RS-17-140, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

ML17291A508
Person / Time
Site:	Clinton
Issue date:	10/18/2017
From:	Simpson P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-17-140
Download: ML17291A508 (4)

Text

4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Office RS-17-140 10 CFR 50.46 October 18, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station

Reference:

Letter from P.R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 21, 2016 This letter provides the annual report required by 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," for Clinton Power Station, Unit 1. The attachments describe the changes in accumulated peak cladding temperature since the previous annual report submitted in the referenced letter.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803 .

Patrick R. Simpson Manager - Licensing Attachments:

1. 10 CFR 50.46 Report

2. 10 CFR 50.46 Report Assessment Notes cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Clinton Power Station

ATTACHMENT 1 Clinton Power Station, Unit 1 l SAFER/GESTR-LOCA l GNF2 Fuel 10 CFR 50.46 Report PLANT NAME: Clinton Power Station, Unit 1 ECCS EVALUATION MODEL: SAFER/GESTR-LOCA EVALUATION MODEL VENDOR: GNF/GEH REPORT REVISION DATE: October 18, 2017 CURRENT OPERATING CYCLE: 18 ANALYSIS OF RECORD CALCULATIONS

1. GEH Report 0000-0121-9100-R0, Clinton Power Station, GNF2 ECCS-LOCA Evaluation, October 2011.

2. NEDO-33173, Supplement 4-A, Revision 1, "Implementation of PRIME Models and Data in Downstream Methods," November 2012.

Fuel Analyzed in Calculation and in Operation: GNF2 Limiting Fuel Type: GNF2 Limiting Single Failure: High Pressure Core Spray Diesel Generator Limiting Break Size/Location: Double-Ended Guillotine of Recirculation-Pump Suction Piping Reference Peak Cladding Temperature (PCT): 1880 °F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS:

10 CFR 50.46 report dated October 26, 2012 (Note 1) PCT = 0 °F 10 CFR 50.46 report dated October 25, 2013 (Note 2) PCT = 40 °F 10 CFR 50.46 report dated October 24, 2014 (Note 3) PCT = -15 °F 10 CFR 50.46 report dated October 23, 2015 (Note 4) PCT = 0 °F 10 CFR 50.46 report dated October 21, 2016 (Note 5) PCT = 0 °F Net PCT 1905 °F B. CURRENT LOCA MODEL ASSESSMENTS:

Total PCT change from current assessments (Note 6) PCT = 30 °F Total PCT change from current assessments PCT = 30 °F Cumulative PCT change from current assessments lPCTl = 30 °F Net PCT 1935 °F

ATTACHMENT 2 Clinton Power Station, Unit 1 10 CFR 50.46 Report Assessment Notes

1. Prior LOCA Model Assessment (2012)

The referenced letter reported that the GNF2 fuel design was introduced into the Clinton Power Station (CPS) core during the Reload 13 (Cycle 14) outage. There were no Emergency Core Cooling System (ECCS) related changes or modifications that affected the assumptions in the CPS Loss-of-Coolant Accident (LOCA) analysis of record.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 26, 2012]

2. Prior LOCA Model Assessment (2013)

To address inaccuracies in thermal conductivity degradation, GEH replaced the GESTR-LOCA model with a newer model, PRIME. The dominant Peak Cladding Temperature (PCT) effect is from the PRIME thermal conductivity which produces higher fuel stored energy. The PCT impact identified in the referenced letter reflects the difference between the existing GESTR analysis PCT and a conservatively postulated PCT if the analysis were performed with the PRIME model. The CPS ECCS-LOCA analysis methodology remains GESTR based, and it will not be PRIME based until the ECCS-LOCA analysis is re-performed using PRIME. The notification resulted in a 40 °F PCT impact to GNF2 fuel.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 25, 2013]

3. Prior LOCA Model Assessment (2014)

The referenced letter identified four vendor notifications.

• The first notification addressed several accumulated updates to the SAFER04A model. These code maintenance changes had an individually and collectively insignificant effect on calculated PCT.

• The second notification corrected a logic error that was isolated, occurring with an indication that the expected system mass diverges from the calculated actual system mass. This error affects the ECCS flow credited as reaching the core. Correction of this error did not impact the PCT for GNF2 fuel.

• The third notification addressed an error with the imposed minimum pressure differential (p) for droplet flow above a two-phase level in the core. This error can create an inappropriate steam cooling benefit above the core two phase level. To correct this error, an explicit core p calculation was applied without regard to droplet condition resulting in a PCT of -15 °F to GNF2.

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ATTACHMENT 2 Clinton Power Station, Unit 1 10 CFR 50.46 Report Assessment Notes

• The fourth notification addressed an incorrect pressure head representation when defining the counter current flow limitation. Correction of this error did not impact the PCT for GNF2 fuel.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 24, 2014]

4. Prior LOCA Model Assessment (2015)

Per the referenced letter, no vendor notifications of ECCS model errors/changes applicable to CPS, were issued. There were no ECCS related changes or modifications at CPS that affect the LOCA analysis of record.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 23, 2015]

5. Prior LOCA Model Assessment (2016)

Per the referenced letter, no vendor notifications of ECCS model errors/changes applicable to CPS, were issued. There were no ECCS related changes or modifications at CPS that affect the LOCA analysis of record.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 21, 2016]

6. Current LOCA Model Assessment (2017)

Two errors were reported against the GNF2 fuel design during this reporting period applicable to CPS.

• Error 2017-01 identifies that the GNF2 leakage paths between the bundle and the bypass (i.e., lower tie plate flow hole and channel to lower tie plate interface) were incorrectly modeled. The error was estimated to have 30 °F PCT impact for GNF2 fuel.

• Error 2017-02 identifies that the previous modelling of the fuel rod plenum region was not consistent with the fuel rod design for current 10x10 fuel designs, including GNF2. Fuel rod plenum inputs were changed to reflect current 10x10 fuel bundle rod designs. The error was estimated to have 0 °F PCT impact for GNF2 fuel.

There were no ECCS related changes or modifications at CPS that affect the LOCA analysis of record.

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