ML20133J933

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Submittal of Updated Final Safety Analysis Report, Revision 20
ML20133J933
Person / Time
Site: South Texas  
Issue date: 04/29/2020
From: Schaefer M
South Texas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML20133J932 List:
References
NOC-AE-20003721
Download: ML20133J933 (11)
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Text

Enclosure 4 contains Sensitive information and is being withheld from public disclosure in accordance with 10 CFR 2.390(d)(1).

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ATTN: 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 20 April 29, 2020 NOC-AE-20003721 10 CFR 50.71(e) 10CFR 2.390 File No. 043.01 STI: 35007975 Pursuant to 10 CFR 50.71(e), STP Nuclear Operating Company (STPNOC) hereby submits an update to the South Texas Project (STP) Updated Final Safety Analysis Report (UFSAR). This revision addresses changes made to the STP UFSAR since submittal of the last biennial update on April 30, 2018. to this letter includes a summary of changes made in Revision 20 under the provisions of 10CFR50.59 or in accordance with the guidance of NEI 98-03 and NEI 96-07. Enclosure 2 to this letter includes a listing of information being withheld from Public Disclosure. Enclosure 3 includes one DVD containing the redacted version of the STP UFSAR, Revision 20. Enclosure 4 to this letter includes one DVD containing the non-public version of the STP UFSAR. Enclosure 4 contains sensitive information as defined by 10 CFR 2.390(d)(1) and should be withheld from public disclosure.

There are no commitments in this letter.

If you have any questions concerning this submittal, please contact me at (361) 972-7888 or N.

Boehmisch at (361) 972-8172.

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

Executed on,J/_, 9 h-o:i.*

. * ~

~

- ~;;;~I Schaefer Site Vice President :

South Texas Project Updated Final Safety Analysis Report, Revision 20 Summary of Changes :

Information Redacted from the STP UFSAR Revision 20 :

Updated Final Safety Analysis Report, Revision 20 (Redacted - Public Version) :

Updated Final Safety Analysis Report, Revision 20 (Not for Public Disclosure)

cc:

Regional Administrator, Region 1v U.S. Nuclear Regulatory Commiss*ion 1600 E. Lamar Boulevard Arlington, TX 76011-4511 NOC-AE-20003721 Page 2 of 2 NOC-AE-20003721 South Texas Project Updated Final Safety Analysis Report, Revision 20 Summary of Changes

South Texas Project Updated Final Safety Analysis Report, Revision 20 Summary of Changes UFSAR Chapter 1, "Introduction and General Description of Plant"

1. Update dry cask storage related acronyms and definitions. (CN-3214) [Table 1.1-1, Sections 1.2.2.11.1.3.1, 1.2.2.11.1.4, 1.2.2.15]

Chapter 2, "Site Characteristics

1. Revised location of marker HF. (CN-3214) [Figure2.5.C-1]

Chapter 3, "Design Of Structures. Components, Equipment, and Systems

1. Add dry cask storage related SSCs quality classifications. Update description of cask loading connecting channel and pool lining and leak detection.

(CN-3214) [3.1.2.6.2.2, Table 3.2A-1, 3.8.4.1.3, 3.8.4.4.3]

2. Clarify acceptance criteria for "watertight" features in Flood Protection.

(CN-3246) [3.4.1.2]

3. Remove "Plasma" from display description. (CN-3260) [Table 3.10N-1]
4. Include discussion of Unit 2 MSIP. (CN-3284) [3.6.2.1.1; 3.6-39, 3.9.1.4.3]
5. Administrative correction, typo to "fail." (CN-3287) [3.1.2.3.4] {NEI 98-03}

Chapter 4, "Reactor"

<no changes>

Chapter 5, "Reactor Coolant System"

1. Include discussion of Unit 2 MSIP. (CN-3284) [5.1, 5.2.3.1, Table 5.1-1]

Chapter 6, "Engineered Safety Features~

1. Revise UFSAR Figure 6.2.4-1 (Containment Penetrations Sheet 53 of 100) to change valve type for CV0392 from BELL SEAL to GLOBE, remove asterisk.

(Cl\\l-3245) [6.2.4-1 sheet 53 of 100]

2. Updates to table 6.2.1.2-9 and 6.2.1.2-17 to incorporate design information.

(CN-3252) [Table 6.2.1.2-9, Table 6.2.1.2-17]

3. Update Reg Guide 1.52 comparison based on TS Amendment 215-201 implementation. (CN-3274) [Table 6.5-1]
4. Include discussion of Unit 2 MSIP. (CN-3284) [6A.1.2.3]

Chapter 7, "Instrumentation and Controls

1. Remove "Plasma" from display description. (CN-3260) [Tables 7.1-2, 7.4-1, 7.5-4, Sections 7.2.2.2.3.10, 7.4.1.9.1, 7.5.1.2, 7.5.6.1.1.1, 7.5.6.1.1.4, 7.5.6.1.2, 7.5.6.1.2.2, 7.5.6.1.2.3, 7A.II.F.2, 7B.3.2.1.4, Figures 7A.II.F.2-1, 7A.II.F.2-3]

Chapter 8. "Electric Power"

1. Reflect information for CROM fan motor replacement. (CN-3256) [Table 8.3-3]
  • 2. Correct administrative error that shows the rated horsepower for a residual heat removal pump as 30 instead of 300. (CN-3254) [Table 8.3-3]
3. Add Main Generator 100% stator ground detection capability. (CN-3262)

[8.2.1.5]

Page 1 of 3

South Texas Project Updated Final Safety Analysis Report, Revision 20 Summary of Changes Chapter 9, "Auxiliary Systems'*

1. Add interim dry cask storage and ISFSI descriptions. Upgrade cask handling*

crane to single failure proof for lifting DCSS components. Uodate obsolete description of dry cask storage operations. Add spent fuel dry cask storage.

Add spent fuel cask and transfer cask description. Cask Drop Accident is no longer a credible design basis accident. (CN-3214) [9.1, 9.1.2.2, 9.1.3.1.2, 9.1.3.2, 9.1.3.3.2, 9.1.4.1, 9.1.4.2, 9.1.4.2.3, 9.1.4.2.4.11, 9.1.4.3.1.6, 9.4.2.2.1]

2. Apply industry guidance and performance based maintenance and testing program to aa1ust testing and inspection frequencies commensurate with STP equipment performance history and reliability criteria. (CN-3263) [9.5.1.6.1]
3. Revise the definition of Fire Protection Engineer to meet Regulatory Guide 1.189 rev 3. and consistent with the FHAR. (CN-3272) [9.5.1.6]
4. Add minimum to the description of fire pump capacity rating. (CN-3268)

[9.5.1.2.1]

5. Apply industry guidance and performance based maintenance and testing program to adjust testing and inspection frequencies commensurate with STP equipment performance history and reliability criteria. (CN-3281) [9.5.1.6.1]
6. Revise material of open-loop duplex strainers for unit 2. (CN-3282) [9.2.1.1.2]

Chapter 10, "Steam and Power System Conversions"

1. Correct description of Automatic FW control inputs, by removing turbine impulse stage pressure. (CN-3277) [10.4.7.5] {NEI 98-03}

Chapter 11, "Radioactive Waste Management"

1. Clarify this chapter does not pertain to spent fuel storage. (CN-3214) J11.41 Chaoter 12, "Radiation Protection"
1. Add Independent Spent Fuel Storage Installation to design and ALARA considerations. Specifies that ISFSI is not zone 1. Transfer casks, overpack, and MPC-37 provide shielding for spent fuel. (CN-3214) [12.1.2.1, 12.1.3.5, 12.2.1.2, 12.3.2.1, 12.3.2.2.2, 12.3.2.2.2.4, 12.3.2.2.2.11, 12.5.3.2]

Chaoter 13, "Conduct of Operation's

1. Revised to remove reference (no longer used) and enhance the description of Security Plans, adding Cyber Security Plan. (CN-3244) [13.6} {NEI 98-03}

Chapter 14, "Initial Test Program"

<no changes>

Page 2 of 3

South Texas Project Updated Final Safety Analysis Report, Revision 20 Summary of Changes Chapter 15, "Accident Analyses"

1. Reflect changes in fuel peak.clad temperature (Pen in the emergencv core cooling system (ECCS) model. (CN-3243) [Table15.6-21] {NEI 98-03}
2. The single-failure proof cask handling crane renders the spent fuel cask drop accident not credible. (CN-3214) [15.7.5, Figure 15.0-30]
3. Incorporate revised HZP MSLB core response analysis with RCCA D-o removed. (CN-3276) [15.1.5.2, 15.1.5.3, 15.1.5.4, Tables 15.1-1, 15.1-2, Figures 15.1-11, 15.1-14, 15.1-15, 15.1-16, 15.1-17]
4. Enhance understanding for when cool down ends, and clarify MSIV above seat drain. (CN-3286) [15.1.4.4, 15.6.3.3, 15.6.3.5, Tables 15.1-2, 15.3-3, 15.6-5] {NEI 98-03}

Chapter 16, "Technical Specifications"

<no chanpes>

Chapter 17, "Quality Assurance"

<no changes>

Chapter 19A - "License Renewar

1. Update EPRI Primary and Secondary water chemi~try guidelines. (CN-3250}

(19A.1.2]

2. Update EPRI Closed Cooling Water Chemistry Guidelines. (CN-3253)

[19A.1.10]

3. Correction of Introduction text and page numbering throughout the chapter.

(CN-3267) [19A.O] {NEI 98-03}

NRC Q&R's

1. The single-failure proof cask handling crane renders the spent fuel cask drop accident not credible. The related information is designated Historical. (CN-3214) [Ch 15 Question 211.42] {NEI 98-03}
2. Operator Actions originally taken from RESAR 414 are superseded by the analysis in WCAP-12476. The related information is designated Historical.

(CN-3266) [Ch 6 Question 211.32] {NEI 98-03}

Page 3 of 3 NOC-AE-20003721 Information Redacted from the STPEGS UFSAR Revision 20

NOC-AE-20003721 Page 1 of 3 Information Redacted from the STP UFSAR Revision 20 Aoril 2020 In accordance with the request in Regulatory Issues Summary 2015-17, "Review and Submission of

  • Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Oocuments." the South Texas Project is providing a redacted version of Revision 20 to the South Texas Project Updated Final Safety Analysis (UFSAR). The UFSAR contains certain sensitive information. Using the guidance provided in SECY-04-0191, the information listed below has been redacted.

Document Number Justification for Withholding Figure 1.2-3, Plot Plan Figure shows "vital area.boundarv" fencing Figure 1.2-4, Plot Plan Figure shows "vital area boundary" fencing Table 2.4.1-1 Contains design information on nearby dams Table 2.4.1-2 Contains design information on nearby dams

  • Table 2.4.1-3 Contains design information on nearby dams Table 2.4.1-4 Contains design information on nearby dams Table 2.4.1-5 Contains design information on nearby danis Table 2.4.1-6 Contains desian information on nearby dams Table 2.4.1-7 Contains design information on nearby dams
  • Table 2.4.1-8 Contains design information on nearby dams Table 2.4.1-9 Contains desian information on nearby dams Table 2.4.1-10 Contains design information on nearby dams Table 2.4.1-11 Contains design information on nearby dams Table 2.4.1-12 Contains desian information on nearby dams Table 2.4.1-13 Contains design information on nearby dams Table 2.4.1-14 Contains design information on nearby dams Table 2.4.1-15 Contains desian information on nearby dams Table 2.4.1-16 Contains design information on nearby dams Table 2.4.1-17 Contains design information on nearby dams Table 2.4.1-18 Contains design information on nearby dams

. Table 2.4.1-19 Contains design information on nearby dams Table 2.4.1-20 Contains design information on nearby dams Table 2.4.1-21 Contains design information on nearby dams Table 2.4.1-22 Contains design information on nearby dams Table 2.4.1-23 Contains design information on nearby dams Table 2.4.1-24 Contains design information on nearby dams Figure 6.2.1.2-3 Subcompartment analysis drawings that show equipment locations, doorways, stairways Figure 6.2.1.2-4 Subcompartment analysis drawings that show equip~ent locations,. doorways, stairways Figure 6.2.1.2-5 Subcompartment analysis drawings that show equipment locations, doorways, stairways Figure 6.2.1.2-6 Subcompartment analysis drawings that show equipment locations, doorwavs, stairways Figure 6.2.1.2-7 Subcompartment analysis drawings that show equipment locations, doorways, stairwavs

l Document Number I

Figure 6.2.1.2-9 i

! F,gure 6.2.2-3 Figure 6.2.2-6 Figure 6.2.2-7 Figure 6.2.2-8 Figure 6.2.2-9 Figure 6.2.2-10

  • Figure 6.2.2-11 Figure 6.2.2-12 Figure 6.4-1 Figure 6.4-2 Figure 9.5.1-40 Fiaure 9.5.1-41 Figure 9.5.1-42 Fiaure 9.5.1-43 Figure 9.5.1-44 Figure 9.5.1-45 Figure 9.5.1-46 Figure 15.0-7 FiQure 15.0-8 Figure 15.0-9 FiQure 15.0-10 Fiaure 15.0-11 Figure 15.0-12 Fiaure 15.0-13 Figure 15.0-14 Figure 15.0-15 Figure 15.0-16 Fiaure 15.0-17 Figure 15.0-18 Figure 15.0-19 Fiaure 15.0-20 Fiaure 15.0-21 Figure 15.0-22 Information Redacted from the STP UFSAR Revision 2u

! Justification for Withholding NOC~AE-20003721 Ei,ciosure 2 Page 2 of 3 Subcompartment analysis drawings that show equipment locations, doorways, stairways

. Reactor Building composite piping drawings that show eauioment locations Reactor Building Containment Spray System spray coverage drawings that show equipment locations, doorways, stairways, Reactor Building Containment Spray System spray coverage drawings that show equipment locations, doorways, stairways, Reactor Bui!ding Containment Spray System spray coverage drawings that show eauioment locations, doorways, stairwavs, Reactor Building Containment Spray System spray coverage drawings that show equipment locations, doorways, stairways, Reactor Building Containment Spray System spray coverage drawings that show equipment locations, doorways, stairways, Reactor Building Containment Spray System spray coverage drawinas that show eauioment locations, doorways, stairwavs, Reactor Building Containment Spray System spray coverage drawings that show equioment locations, doorwavs, stairwavs, Control Room layout drawings showing equipment locations and doorways.

Control Room layout drawings showing equipment locations and doorways.

Equipment location Eauioment location Equipment location Eauipment location Equipment location Equipment location Eauioment location Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode

I Document Number J>>i~ure 15.0-23 r Figure 15.0-24 1 (:.i,ure 15.0-25 Fiaure 15.0-27 Figure 15.0-28 Figure 15.0-29 Fiaure 15.0-30 Figure 15.0-31 Information Redacted from the STP UFSAR Revision 20 I Justification for Withholding Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure Mode Failure l\\iloae Failure Mode liOC-AE-20003721 E:1ciosure 2 Page 3 of 3

-~-*

l-Updated Final Safety Analysis Report, Revision 20 (Redacted - Public Version)

,_.OC-AE-20003721 f::1ciosure 3

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