94 10 MFN 087-95 6/24/95 7/1194- No changes or errors. No No No No N/A 6/24/95 MFN 278-95 12115/95 7/1/94- Revises NFM 087-95. Pointed out that in March of 1995 a domestic No No Yes No N/A 12/15/95 utility asked about the impact of the RPV bottom head drain (D3JD) on LOCA evaluations. GE stated that the BlID impact is believed to be less than 10 'F.

OB21-0112 Revision II Page 2-5 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change In Error In Change In Error In Other?

No. Document Covered Model? Model? Application? Application? (See Date Note 4) 12 NEDC 31624P (1/96) NIA BNP GE13 LOCA analysis (NEDC-23785, SAFER04). Yes No Yes No No Supplement 3 Yes. for GE Rev. 0 Relative to the base analysis, this analysis was done with a revised 13 BIIHD version oathe SAFER model.

I Calculated results:

GE13 Licensing Basis PCT 1535 OF Peak Local Oxidation 0.27% 0.27%

Metal-Water Reaction 0.036% 0.036% (GE7)

Upper Bound PCi' 1448 OF Summary onBNP ECCS Results as of BIC11 and B2C12 Unit I Unit 2 licensing Basis PCT 1535OPGE13 1537OF GE7 Peak Local Oxidation 0.299% GE7 0.306% GE7 Metal-Water Reaction 0.046% GE7 0.036% GE7 Upper Bound PCT 1353@F (GE7) 1390 0F (GE7)

Upper Bound PCIT 1448 OF GEI3 1448 OF GEI3 Note that this analysis did not attempt to model BIID eftects.

Therefore, the PCT impact described in NFM 278-95 applies to the GE 13 analysis. Also the 500F uncertainty described in MFN 058-92 applies to all fuel.

13 MFN 020-96 2/20/96 12115/95 Revises NFM 278-95. Just adds a drawing to more clearly describe NIA N/A N/A N/A N/A

-2/20/96 the BIIHD concern. No change in estimated PCT impact.

14 MFN 088.96 6/28/96 2/2/96- No changes or errors but some applications used the wrong number of No No No Yes N/A 6/28/96 fuel rods for GE9/10/111/12/13 (designs containing large water rods).

It has been confirmed that this notice does not apply to BNP LOCA evaluations (see GRH 96-088).

15 MFN 029-97 6/27/97 6128/96. No changes or errors. No No No No N/A 6/27/97 16 MFN 032-98 6/30/98 6/28/97- No changes or errors. No No No No N/A 6/30/98

OB21-0112 Revision II Page 2-6 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change In Error In Change In Error In Other?

No. Document Covered Model? Model? Application? Application? (See Date Note 4) 17 W1V1:99-007 1/27199 711/98- Notification that +/- 50F for sensitivity to small input parameter No No No Yes No (supplemented by I 27/99 changes for BWR14 plants with LPCI injection into the lower plenum W(splen99-01t1b (see MFN-090-93) as well as lo0 F BHD error (see MFN-020-96) not daedIII 0199. included In NEDC 31624P Supplement 3 Rev. 0 analysis.

dated 2/10/99)I (see notes 1. 5) 18 WHH:99-044 6M5/99 1/27/99. CCFL error, for jet pump plants including GE10 fuel, SAFER counter No No No Yes No 6/25199 core flow limiting coefficients not matched to flow area (upper tie (suppementd byplate area used but top spacer is flow limited). Impact is +5IF to +25 (supplemented by peor affected plants. Both letter and attached table identify NF-99A-0145, Brunswick Units I & 2 as not affected.

dated 07/26/99)

Supplemental letter clarifies basis for NA determination.

19 MFN-004-99 6/30/99 7/1/98- For non-jet pump plants, waterrod diameter not transferred between No No No Yes No 6130/99 software routines.

For jet pump plants including GE10 fuel, notice for CCFL error described above. Impact is +5IF to +25 TF for affected plants.

20 WHII1:2000-044 6/30/00 7/1/99- NA for BNP. Error in vessel heat slab model heat transfer areas for No Yes No No No 6/30/00 BWR/6 design only.

21 W{H1:2000-053 8/9/00 7/1/00 - +50F for Heat Conduction Time Step Size No No Yes Yes No 8/08/00

+IO for GESTR Fuel File Interpolation No Yes No No No

+900F for LPCI Condensation No Yes No No No

+21F for Low Water Level Setpoint No No No Yes No 22 WHH: 000-073 l 17/00 89/00 - Same deltas as prior notice WHH:2000-053 No Yes Yes Yes No 1(7/00 (revised new estimates for UB PCT and LB PCT) 23 NEDC-31624P, November, through New LOCA calculation for GE113 fuel PCT baseline No Yes Yes Yes No Supplement 3, Rev. 1 2000 117n/00

OB21-0112 Revision I11 Page 2-7 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change In Error In Change In Error In Other?

No. Document Covered MIodel? lModel? Application? Application? (See D ate __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _N ote 4) 24 GE-NE-JI 103781-09-02P February, through Original BNP LOCA calculation for GE14 fuel Yes No Yes No No 2001 2/28/00 25 I(t)FR50.46 Notification May. 2001 through LPCI Condensation Error as noticed in WHH:2000-053 and No Yet No No No Letter 2001-01 5/24/01 WHH:2000-073 26 10CFR50.46 Notification May, 2001 through Impact of SAFER Pressure Rate Inconsistency Error on No Yes No No No Letter 2001-02 5/24/01 27 1 CFR50.46 Notification May, 2001 through 3NP 0E14 Analysis Dryout Time and Initial Pressure Errors No No No Yes No Letter 2001-03 5124/01 28 GE-NE-A22-00113-27-01 June 2001 Through ECCS-LOCA analysis to evaluate EPU (2923 MNVt) impact on PCT No No Yes No No 5/15/02 29 IOCFR50.46 Notification June, 2002 Through SAFER Core Spray Injection Elevation Error No No No Yes No Letter 2002-01 6/01/02 30 IOCFR50.46 Notification June, 2002 Through SAFER Bulk Water Level Error Impact on PCT No No No Yes No Letter 2002-02 6/01/02 31 10CFR50.46 Notification August, Through GESTR Input File Interpolation Error Impact on PCT No Yes No No No Letter 2002-03 2002 8126/02 32 IOCFR50.46 Notification August, Through SAFER04 Computer Platform Change Impact on PCT Yes No Yes No No Letter 2002-04 2002 8/26/02 33 10CFR50.46 Notification August, Through NVEVOLSI Volume Error Impact on PCT No No No Yes No Letter 2002-05 2002 8/26/02

I 0B21-0112 Revision 11 Page 2-8 of 2-18 Entry Change or Error Notice Notice or Period Change or Error Description Change In Error In Change In Error in Other?

No. Document Covered .Model? Model? Application? Application? (See Date _ _ _ _ __ _ _ _ _ _ _ _ _ _ __ Note 4) 34 IOCFR50.46 Notification May, 2003 Through SAFER Levceiolume Table Error Impact on PCT No No No Yes No Letter 2003-01 5/06103 35 IOCFR50.46 Notification May. 2003 Through SAFER Initial Separator Pressure Drop Error Impact on PCT No No No Yes No Letter 2003-03 5/06103 36 IOCFR50.46 Notification May, 2004 Through New llydrogen-Oxygen Recombination Heat Source No Yes No Yes No Letter 2003-05 8/10/04

0B21-0112 Revision 11 Page 2-9 of 2-18 Entry GE BWR Is there Estimated BNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing performance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? oloth (See note 3) & than +/ 50 IF? (See note 3) greater than (See Note 2 tor Estimated (See Note 1) 50°F? definition of Licensing PCT (See Note I) Impacted.) _ _ _

N/A Yes Approx. -660 °F Yes Approx. 660 IF Yes No Yes, 0NP 03/29/89 Switch to Switch to NRC SER Best Estimate Best Estimate issued 06/01/89.

LOCA Method. LOCA Method.

2 NMA No NMA No NMA No No No, not required. N/A Ul 1533°F Gi.7 Resetby U2 1537 °F GE7 06/01/89 SER

+20 °F to Yes Unknown. assume Yes 100 OF Yes No Yes. GE 06/13/90

-1()0 F +100 F for error accumulation and

+20 F fior evaluation oaPCT impact Ul 1633 OF GE7 U2 1637 OF GE7 4 N/A No No No 100 °F Yes No Yes, BNP 09/090 Ul 1633°F GE7 NRCSER U2 1637 OF GE7 issued 01/10/91.

5 N/A No No No 100 F Yes ' No Yes, GE 03/12/91 U1 1633 °F GE7 U2 1637 OF GE7 6 less than Yes N/A No 150 OF Yes No Yes, GE 06/26/92

+/-50 OF Ul 1683 OF GE7 U2 1687 OF G1.

0B21-0112 Revision II Page 2-10of 2-18 Entry GE BWR Is there Estimated BNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing performhance By GE, IBNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/. 50 °F? (See note 3). greater than (See Note 2 for Estimated (See Note 1) 50 0 F? definition or Licensing PCT (See Note 1) Impacted.)

7 +/5 0P Yes Unknown, assume No 155 OF Yes No Yes GE 06/30/93

+5 °F (see note 5)

Ut 1688 'F GE7 U2 1692 OF GE7 8 NMA Yes Licensing PCT No 63 OF Yes No No NMA increase of 13 oF relative to base Cumulative analysis for impact change reduced or errors noted in from 155 OF to NIPN 023-90 63 IF based on (Entry 3) and MFN revised estimate 090-93 (Entry 7). of prior effects obtained from Corresponding the Lucs.oos Upper Bound PCT Report.

increase of 50 F Corresponding for Entries 3 and 7. Upper Bound PCUT cumulative 50 0F from MF change reduced 058-92 (Entry 6) from 155 IF to remains. 100 TF based on revised estimate UI 1596OF GE7 of prioreffects 2 160 OFobtained from the LPCSOOS Report.

9 N/A No N/A No 63 F Yes No Yes, GE 07/01/94 100 PFUpper U11596 OF GE7 Bound PCT U2 16000 F GE7 10 N/A No N/A No 63 F Yes No Yes, GE 06/24/95 1t00 F Upper UI 1596 OF GCE7 Bound PCT U2 1600 OF GE7

OB21-0112 Rcvision II Page 2-1 1 of 2-1 8 Entry GE BWR Is there Estimated RNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing pertormance By GE, BNP, or PCT Impact Impact ? Impact impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/ 50 °F? (See note 3) greater than (See Note 2 far Estimated (See Note 1) 50°F? deflnition of Licensing PCT (See Note 1) Impacted.)

10 °F Yes Unknown, assume No 73 OF Yes No Yes, GE 12115/95 10O°F 110 °Upper Bound PCT Ul 1606°F G67 U2 1610 °F GE7 12 N/A Yes Unit I licensing No 73 °F GE7 Yes No No N/A basis PCT 60 IF GEI 3 increased by 2 IF Errors have not relative to original Upper Bound been reported GE7 calculations PCT. but the GE133 but no increase Supplement to relative to the 110 OF GE7 the base LOCA current estimated 60°FGE13 report was GE 7 PCT. provided to the NRC with the GE13 Upper B2C12 COLR, Bound PCT SRLR, and cycle increases 58 IF to specific LOCA 1448 IF relative to repor.

original GE7 UB.

10 IF increase for GE13 due to the BfD issue.

50 °F increase for GE13 due to the Entry 6(MFN 058-92) issue.

Ul 1606°F GE7 U2 1610°F 6E7 UI 1595°F GE13 U2 1595 OF GE13

OB21-0112 Revision I11 Page 2-12 of 2-18 Entry CE BWR Is there Estimated BNP Is limiting BNP Cumulative Is cumuiltive Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNr Licensing performance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Bloth (See note 3) & than +/- 50 OF? (See note 3) greater than (See Note 2 for Estimated (See Note 1) 50°F? definition of Licensing PCT (See Note 1) Impacted.)

13 N/A N/A N/A 7300F GE7 Yes No Yes. GE 02/20/96 13N/A 60 FGE13 Ul 1606°F GE7 U2 1610 °F GE7 Upper Bound POT:

.Ul 1595°F GE13 110 OFGE7 U2 1595 OP GE13 60 0FGE13 14 less than No N/A N/A 73 IF GE7 No No Yes, GE 06/28/95 30 °F 60°FGE13

. 1606°F GE7 U

U2 1610 OF GE7 Upper T ound PCT:

Ul 1595F GE13 110°FGE7 U21595°F GE13 60°GE13 15 N/A No N/A N/A 73 °FGE7 No No Yes, GE 06/27/97 60 FGE13 U 1 1606 OF GE7 U2 IGIO0 °F GE7 .Upper Bound PCT:

II1 1595SOF GE13 112 i595 °F GEi3 IlO0 FGE7 60°FGE13 16 N/A No N/A N/A 73 0IF GE7 No No Yes, GE 06/30198 60 PGE13 Ul 1606 °F GE7 U2 1610°F GE?7 Upper Bound 1111595 OF GE13 l0FH U2 1595 'F GE13 110 GB7 60 OF GE13

OB2 1-0 112 Revision I11 Page 2-13 of 2-18 Entry GE BWR Is (here Estimated BNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing perrormance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +1. 50 OF? (See note 3) greater than (See Note 2 for Estimated (See Note 1) 50OF? definition of Licensing PCT (See Note I) Impacted.)

17 less than Yes This notice results Yes 73 OF GE7 Yes No To bt reported by To be reported 60°F in additional 50°F See Note 5 60 0F GE13 02/26/99 by PGN by 02126199 (10°F ror accumulated PCT. by PGN tlD already Table tracks this Upper Bound included by 50 0 F starting in PCT:

PGN) Entry 6. 110 OF GE7 See Note 5 60FG2E13 UI 1606 FGE7 U2 1610°F GE7 Ul 1595°F GE13 U2 1595 OF GEI3 18 +5F to No N/A No 73 OF GE7 Yes No To be reported To be reported

+25F 60 F GE13 by PGN in by PGN in U1 1606 °FGE7 annual notice annual notice U2 1610 OF GE7 UpperlBound PCT':

Ul 1595°F GE13 . 11 0°FGE7 U2 1595 OF GE13 60°FGE13 19 +5OF to No N/A No 73 OF GE7 Yes No Yes. GE. 06/30/99 0

+25°F 60° FGE13 U211606FGC7 To be reported To be reported U2 1610 °F U2 GE7 GE7PCIT:

110 O Upper Bound by PGN in by PGN in annual notice annual notice Ul 1595 OF GE13 I10 F GE7 U2 1595 OF GE13 600FGE13 20 0°F to No N/A No 73 OF GE7 Yes No Yes, GE. 06/30/99 45@p 60 OFGE13 U 1 1606 OF GE7 To be reported To be reported U2 1610°F GE7 Upper Bound by PGN in by PGN in PCT.:

annual/30 day notice annuaV30 day U2 1595SF GE13 0°OFGE7 notice U2 1595 OF GE13 60@OF GEI3

oB21-0112 Revision I11 Page 2-14 of 2-18 Entry GE B\VR Is there Estimated BNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing performance By GE, BNP, or PCT Impact Impact ? Impact - impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/-50 F? (See note 3) greater than (See Note 2 ror Estimated (See Note 1) 50°F? deflnition or Licensing PCT (See Note 1) Impacted.)

21 +5°F for Yes +98°F total Yes 171°FGE7 Yes No YesAGE. 06/30/00 Heat 158F GE13 Conduction Time Step Ul 170481 GE7 Reported 08/29/00 Size U2 17080F 0137 Upper Bound by PGN in Ul 1693°F GE13 208°FGE7

+1°Ft or Yes U2 1693°F GE13 158F GE13 GFSTR Fuel FIle Interpolation

+900 1Ffor LPCI ye Condensation

+2°F for Low Yes Water Level Setpoint 22 Same No NA No +171°FGE7* Yes No Reported 127/00 via 0

changes & (included Ul1 1704 F GE7 +158°FGE13 by PGN in SSEP delta-PCls by day notice 00-0165 as entry 21 entry 21) U2 1708QP0GE7* 30 dyntc (revised new Ut 16930 FGE13 estimates for U2 1693°F GE133 UB PCr and LB PCT) .

01321-0112 Revision I I Page 2-15 of 2-18 Entry GE BVR Is there Estimated IINP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing perrofmance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/. 50 IF? (See note 3) greater than (See Note 2 ror Estimated (See Note 1) 50°F? definition ot Licensing PCT (See Note 1) Impacted.)

23 New LOCA Yes New GE013 PCT No Yes No Repqrted 12/7J00 via calculation calculation to zero by PGN in DSEP for GE13 accumulated error LOCA calculation 00-0165 baseline update notice Ui 174FGE7+171iPGE7*

U2 1708*FGE7*

GE13: Ul < U2 15FG-3 c1710°F111 175°FGE13'

<1710OF 24 New LOCA Yes GE13: UI < U2 No 0°F No No Reported by PGN via 3/16/01 per calculation <1710OF for btGE13 typical reload BSEP for GE14 andGE14 licensing update 01-0029 rtul notice 3GE14:

UI < U2 (no earlier fuel

<158(OF designs remain in use) 25 Generically No GE13: Ul < U2 No 0°F No No Yes, GE. 06/30/00 0 to +220°F (included <17100F forboth GE13 for LPCI by and GE14 Reported 7/11/01 via CoGENd entry 21) GE14: Ui < U2 (no earlier nuel by PGN in BSEPOI-0083 (Unchanged <1590PF designs remain tar BNP in use) LOCA calculation firorm entry update notice 26 Generically Yes GE13: +10°0 No 10°F forGE13 No No Reported 7/11/01 via 0

+/-10 F for Ul <1U2 by PGN in BSEPOI-0083 LPCI <1720°F 0°F for GE14 LOCA calculation injection update notice through jet014:N pumps GE14 NA Ul <U2

< 1580°F

OB21-0112 Revision I11 Page 2-16 of 2-18 Entry GE BWR Is there Estimated BNP Is limiting BNr Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT 8Nr Licensing BNP Licensing perfoimance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/ 50 °F? (See note 3) greater than (See Note 2 for Estimated (See Note 1) 50°F? deflnition of Licensing PCT (See Note 1) Impacted.)

27 -20°F for Yes GE13: NA No lo0F for GE13 No No Reptrted 7/11101 via Initial Ul <U2 by PGN in IISEPOI-0083 Pressure <1720°F 20°F for GE14 LOCA calculation error, oT update notice for Dryout Time error GUl -20 Ul <U2

<1560T1 28 Evaluation or Yes GE13: -3°F No 31F for GE13 No No Reported by PGN in 7/10/02 via 2923 MWt Ul <U2 annual notice BSEP 02-0123 EPU impact <1717°P 30F for GE14 GE14: -3P Ul <U2

<1557°'

29 SAFER Core Yes GE13: +51F No 5°F for GE13 No No To be reported by Projected Spray UI <U2 PGN in annual notice July 2003 Injection <1722 0F 5OF for GE14 Elevation Error for JPplants GE14: +50F generically Ul <U2

-951F to <15621'

+601F for LBLOCA, up to +30°1 for SBLOCA.

OB21-01 12 Revision I11 Page 2-17 of 2-18 Entry GE BIVR Is there Estimated BNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BN? Licensing performance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/. 50 OF? (See note 3) greater than (See Note 2 for Estimated (See Note 1) 50°F? definition of I Licensing PCT (See Note 1) impacted.)

30 SAFER Bulk Yes GE13: +100° No 15°F forGE13 No No To t reported by Projected Water Level Ul <U2 PGN in annual notice July 2003 EIrrR2-6 <1732OF 15F for GE14 generically

-5°Fto GE14: +10°F

+20°F UI U2

<1572°F 31 GESTR No GE13: U1 <U2 No 15°F for GE13 No No To be reported by Projected Input File <1732°F PGN in annual notice July 2003 Interpolation Error for 15°F for GE14 IWR2-6 GE14: Ut < U2 generically <1572°F negligible 32 SAFER04 Yes GE13: 0°F No 15°F forGE13 No No To be reported by Projected Computer (GE13) U I < U2 PGN in annual notice July 2003 Platform <1732°F 15T rorGE14 Change Impact for HWR2-6 No GE14: Ul <U2 generically (GE14) <1572°F negligible 33 WEVOL SI Yes GE13: 0°F No 15T for GE13 No No To be reported by Projected Volume U1 <U2 PGN in annual notice July 2003 Error for EWR2-6 <1732°F 15°F for GE14 generically negligible GE14: 0F U< <U2

OB21-0112 Revision I11 Page 2-18 of 2-18 Entry GE IIWR Is there Estimated BNP Is limiting BNP Cumulative Is cumulative Is ECCS Reported to NRC? Date Reported No. Estimated a BNP Licensing PCT Licensing PCT BNP Licensing BNP Licensing perrotmance By GE, BNP, or PCT Impact Impact ? Impact Impacted by more PCT change. PCT change Impacted? Both (See note 3) & than +/ 50 OF? (See note 3) greater than (See Note 2 for Estimated (See Note 1) 50OF? definition Of Licensing PCT (See Note 1) Impacted.)

0 34 SAFER Yes GE13: 00 F No 15 F torGE13 No No To reported by Projected LA-Vel/ III < U2 PG in annual notice July 2003 Volume <17321F 20'F for GE14 Tabie Error for BIWR2-6 generically GE14: -5F not reported UI <U2

<1567i1' 0 0 35 SAFER Yes GE13: 0 F No 15 F for GE] 3 No No To be reported by Projected Initial (GEI3) UI <U2 PGN in annual notice July2003 Separator <1732OF 0FttG 4 Pressure 20°F rorGE14 Drop Error for BWR2-6 No GE14: UI < U2 generically (0E14) <1567 9F not reported 0 0 36 New No GE13: 0 F No 15 F forGE13 No No To be reported by Projected Hydrogen. (GE13) Ul < U2 PGN in annual notice August 2004 0

Oxygen <1732°P 20 F for GE14 on Heat Source No GE14: 0WF.

(GE14) UI U2

<15670F

• GE7 bounds GE8, GE9 and GE10. PCT for fuel types prior to GE13 no longer being reported to NRC, as noticed by BSEP 01-0029 on 3/16/01.

Notes:

I - Report to NRC within 30 days 2 - Immediate Reportability. ECCS performance is not impacted if PCT<2200 IF, oxidation <17%, hydrogen < 1%. coolable geometry maintained, and long term cooling is available.

(SAFER/GESTR results must remain below 1600 OF) 3 - Report tn NRC annually if less than 50 'F 4 - Numerical convergence, change in computing platform, etc.

5 - No changes or errors were included prior to Revision 2 of 0B21-0112 for sensitivity to changes in computer operating system or small changes in input parameters aet pump loss coefficients). This was considered not to apply to Base LOCA Analysis NEDC 31624P Rev. 2 because BNP analyses had not been run on a new computing system. As further information became known in MFN 090-93 and WHH:99-07, this notice is recognized as a change in application where greater uncertainty is applied to compensate for the previously-unrecognized sensitivity to small input parameter changes. PGN had recognized +/- 50WI for sensitivity effect but believed to be NIA for Base LOCA Analysis NEDC 31624P Rev. 2, and to be corrected in LPCS OOS GE-NE-208-05-0393 and NEDC 31624P Supplement 3 Rev. 0.

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa . CALCULATION SHEET Revision 11 Supervisor: George E. Smith Page 3-1 of 3-2 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update

_w Attachment 3 Design Verification

ATTACHMENT 2 Sheet 1 of 1 Record of Lead Review Design 0B21-0112, 10CFR50.59 SAFER/GESTR Update Revision 11 The signature below of the Lead Reviewer records that:

- the review indicated below has been performed by the Lead Reviewer;

- appropriate reviews were performed and errors/deficiencies (for all reviews performed) have been resolved and these records are included in the design package;

- the review was performed in accordance with EGR-NGGC-0003.

Z Design Verification Review El Engineering Review a Owner's Review El Design Review Ej Alternate Calculation El Qualification Testing L Special Engineering Review El YES Z N/A Other Records are attached.

Mourad Aissa/ a-I <- NE _ _ _ _ _ _ _ _

Lead Reviewer (print/sign) Digscipline Date Item Deficiency Resolution No.

No deficiencies identified

=

FORM EGR-NGGC-0003-2-5 This form is a QA Record when completed and included with a completed design package. Owner's Reviews may be processed as stand alone QA records when Owner's Review is completed.

EGR-NGGC-0003 Rev 9

Preparer: Tom Dresser Calculation No. OB21-0112 Verifier: Mourad Aissa CALCULATION SHEET Revision 11 Supervisor: George E. Smith _ Page 4-1 of 4-2 Calculation

Title:

10CFR50.46 SAFER/GESTR-LOCA ECOS Analysis Update Attachment 4 User Production and Controlled Library Maintenance

ATTACHMENT I Sheet 1 of 1 CONTROLLED LIBRARY MAINTENANCE REQUEST FILE: hi; NF-1100.01 li:

FORM NGGS-NFP-0009-1-0 Originator: Tom Dresser Date 8/12104

1. File Name: DC OB21-0112 Rev. 1I August 2004.doc Action: Copy From: N:\Fuels\BNPLOCA\10CFR50.46 To: P:\Site\HNPAsps\Contro1\Data\BWR\BARF\

2. File Name: Action From:

To:

3. File Name: Action From: _

To:

4. File Name: Action From:

To:

5. File Name: Action From:

To:

Reason for Action: Update for 2003-2004 10CFR50.46 notices, archive for future updates Approved by Date:

Software Owner or Unit Manager Performed by Date:

Librarian or System Administrator Reviewed by Date:

Reviewer NGGS-NFP-0009 Rev. 0