NL-08-1735, Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007: Difference between revisions

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| issue date = 12/19/2008
| issue date = 12/19/2008
| title = Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007
| title = Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007
| author name = Ajluni M J
| author name = Ajluni M
| author affiliation = Southern Nuclear Operating Co, Inc
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Southern Nuclear Operating Company, Inc. Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN'\
{{#Wiki_filter:Southern Nuclear Operating Company, Inc.
COMPANY December 19, Energy to Serve Your World'" Docket 50-321 50-348 50-424 NL-08-1735 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Joseph M. Farley Nuclear Vogtle Electric Generating 10 CFR 50.46 ECCS Evaluation Model Annual Reports for Ladies and Gentlemen:
Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN'\
Southern Nuclear Operating Company (SNC) is the licensed operator for the Edwin I. Hatch Nuclear Plant (Hatch), the Joseph M. Farley Nuclear Plant (Farley), and the Vogtle Electric Generating Plant (Vogtle).
COMPANY December 19, 2008                                                Energy to Serve Your World'"
The requirements of 10 CFR 50.46(a)(3)(ii) include an annual report by licensees of changes to or errors in acceptable emergency core cooling (ECCS) models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis.
Docket Nos.: 50-321       50-348   50-424                           NL-08-1735 50-366 50-364   50-425 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Ladies and Gentlemen:
Accordingly, the reports required by 10 CFR 50.46(a)(3)(ii) for Hatch, Farley, and Vogtle are provided in Enclosures 1, 2, and 3, respectively.
Southern Nuclear Operating Company (SNC) is the licensed operator for the Edwin I. Hatch Nuclear Plant (Hatch), the Joseph M. Farley Nuclear Plant (Farley), and the Vogtle Electric Generating Plant (Vogtle). The requirements of 10 CFR 50.46(a)(3)(ii) include an annual report by licensees of changes to or errors in acceptable emergency core cooling (ECCS) models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. Accordingly, the reports required by 10 CFR 50.46(a)(3)(ii) for Hatch, Farley, and Vogtle are provided in Enclosures 1, 2, and 3, respectively. The resultil1g PCT for Hatch, Farley, and Vogtle continues to meet the criterion of 10 CFR 50.46(b)(1) (Le., S 2200°F).
The resultil1g PCT for Hatch, Farley, and Vogtle continues to meet the criterion of 10 CFR 50.46(b)(1) (Le., S 2200°F). This letter contains no NRC commitments.
This letter contains no NRC commitments. If you have any questions, please advise.
If you have any questions, please advise. Sincerely, Mark J. Ajluni Manager, Nuclear Licensing MJNTWS/daj U. S. Nuclear Regulatory Commission NL-08-1735
Sincerely,
                    ~~~
Mark J. Ajluni Manager, Nuclear Licensing MJNTWS/daj


Page 2    
U. S. Nuclear Regulatory Commission NL-08-1735 Page 2


==Enclosures:==
==Enclosures:==
: 1. Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007 2. Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007 3. Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007  
: 1. Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007
: 2. Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007
: 3. Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007 cc:  Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CFA04.054; CHA02.004; CVC7000; LC# 14867 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. R. E. Martin, NRR Project Manager - Hatch Mr. R. E. Martin, NRR Project Manager - Vogtle Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. J. A. Hickey, Senior Resident Inspector - Hatch Mr. E. D. Morris, Acting Senior Resident Inspector - Vogtle


cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle  Mr. D. H. Jones, Vice President - Engineering  RType: CFA04.054; CHA02.004; CVC7000; LC# 14867 
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007


U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley  Mr. R. E. Martin, NRR Project Manager - Hatch  Mr. R. E. Martin, NRR Project Manager - Vogtle Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. J. A. Hickey, Senior Resident Inspector - Hatch Mr. E. D. Morris, Acting Senior Resident Inspector - Vogtle
Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Edwin I. Hatch Nuclear Plant Unit 1 SAFER/GESTR-LOCA Analysis Model Table 1-1a - Summary of Changes/Errors (2007)
Estimated Description                            Effect
( PCT)
None affecting PCT                                                  N/A Table 1-1b - Cumulative Impact of Changes/Errors GE14 Description lPCTl
(°F)
* Changes/Errors Previously Reported (Reference 1)                  5
* Current Year - 2007 (Reference 2)                                  0 Cumulative Total                5 Page 1 of 3


Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007   Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007  
Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Edwin I. Hatch Nuclear Plant Unit 2 SAFER/GESTR-LOCA Analysis Model Table 1-2a - Summary of Changes/Errors (2007)
Estimated Description                                              Effect
( PCT)
None affecting PCT                                                                        N/A Table 1-2b - Cumulative Impact of Changes/Errors GE13*            GE14*
Description lPCTl          lPCTl
(°F)            (°F)
* Changes/Errors Previously Reported (Reference 1)                      25 **            5
* Current Year - 2007 (Reference 3)                                        0              0 Cumulative Total            25              5
* Hatch Unit 2 operated a portion of 2007 with the core containing both GE13 and GE 14 fuel.
** Changes/Errors identified since previous significant change/error report (Reference 4)
Page 2 of 3


Page 1 of 3 Edwin I. Hatch Nuclear Plant Unit 1 SAFER/GESTR-LOCA Analysis Model Table 1-1a - Summary of Changes/Errors (2007)
Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
Description Estimated Effect ( PCT) None affecting PCT N/A Table 1-1b - Cumulative Impact of Changes/Errors GE14 Description lPCTl (°F)
* Changes/Errors Previously Reported  (Reference 1) 5
* Current Year - 2007 (Reference 2) 0  Cumulative Total 5    Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
 
Page 2 of 3 Edwin I. Hatch Nuclear Plant Unit 2 SAFER/GESTR-LOCA Analysis Model Table 1-2a - Summary of Changes/Errors (2007)
Description Estimated Effect ( PCT) None affecting PCT N/A Table 1-2b - Cumulative Impact of Changes/Errors GE13* GE14* Description lPCTl (°F) lPCTl (°F)
* Changes/Errors Previously Reported (Reference 1) 25 ** 5
* Current Year - 2007 (Reference 3) 0 0  Cumulative Total 25 5
* Hatch Unit 2 operated a portion of 2007 with the core containing both GE13 and GE 14 fuel. ** Changes/Errors identified since previous significant change/error report (Reference 4)
Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007  
 
Page 3 of 3


==References:==
==References:==
: 1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006," dated December 26, 2007 2. Global Nuclear Fuel Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Power Plant Unit 1 (Report Number 0000-0067-2863-SRLR), Revision 0, dated December 2007 3. Global Nuclear Fuel Supplemental Reload Licensing Report for Edwin I. Hatch Nuclear Power Plant Unit 2 (Report Number 0000-0083-5389-SRLR),
: 1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006," dated December 26, 2007
Revision 0, dated December 2008 4. Letter from H. L. Sumner, Jr. to USNRC (HL-6090), "Edwin I. Hatch Nuclear Plant Reporting of Changes and Errors in ECCS Evaluation Models," dated May 21, 2001  
: 2. Global Nuclear Fuel Supplemental Reload Licensing Report for Edwin I.
 
Hatch Nuclear Power Plant Unit 1 (Report Number 0000-0067-2863-SRLR),
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
Revision 0, dated December 2007
 
: 3. Global Nuclear Fuel Supplemental Reload Licensing Report for Edwin I.
Page 1 of 5 Joseph M. Farley Nuclear Plant - Unit 1 ASTRUM Best Estimate Large Break LOCA Evaluation Table 2-1a - Summary of Changes/Errors (2007)
Hatch Nuclear Power Plant Unit 2 (Report Number 0000-0083-5389-SRLR),
Description Estimated Effect ( PCT) None affecting PCT N/A
Revision 0, dated December 2008
 
: 4. Letter from H. L. Sumner, Jr. to USNRC (HL-6090), "Edwin I. Hatch Nuclear Plant Reporting of Changes and Errors in ECCS Evaluation Models," dated May 21, 2001 Page 3 of 3
Table 2-1b - Cumulative Impact of Changes/Errors Description lPCTl (°F)
* Changes/Errors Previously Reported  (Reference 1) 0
* Current Year - 2007 (Reference 2) 0  Cumulative Total 0 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007


Page 2 of 5 Joseph M. Farley Nuclear Plant - Unit 1 NOTRUMP Appendix K Small Break LOCA Evaluation Table 2-1c - Summary of Changes/Errors (2007)
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
Description Estimated Effect ( PCT) NOTRUMP-EM Refined Break Spectrum During the course of reviewing several extended power uprate and replacement steam generators Small Break LOCA (SBLOCA) analyses, the Nuclear Regulatory Commission (NRC) questioned the break spectrum analyzed in the NOTRUMP evaluation model (EM). The NRC was concerned that the resolution of the break spectrum used in the NOTRUMP EM may not be fine enough to capture the worst break with regard to limiting peak clad temperature as per 10 CFR 50.46. That is, the plant could be SBLOCA limited with regard to overall LOCA results. 
-17 °F    Table 2-1d - Cumulative Impact of Changes/Errors Description lPCTl (°F)
* Changes/Errors  - Previously Reported (Reference 1) 25
* Changes/Errors - 2007 (Reference 2) 17  Cumulative Total 42 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007  


Page 3 of 5 Joseph M. Farley Nuclear Plant - Unit 2 ASTRUM Best Estimate Large Break LOCA Evaluation Table 2-2a - Summary of Changes/Errors (2007)
Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 1 ASTRUM Best Estimate Large Break LOCA Evaluation Table 2-1a - Summary of Changes/Errors (2007)
Description Estimated Effect ( PCT) None affecting PCT N/A  
Estimated Description                             Effect
( PCT)
None affecting PCT                                                   N/A Table 2-1b - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Changes/Errors Previously Reported (Reference 1)                    0
* Current Year - 2007 (Reference 2)                                    0 Cumulative Total      0 Page 1 of 5


Table 2-2b - Cumulative Impact of Changes/Errors Description lPCTl (°F)
Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 1 NOTRUMP Appendix K Small Break LOCA Evaluation Table 2-1c - Summary of Changes/Errors (2007)
* Changes/Errors Previously Reported (Reference 1) 0
Estimated Description                                  Effect
* Current Year - 2007 (Reference 2) 0  Cumulative Total 0 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
( PCT)
NOTRUMP-EM Refined Break Spectrum During the course of reviewing several extended power uprate and replacement steam generators Small Break LOCA (SBLOCA) analyses, the Nuclear Regulatory Commission (NRC) questioned the break spectrum analyzed in the NOTRUMP evaluation model (EM). The NRC was                    -17 °F concerned that the resolution of the break spectrum used in the NOTRUMP EM may not be fine enough to capture the worst break with regard to limiting peak clad temperature as per 10 CFR 50.46. That is, the plant could be SBLOCA limited with regard to overall LOCA results.
Table 2-1d - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Changes/Errors - Previously Reported (Reference 1)                         25
* Changes/Errors - 2007 (Reference 2)                                       17 Cumulative Total         42 Page 2 of 5


Page 4 of 5 Joseph M. Farley Nuclear Plant - Unit 2 NOTRUMP Appendix K Small Break LOCA Evaluation Table 2-2c - Summary of Changes/Errors (2007)
Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 2 ASTRUM Best Estimate Large Break LOCA Evaluation Table 2-2a - Summary of Changes/Errors (2007)
Description Estimated Effect ( PCT) None affecting PCT N/A  
Estimated Description                             Effect
( PCT)
None affecting PCT                                                   N/A Table 2-2b - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Changes/Errors Previously Reported (Reference 1)                    0
* Current Year - 2007 (Reference 2)                                    0 Cumulative Total      0 Page 3 of 5


Table 2-2d - Cumulative Impact of Changes/Errors Description lPCTl (°F)
Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 2 NOTRUMP Appendix K Small Break LOCA Evaluation Table 2-2c - Summary of Changes/Errors (2007)
* Previously Reported (Reference 1) 0
Estimated Description                                            Effect
* Current Year - 2007 (Reference 2)   0
( PCT)
* Cumulative Total 0
None affecting PCT                                                                        N/A Table 2-2d - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Previously Reported (Reference 1)                                                       0
* Current Year - 2007 (Reference 2)                                                       0*
Cumulative Total                 0
* No subsequent changes to or errors in the model were identified in 2007 following issuance of significant change/error report (Reference 3).
* No subsequent changes to or errors in the model were identified in 2007 following issuance of significant change/error report (Reference 3).
Page 4 of 5


Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007  
Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 References
 
Page 5 of 5 References  
: 1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006,"
: 1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006,"
dated December 26, 2007 2. Westinghouse Letter LTR-LIS-08-48, "J. M. Farley Units 1 & 2 10 CFR 50.46 Annual Notification and Reporting for 2007," dated January 31, 2008 3. Letter from B. J. George to USNRC (NL-07-0379), "Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Significant Change Report," dated February 26, 2007
dated December 26, 2007
 
: 2. Westinghouse Letter LTR-LIS-08-48, "J. M. Farley Units 1 & 2 10 CFR 50.46 Annual Notification and Reporting for 2007," dated January 31, 2008
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
: 3. Letter from B. J. George to USNRC (NL-07-0379), "Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Significant Change Report," dated February 26, 2007 Page 5 of 5
 
Page 1 of 5 Vogtle Electric Generating Plant - Unit 1 BASH Large Break LOCA Evaluation


Table 3-1a - Summary of Changes/Errors (2007)
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
Description Estimated Effect ( PCT) LOCBART Pellet Volumetric Heat Generation Rate The LOCBART code has been modified to correct an inverted term in the calculation of the pellet volumetric heat generation rate. This change affects the steady-state and transient heat generation for all three rods and could result in either an increase or decrease in peak cladding temperature for a given calculation.
18 °F Updated Analysis Based on LOCBART Version 36 Prior to determination of effect of the LOCBART Pellet Volumetric Heat Generation Rate error described above, the limiting case was modeled using LOCBART Version 36 instead of LOCBART Version 25 previously used in order to determine the contribution of the LOCBART Pellet Volumetric Heat Generation Rate error.
-22 °F Table 3-1b - Cumulative Impact of Changes/Errors Description lPCTl (°F)
* Previously Reported (Reference 1) 0
* Current Year - 2007 (Reference 2) 40  Cumulative Total 40 Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007  


Page 2 of 5 Vogtle Electric Generating Plant - Unit 1 Appendix K Small Break LOCA Evaluation Table 3-1c - Summary of Changes/Errors (2007)
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 1 BASH Large Break LOCA Evaluation Table 3-1a - Summary of Changes/Errors (2007)
Description Estimated Effect ( PCT) None Affecting PCT N/A Table 3-1d - Cumulative Impact of Changes/Errors Description lPCTl (°F)
Estimated Description                                   Effect
* Previously Reported (Reference 1) 0
( PCT)
* Current Year - 2007 (Reference 2) 0  Cumulative Total 0
LOCBART Pellet Volumetric Heat Generation Rate The LOCBART code has been modified to correct an inverted term in the calculation of the pellet volumetric heat generation rate. This change affects    18 °F the steady-state and transient heat generation for all three rods and could result in either an increase or decrease in peak cladding temperature for a given calculation.
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
Updated Analysis Based on LOCBART Version 36 Prior to determination of effect of the LOCBART Pellet Volumetric Heat Generation Rate error described above, the limiting case was modeled using      -22 °F LOCBART Version 36 instead of LOCBART Version 25 previously used in order to determine the contribution of the LOCBART Pellet Volumetric Heat Generation Rate error.
Table 3-1b - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Previously Reported (Reference 1)                                             0
* Current Year - 2007 (Reference 2)                                             40 Cumulative Total         40 Page 1 of 5


Page 3 of 5 Vogtle Electric Generating Plant - Unit 2 BASH Large Break LOCA Evaluation  
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 1 Appendix K Small Break LOCA Evaluation Table 3-1c - Summary of Changes/Errors (2007)
Estimated Description                              Effect
( PCT)
None Affecting PCT                                                      N/A Table 3-1d - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Previously Reported (Reference 1)                                    0
* Current Year - 2007 (Reference 2)                                    0 Cumulative Total      0 Page 2 of 5


Table 3-2a - Summary of Changes/Errors (2007)
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 2 BASH Large Break LOCA Evaluation Table 3-2a - Summary of Changes/Errors (2007)
Description Estimated Effect ( PCT) LOCBART Pellet Volumetric Heat Generation Rate The LOCBART code has been modified to correct an inverted term in the calculation of the pellet volumetric heat generation rate. This change affects the steady-state and transient heat generation for all three rods and could result in either an increase or decrease in peak cladding temperature for a given calculation.
Estimated Description                                   Effect
18 °F Updated Analysis Based on LOCBART Version 36 Prior to determination of effect of the LOCBART Pellet Volumetric Heat Generation Rate error described above, the limiting case was modeled using LOCBART Version 36 instead of LOCBART Version 25 previously used in order to determine the contribution of the LOCBART Pellet Volumetric Heat Generation Rate error.
( PCT)
-22 °F  Table 3-2b - Cumulative Impact of Changes/Errors Description lPCTl (°F)
LOCBART Pellet Volumetric Heat Generation Rate The LOCBART code has been modified to correct an inverted term in the calculation of the pellet volumetric heat generation rate. This change affects   18 °F the steady-state and transient heat generation for all three rods and could result in either an increase or decrease in peak cladding temperature for a given calculation.
* Previously Reported (Reference 1) 0
Updated Analysis Based on LOCBART Version 36 Prior to determination of effect of the LOCBART Pellet Volumetric Heat Generation Rate error described above, the limiting case was modeled using       -22 °F LOCBART Version 36 instead of LOCBART Version 25 previously used in order to determine the contribution of the LOCBART Pellet Volumetric Heat Generation Rate error.
* Current Year - 2007 (Reference 2) 40 Cumulative Total 40 Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
Table 3-2b - Cumulative Impact of Changes/Errors lPCTl Description
(°F)
* Previously Reported (Reference 1)                                             0
* Current Year - 2007 (Reference 2)                                             40 Cumulative Total         40 Page 3 of 5


Page 4 of 5 Vogtle Electric Generating Plant - Unit 2 Appendix K Small Break LOCA Evaluation Table 3-2c - Summary of Changes/Errors (2007)
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 2 Appendix K Small Break LOCA Evaluation Table 3-2c - Summary of Changes/Errors (2007)
Description Estimated Effect ( PCT) None Affecting PCT N/A Table 3-2d - Cumulative Impact of Changes/Errors Description lPCTl (°F)
Estimated Description                             Effect
* Previously Reported (Reference 1) 0
( PCT)
* Current Year - 2007 (Reference 2) 0 Cumulative Total 0
None Affecting PCT                                                       N/A Table 3-2d - Cumulative Impact of Changes/Errors lPCTl Description
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007
(°F)
* Previously Reported (Reference 1)                                   0
* Current Year - 2007 (Reference 2)                                   0 Cumulative Total     0 Page 4 of 5


Page 5 of 5 References  
Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 References
: 1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006," dated December 26, 2007 2. Westinghouse Letter LTR-LIS-08-65, "Vogtle Units 1 & 2 10 CFR 50.46 Annual Notification and Reporting for 2007," dated January 30, 2008}}
: 1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006," dated December 26, 2007
: 2. Westinghouse Letter LTR-LIS-08-65, "Vogtle Units 1 & 2 10 CFR 50.46 Annual Notification and Reporting for 2007," dated January 30, 2008 Page 5 of 5}}

Latest revision as of 11:15, 14 November 2019

Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007
ML083570435
Person / Time
Site: Hatch, Vogtle, Farley  Southern Nuclear icon.png
Issue date: 12/19/2008
From: Ajluni M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-08-1735
Download: ML083570435 (18)
v • d • e


Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN'\

COMPANY December 19, 2008 Energy to Serve Your World'"

Docket Nos.: 50-321 50-348 50-424 NL-08-1735 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Ladies and Gentlemen:

Southern Nuclear Operating Company (SNC) is the licensed operator for the Edwin I. Hatch Nuclear Plant (Hatch), the Joseph M. Farley Nuclear Plant (Farley), and the Vogtle Electric Generating Plant (Vogtle). The requirements of 10 CFR 50.46(a)(3)(ii) include an annual report by licensees of changes to or errors in acceptable emergency core cooling (ECCS) models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. Accordingly, the reports required by 10 CFR 50.46(a)(3)(ii) for Hatch, Farley, and Vogtle are provided in Enclosures 1, 2, and 3, respectively. The resultil1g PCT for Hatch, Farley, and Vogtle continues to meet the criterion of 10 CFR 50.46(b)(1) (Le., S 2200°F).

This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely,

~~~

Mark J. Ajluni Manager, Nuclear Licensing MJNTWS/daj

U. S. Nuclear Regulatory Commission NL-08-1735 Page 2

Enclosures:

1. Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007
2. Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007
3. Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Report for 2007 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CFA04.054; CHA02.004; CVC7000; LC# 14867 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. R. E. Martin, NRR Project Manager - Hatch Mr. R. E. Martin, NRR Project Manager - Vogtle Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. J. A. Hickey, Senior Resident Inspector - Hatch Mr. E. D. Morris, Acting Senior Resident Inspector - Vogtle

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007

Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Edwin I. Hatch Nuclear Plant Unit 1 SAFER/GESTR-LOCA Analysis Model Table 1-1a - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None affecting PCT N/A Table 1-1b - Cumulative Impact of Changes/Errors GE14 Description lPCTl

(°F)

  • Changes/Errors Previously Reported (Reference 1) 5
  • Current Year - 2007 (Reference 2) 0 Cumulative Total 5 Page 1 of 3

Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Edwin I. Hatch Nuclear Plant Unit 2 SAFER/GESTR-LOCA Analysis Model Table 1-2a - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None affecting PCT N/A Table 1-2b - Cumulative Impact of Changes/Errors GE13* GE14*

Description lPCTl lPCTl

(°F) (°F)

  • Changes/Errors Previously Reported (Reference 1) 25 ** 5
  • Current Year - 2007 (Reference 3) 0 0 Cumulative Total 25 5
  • Hatch Unit 2 operated a portion of 2007 with the core containing both GE13 and GE 14 fuel.
    • Changes/Errors identified since previous significant change/error report (Reference 4)

Page 2 of 3

Enclosure 1 Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007

References:

1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006," dated December 26, 2007
2. Global Nuclear Fuel Supplemental Reload Licensing Report for Edwin I.

Hatch Nuclear Power Plant Unit 1 (Report Number 0000-0067-2863-SRLR),

Revision 0, dated December 2007

3. Global Nuclear Fuel Supplemental Reload Licensing Report for Edwin I.

Hatch Nuclear Power Plant Unit 2 (Report Number 0000-0083-5389-SRLR),

Revision 0, dated December 2008

4. Letter from H. L. Sumner, Jr. to USNRC (HL-6090), "Edwin I. Hatch Nuclear Plant Reporting of Changes and Errors in ECCS Evaluation Models," dated May 21, 2001 Page 3 of 3

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007

Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 1 ASTRUM Best Estimate Large Break LOCA Evaluation Table 2-1a - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None affecting PCT N/A Table 2-1b - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Changes/Errors Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 0 Cumulative Total 0 Page 1 of 5

Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 1 NOTRUMP Appendix K Small Break LOCA Evaluation Table 2-1c - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

NOTRUMP-EM Refined Break Spectrum During the course of reviewing several extended power uprate and replacement steam generators Small Break LOCA (SBLOCA) analyses, the Nuclear Regulatory Commission (NRC) questioned the break spectrum analyzed in the NOTRUMP evaluation model (EM). The NRC was -17 °F concerned that the resolution of the break spectrum used in the NOTRUMP EM may not be fine enough to capture the worst break with regard to limiting peak clad temperature as per 10 CFR 50.46. That is, the plant could be SBLOCA limited with regard to overall LOCA results.

Table 2-1d - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Changes/Errors - Previously Reported (Reference 1) 25
  • Changes/Errors - 2007 (Reference 2) 17 Cumulative Total 42 Page 2 of 5

Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 2 ASTRUM Best Estimate Large Break LOCA Evaluation Table 2-2a - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None affecting PCT N/A Table 2-2b - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Changes/Errors Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 0 Cumulative Total 0 Page 3 of 5

Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Joseph M. Farley Nuclear Plant - Unit 2 NOTRUMP Appendix K Small Break LOCA Evaluation Table 2-2c - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None affecting PCT N/A Table 2-2d - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 0*

Cumulative Total 0

  • No subsequent changes to or errors in the model were identified in 2007 following issuance of significant change/error report (Reference 3).

Page 4 of 5

Enclosure 2 Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 References

1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006,"

dated December 26, 2007

2. Westinghouse Letter LTR-LIS-08-48, "J. M. Farley Units 1 & 2 10 CFR 50.46 Annual Notification and Reporting for 2007," dated January 31, 2008
3. Letter from B. J. George to USNRC (NL-07-0379), "Joseph M. Farley Nuclear Plant 10 CFR 50.46 ECCS Evaluation Significant Change Report," dated February 26, 2007 Page 5 of 5

Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007

Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 1 BASH Large Break LOCA Evaluation Table 3-1a - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

LOCBART Pellet Volumetric Heat Generation Rate The LOCBART code has been modified to correct an inverted term in the calculation of the pellet volumetric heat generation rate. This change affects 18 °F the steady-state and transient heat generation for all three rods and could result in either an increase or decrease in peak cladding temperature for a given calculation.

Updated Analysis Based on LOCBART Version 36 Prior to determination of effect of the LOCBART Pellet Volumetric Heat Generation Rate error described above, the limiting case was modeled using -22 °F LOCBART Version 36 instead of LOCBART Version 25 previously used in order to determine the contribution of the LOCBART Pellet Volumetric Heat Generation Rate error.

Table 3-1b - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 40 Cumulative Total 40 Page 1 of 5

Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 1 Appendix K Small Break LOCA Evaluation Table 3-1c - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None Affecting PCT N/A Table 3-1d - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 0 Cumulative Total 0 Page 2 of 5

Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 2 BASH Large Break LOCA Evaluation Table 3-2a - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

LOCBART Pellet Volumetric Heat Generation Rate The LOCBART code has been modified to correct an inverted term in the calculation of the pellet volumetric heat generation rate. This change affects 18 °F the steady-state and transient heat generation for all three rods and could result in either an increase or decrease in peak cladding temperature for a given calculation.

Updated Analysis Based on LOCBART Version 36 Prior to determination of effect of the LOCBART Pellet Volumetric Heat Generation Rate error described above, the limiting case was modeled using -22 °F LOCBART Version 36 instead of LOCBART Version 25 previously used in order to determine the contribution of the LOCBART Pellet Volumetric Heat Generation Rate error.

Table 3-2b - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 40 Cumulative Total 40 Page 3 of 5

Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 Vogtle Electric Generating Plant - Unit 2 Appendix K Small Break LOCA Evaluation Table 3-2c - Summary of Changes/Errors (2007)

Estimated Description Effect

( PCT)

None Affecting PCT N/A Table 3-2d - Cumulative Impact of Changes/Errors lPCTl Description

(°F)

  • Previously Reported (Reference 1) 0
  • Current Year - 2007 (Reference 2) 0 Cumulative Total 0 Page 4 of 5

Enclosure 3 Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2007 References

1. Letter from B. J. George to USNRC (NL-07-2160), "Edwin I. Hatch Nuclear Plant, Joseph M. Farley Nuclear Plant, Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2006," dated December 26, 2007
2. Westinghouse Letter LTR-LIS-08-65, "Vogtle Units 1 & 2 10 CFR 50.46 Annual Notification and Reporting for 2007," dated January 30, 2008 Page 5 of 5
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