NOC-AE-14003129, Updated Final Safety Analysis Report Revision 17

Updated Final Safety Analysis Report Revision 17

ML14132A289
Person / Time
Site:	South Texas
Issue date:	04/28/2014
From:	Gerry Powell South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-14003129, STI: 33866719
Download: ML14132A289 (7)

Text

Nuclear Operating Company South Texas Pro/ect Electric Generatin$ Station PO.Box 289 Wadsworth. Texas 77483 A April 28, 2014 NOC-AE-14003129 10CFR50.71 (e)

STI: 33866719 Attention: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Updated Final Safety Analysis Report Revision 17 Pursuant to 10CFR50.71(e), STP Nuclear Operating Company (STPNOC) submits Revision 17 to the South Texas Project Updated Final Safety Analysis Report (UFSAR).

Attachment 1 includes a summary of changes in Revision 17 that were made under the provisions of 10CFR50.59 or in accordance with the guidance of NEI 98-03 and NEI 96-07. Attachment 2 consists of three CD-ROM's. CD-ROM 1 includes the UFSAR; CD-ROM 2 and 3 contain the UFSAR Figures and Controlled Drawings.

Errors have been found in the dose values reported in Chapter 15 Table 15.6-17, Dose Resulting from Large Break Loss of Coolant Accident. These errors are transcription errors from the underlying analysis which was submitted to the Commission as part of the STPNOC License Amendment Request for Alternate Source Term. Due to the magnitude of the changes in values, a submittal to the Commission is required. All the corrected dose values remain below the applicable regulatory limits and STPNOC is tracking this action in the Corrective Action Program.

If you should have any questions on this submittal, please contact either Marilyn Kistler at (361) 972-8385 or me at (361) 972-7566.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on , 2.,.

G.T. Powell Site Vice President MK : Summary of Changes : Updated Final Safety Analysis Report, Revision 17 Ac6 3

NOC-AE-14003129 Page 2 of 2 cc:

(paper copy) (electronic copy)

Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 1600 East Lamar Boulevard Arlington, TX 76011-4511 Balwant K. Singal U. S. Nuclear Regulatory Commission Balwant K. Singal John Ragan Senior Project Manager Chris O'Hara U.S. Nuclear Regulatory Commission Jim von Suskil One White Flint North (MS 8 B1) NRG South Texas LP 11555 Rockville Pike Rockville, MD 20852 Kevin Polio NRC Resident Inspector Cris Eugster U. S. Nuclear Regulatory Commission L. D. Blaylock P. O. Box 289, Mail Code: MN116 City Public Service Wadsworth, TX 77483 Jim Collins City of Austin Peter Nemeth Electric Utility Department Crain Caton & James, P.C.

721 Barton Springs Road Austin, TX 78704 C. Mele City of Austin Richard A. Ratliff Texas Department of State Health Services Robert Free Texas Department of State Health Services Note: Above copies distributed without Attachment 2 except as noted by an asterisk

Attachment 1 NOC-AE-14003129 Page 1 of 5 South Texas Project Updated Final Safety Analysis Report Revision 17 Summary of Changes Chapter 1, "Introduction and General Description of Plant"

1. Removed references to the use of the Post-Accident Sampling System during normal operation and to reflect current usage. (CN-3109) [1.2.2.11.2]

2. Removed amplification details of the Public Address System, removed the statement regarding radio communication in vehicles. (CN-3114) [1.2.2.11.6]

3. Added Reference to Drawing 9P26-0-C-01618. (CN-3101) [Table 1.2-1] {NEI 98-03)

4. Removed Visitor Center approved by Technical Specification Amendments 210 for Unit 1 and Amendment 189 for Unit 2. (CN-3101) [Figures 1.1-1] {NEI 98-03}

5. Updated to GCA Services Group and Regulated Security Solutions. (CN-3101)

[1.4.6.7 and 1.4.6.9] {NEI 98-03)

6. Deleted WCAP-7800 and added Westinghouse Quality Management System (QMS)

Revision 6 and Revision 7. (CN-3090) (CN-3094) [Table 1.6-2]

7. Updated BEACON reference to include NRC-approved addenda to WCAP 12472-P-A. (CN-3084) [Table 1.6-2]

Chapter 2, "Site Characteristics"

1. Corrected typos. (CN-3031) [Table 2.3-34B, 2.5.6.5.1.6.2] {NEI 98-03}

Chapter 3, "Design of Structures, Components, Equipment, and Systems"

1. Corrected statement referencing Containment sumps. (CN-3107) [3.1.2.4.9] {NEI 98-03)

2. Editorial corrections. (CN-3031) [3.9.1.1.7.4, Table 3.8.4-1and 3.1.2.6.2.3] {NEI 98-03)

3. Updated Tables to reflect non-safety related repair allowances.

(CN-3053 and CN-3113) [Table 3.2.B-1, Table 3.2.B-2]

4. Updated Tables to reflect non-safety related repair allowances.

(CN-3053 and CN-3113) [Table 3.2.B-1, Table 3.2.B-2]

5. Revised to delete WCAP-7800 and add Westinghouse Quality Management System (QMS). (CN-3090) [Table 3.2.B-2 Note 24] {NEI 98-03)

6. Revised to more accurately describe the containment liner fatigue analysis. (CN-3054) [3.8.1.5.6 and 3.8.1.5.9] {NEI 98-03}

Attachment 1 NOC-AE-14003129 Page 2 of 5 South Texas Project Updated Final Safety Analysis Report Revision 17 Summary of Changes Chapter 4, "Reactor"

1. Update sections to reflect Optimized ZIRLO Fuel Cladding.

(CN-3066) [4.1, Table 4.1, and 4.2] {NEI 98-03)

2. Revised UFSAR Table 4.1-1 Fuel Pellet length from 0.462 inches to 0.500 inches.

(CN-3079) [Table 4.1-1]

3. Revised to add description of WCAP-7800 and Westinghouse Quality Management System (QMS). (CN-3090) [4.2.4.1 Reference 4.2-13] {NEI 98-03)

4. Updated BEACON reference to include NRC-approved addenda to WCAP 12472-P-A. (CN-3084) [Reference 4.3-43]

5. Updated Figure to show changes made to the location of control rods. (CN-31 11)

[Figure 4.3-36]

Chapter 5, "Reactor Coolant System and Connected Systems"

1. Castings - Corrected CR8A to CF8A (CN-3101) [Table 5.2-5] {NEI 98-03)

Chapter 6, "Engineered Safety Features"

1. Deleted obsolete information concerning the Reactor Containment Fan Cooler System enclosure pressure transient. (CN-3095) [6.2.2.2.1.1.3] {NEI 98-03)

Chapter 7. "Instrumentation and Controls"

1. Updated information regarding the replacement of safety related inverters to state the distribution panels are connected through a manually operated breaker located in each respective distribution panel. (CN-3112) [7.6.1.1, 7.6.1.2]

2. Removed information on AMSAC disarming time delay nonconformance. (CN-3063)

[7.8.2.13]

3. Removed turbine runback feature from UFSAR figures.(CN-3096) [Figure 7.2-5 and Figure 7.2-17] {NEI 98-03)

4. Revised to show spare in place for the Unit 1 Electrical Auxiliary Building air supply heater (CN-3093) [Table 7.3-5]

Attachment 1 NOC-AE-14003129 Page 3 of 5 South Texas Project Updated Final Safety Analysis Report Revision 17 Summary of Changes Chapter 8, "Electric Power"

1. STP does not take credit for the 345 kV Blessing transmission line as a credited source of offsite power. (CN-3099) [8.2.1.1.]

2. Updated information regarding the replacement of safety related inverters to state the distribution panels are connected through a manually operated breaker located in each respective distribution panel. (CN-3112) [8.3.1.1.4.5]

3. Restored information regarding hydrogen recombiners previously removed from the Updated Final Safety Analysis Report, however loads were not disconnected. (CN-3064) [Table 8.3-3 and Table 8.3-14]

4. Removed Tables 8.3-6a and 8.3-6b for the Unit I and Unit 2 125 vdc ESF Loads.

Referenced Calculation EC-5008. (CN-3088) [Table 8.3-6a and Table 8.3-6a] {NEI 98-03}

Chapter 9, "Auxiliary Systems"

1. Added a Unit 2 only designation for the Region 2 rack modules on the south end of the pool (modules #12 and #16) which have not been installed.(CN-3068) [9.1.2]

{NEI 98-03}

2. Corrected Spent Fuel Pool Temperature from 150OF to 150.7 0 F. (CN-3105)

[9.1.3.2.2.] {NEI 98-03}

3. Corrected the description of the Refueling Machine Hoist to identify enhancements to the system. (CN-3071) [9.1.4.3.1.2]

4. Moved the 2.5 mR/hr dose field limit from the water surface to the level of the operating deck. (CN-3100) [9.1.4.3.4]

5. Removed Spent Fuel Pool Cooling Pump design head. (CN-3069) [Table 9.1-2] {NEI 98-03}

6. Revised to state that not all pipe in the Essential Cooling Water System is aluminum-bronze. (CN-3078) [9.2.1.2.3]

7. Updated information for removal of the description for control room alarms for ECW pump lube strainer differential pressures for the ECW product lubricated pumps. (CN-3080) [9.2.1.2.5]

8. Removed references to the use of the Post-Accident Sampling System during normal operation to reflect current usage. (CN-3109) [9.3.2.1.2, 9.3.2.2.3.2, 9.3.2.2.4.2]

Attachment 1 NOC-AE-14003129 Page 4 of 5 South Texas Project Updated Final Safety Analysis Report Revision 17 Summary of Changes

9. Updated to remove Reactor Makeup Water Storage Tank and Component Cooling Water as systems that use the process sampling system. (CN-31 10} [Table 9.3-3]

10. Updated design information for new Technical Support Center Water Chillers. (CN-3089) [Table 9.4.2-1]

11. Updated to show a reduced number of chillers in operation in the Unit 1 Mechanical Auxiliary Building. (CN-3106) [9.4.3, Table 9.4-1 and Table 9.4-2.3]

12. Removed information related to the power rating for Essential Cooling Water Intake Structure heaters. (CN-3108) [Table 9.4-2.7] {NEI 98-03)

13. Removed reference to intake and exhaust louvers in the description for Essential Cooling Water Intake Structure ventilation system. (CN-3060) [9.4.7.2.1] {NEI 98-03}

14. Clarified information regarding physical separation of Chilled Water piping in the Electrical Auxiliary Building. (CN-3102) [9.4.1.3 paragraph 9]

15. Changed the responsibility for the Fire Protection Program and Fire Brigade training from Engineering to Plant Generation/Safety. (CN-3103) [9.5.1.6, 9.5.1.6.2]

16. Added information on the new touch screen Operator Console Panels.

(CN-3058) [9.5.2.2.1]

17. Added information regarding notification of Emergency Response Personnel by use of cellular phone. (CN-3104) [9.5.2]

18.

Changed private branch exchange (PBX) telephone system to telephone switch.

Changed GTE Southwest to Verizon Telephone. (CN-3114) [9.5, Figures 9.5.2-1 and 9.5.2-2]

19. Removal of the one inch relief request exemption from the UFSAR. (CN-3073)

[Appendix 9A]

20. Corrected the maximum flooding rate from 2.5 gpm to 2.3 gpm in the section titled "Combination with design basis accidents". This change was made for consistency.

(CN-3092) [Appendix 9A] {NEI 98-03}

Chapter 11, "Radioactive Waste Management"

1. Expanded the description of the Old Steam Generator Storage Facility to include the design features. (CN-3072) [11.4.2.3.4]

Attachment 1 NOC-AE-14003129 Page 5 of 5 South Texas Project Updated Final Safety Analysis Report Revision 17 Summary of Changes

2. Relocation of the on-site Storage Facility. (CN-3070) [11.4]

Chapter 12, "Radiation Exposure"

1. Expanded the description of radiological material of the Old Steam Generator Storage Facility to include additional source term information. (CN-3072) [12.2.1.4, Tables 12.1.2-11 and 12.1.2-12]

2. Correction to typographical errors Area Radiation Monitor ranges. (CN-3076) [Table 12.3.4-1] {NEI 98-03}

Chapter 15, "Accident Analyses"

1. Added information regarding the addition of impacts of secondary side leakage outside containment on the Main Steam Line Break, Low Radiation Area, Control Room Envelope and Steam Generator Tube Rupture accidents. (CN-3062) [15.1.5.3, 15.3.3.3, 15.4.8.3.2 and 15.6.3.3] {NEI 08-09}

2. Added information concerning Thermal Conductivity Degradation.(CN-3065)

[15.6.5.4.1 and Table 15.6-21]

3. Update sections to reflect Optimized ZIRLO Fuel Cladding. (CN-3066) [15.1, 15.3, 15.4] {NEI 98-03}

Response to NRC Questions Chapter 7

1. Removed turbine runback feature from UFSAR NRC Q & R.(CN-3096) [Q&R 032.22]

{NEI 98-03}

Chapter 9

1. Changed EPBAX to switch on Table 1 .(CN-3114) [Q&R 430.77N]