NOC-AE-00038, Forwards Rev 6 to STP Ufsar,Including Corrections Identified in Accuracy Review Initiated Beginning in 1996

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Forwards Rev 6 to STP Ufsar,Including Corrections Identified in Accuracy Review Initiated Beginning in 1996
ML20198C527
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 12/15/1998
From: Cloninger T
HOUSTON LIGHTING & POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20198C535 List:
References
ST-NOC-AE-00038, ST-NOC-AE-38, NUDOCS 9812220101
Download: ML20198C527 (38)
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Text

. ear Opera g ompany EW E m South Tcus1%yettEkctrk Gener:rtmpSt.utxm PO &w239 nkdsmwth Teus77431 w_

December 15,1998 ST-NOC-AE-000381 STI: 30783583 File No.: GIO 10CFR50.71 U. S. Nuclear Regulatory Commission Attention: Docu. ent Control Desk

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 6 Pursuant to 10CFR50.71, the South Texas Project (STP) submits Revision 6 to the South Texas Project Updated Final Safety Analysis Report (UFSAR) as Attachment 3. Attachment 2 includes a summary of changes in UFSAR Revision 6 that were made unde the provisions of 10CFR50.59.

Beginning in 1996, STP Nuclear Operating Company initiated an accuracy review of the STP UFSAR. This review is essentially complete. None of the areas for correction identified in the review were found to affect operability or to be reportable. Revision 6 of the UFSAR includes conections identified during that review. Some additional areas for correction being tracked in the station's Corrective Action Program may result in future changes in the UFSAR. STPNOC expects to submit an interim update to the UFSAR during 1999 that will incorporate such changes.

Ten copies of Updated Final Safety Analysis Report, Revision 6 and the STP Controlled Drawing Manual are provided under separate cover in accordance with the distribution requirements of 10CFR50.4(b)(6). A copy of this transmittal is attached to each Updated Final Safety Analysis Report copy.

If you should have any questions on this submittal, please contact Mr. A. W. Harrison at 2) 972-7298 or me at (512) 972-8787.

T.11. Clo nger Vice Pr -ident

$~ *3 Engi erin and Techn cal Serv ces AWH/

Attachment 1: Affidavit Attachment 2: Updated Final Safety Analysis Report Changes Made under the Provisions of 10CFR50.59 Attachmcat 3: Updated Final Safety Analysis Report, Revision 6 Attachment 4: STP Controlled Drawing Manual 9@

9812220101 981215 PDR ADOCK 05000498 K PDR jg

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NOC-AE-000381 File No.: G10 Page 2

  • Ellis W. MerschofT- Jon C. Wood Regional Administrator, Region IV Matthews & Branscomb

, U. S. Nuclear Regulatory Commission One Alamo Center 611 Ryan Plaza Drive, Suite 400 106 S. St. Mary's Street, Suite 700 Arlington, TX 76011-8064 San Antonio,TX 78205-3692 Thomas W. Alexion Institute ofNuclear Power Project Manager, Mail Code 13H3 Operations - Records Center U. S. Nuclear Regulatory Commission 700 Galleria Parkway Washington, DC 20555-0001 Atlanta, GA 30339-5957 )

  • Cornelius F. O'Keefe Richard A. Ratliff Sr. Resident Inspector Bureau of Radiation Control c/o U. S. Nuclear Regulatory Comm. Texas Department of Health P. O. Box 910 - 1100 West 49th Street Bay City, TX 77404-0910 Austui, TX 78756-3189 i

J. R. Newman, Esquire D. G. Tees /R. L.Balcom Morgan, Lewis & Bockius Houston Lighting & Power Co.

1800 M Street, N.W. P. O. Box 1700 1 Washington, DC 20036-5869 Houston, TX 77251 l M. T. Hardt/W. C. Gunst Central Power and Light Company City Public Service ATTN: G. E. Vaughn/C. A. Johnson l P. O. Box 1771 P. O. Box 289, Mail Code: N5012

( San Antonio,TX 78296 Wadsworth,TX 77483 l A. Ramirez/C. M. Canady *U. S. Nuclear Regulatory Commission I City of Austin Attention: Document Control Desk

[ Electric Utility Department Washington, D.C. 20555-0001 721 Barton Springs Road l

Ausdn,TX 78704

  • The above copies distributed without Attachments 3 & 4 except as noted by the asterisk l

L

n w e-n. --a J-- - -c .-- A Attachment 1 Affidavit 4

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter )

)

STP Nuclear Operating Company, et al., ) Docket Nos. 50-498

) 50-499 South Texas Project Units 1 and 2 )  ;

1 AFFIDAVIT  ;

1 I, T. H. Cloninger, being duly sworn, hereby depose and say that I am Vice President, Engineering and Technical Services, of STP Nuclear Operating Company; that I am duly authorized to sign and file with the Nuclear Regulatory Commission the attached transmittal of Revision 6 of the South Texas Project Updated Final Safety Analysis Report; that I am familiar '

with the content thereof; and that the matters set forth therein are true and correct to the best of my knowledge and belief.

T

$W1

. Cloninger r JW '

ce President l ngineering and T chnical ervices STATE OF TEXAS )

) l COUNTY OF /1A TAGMDA )

Subscribed and sworn to before me, a Notary Public in and for the State of Texas, this 15th < lay of December,1998.

f"% UNDARITTENBERRY Not un A [&6

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( Notary Public in and for the Sthfe of Texas OCT. 0,2001 l

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O Attachment 2 i

Updated Final Safety Analysis Report

Changes Made under the Provisions of i 10CFR50.59 ,

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Updated Fin:1 Safety Anilysis R: port, R vision 6 1

, Chapter 1. " Introduction and General Description of Plant" V

1. Added new sectica to provide criteria for making non-consequential changes to drawings without a USQE. (CN-2266) [1.1.3.2]
2. Corrected the number ofinverters and battery chargers that power the four independent charmels of the Class IE 125 volt DC system for consistency with license amendment 73/62.

(CN-2103) [1.2.2.7.2]

3. Changed the list of systems that are supplied demineralized water by the Reactor Makeup Water system for consistency with section 9.2.7. Editorial correction (CN-2092) (CN-2345)

[1.2.2.10.5]

4. Changed the name of the diesel generator cooling water system for consistency with section 9.5.5. (CN-2088) [1.2.2.11.8]
5. Corrected misspelling of"Supergrouping". (CN-2088)[ Table 1.6-1]
6. Added the Mobile Filtration Demineralizer components. (CN-2160)[ Figure 1.2-27]
7. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[1.1.1, Table 1.1-1,1.4.2]

8. Clarified text description for various communication system. (CN-2268) [1.2.2.11.6]

O V 9. Added clarifying phrase that optical clarity of the reactor cavity water is maintained by use of the Reactor Cavity Filtration System for Unit 1 only. (CN-2271) [1.2.2.11.1.4]

10. Updated lists of Electrical and I&C drawings specified in Table 1.7-1,1.7-2 and 1.7-3 including addition of unit designation column. (CN-2279)

. Chapter 2. " Site Characteristics"

1. Clarified that a plant shutdown is not required by Technical Specifications until the Main Cooling Reservoir level is less than 25.5 feet. (CN-2174) [2.4.14]
2. Changed " levels" to " levees" - editorial. (CN-2183) [2.4.9.1, 2.4.9.3]
3. Editorial changes to reficct the transfer of operating responsibility to STPNOC. (CN-2249)

[2.1.2.1)

4. Corrected inconsistencies between UFSAR and actual plant configuration / operation involving the Main Cooling Reservoir and the Essential Cooling Pond. (CN-2280) [2.4.1.1, 2.4.11.1,2.4.13.1.4,2.5.6.1.1,2.5.6.1.2]

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- Page 1 of 18 -

Updited Final Srfety An: lysis R: port, Revision 6 l 5. Updated industrial facilities and transportation descriptions, and corrected editorial errors, in O UFSAR Secuon 2.2, Nearby Industrial, Transportation, and Military Facilities. (CN-2285)

[2.2. L4.2, 2.7.2.1, 2.2.2.3, 2.2.2.4, 2.2.2.6, 2.2.3.1.1, 2.2.3.1.2, 2.2.3.1.4.1, 2.2.3.1.4.2, 2.2.3.1.5, Table 2.2-1, Figure 2.2-1]

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6. Updated total plant well water usage flow rate to agree with updated flow rate specified in revised (by ClT-2280) Section 2.4.13.1.4. (CN-2307) [2.5.4.6.8 and 2.5.1.2.9.6.5] l l

Chapter 3. " Design of Structures. Components. Eauipment and Systems"

1. Corrected description of spent fuel pool discharge to include sparger pipe. (CN-2067)

[3.1.2.6.2.2]

2. Removed reference to Essential Cooling Water Intake Structure Gantry Crane as a result of hardware modification. (CN-1960) [ Table 3.2.A-1,3.8.4.1.4]
3. Corrected Residual Heat Removal system diawings to indicate that pipe whip restraints are installed on both units. (CN-2228) (Figure 3.6.1-1 Sheets 8A,8B, and 8C]
4. Corrected typographical errors in equation variables. (CN-2213) [3.7.3B.I.1,3.7.3B.I.2, Table 3.2.B2]

g 5. Deleted duplicate definition of Pipe Rupture 1. cads (Y)- editorial. (CN-2167) [3.8.1.3.1]

V 6. Corrected typographical errors in stress analysis results. (CN-2168,2169,2170) [ Table 3.8.1-7B]

7. Clarified Inservice Testing Program requirements for pumps and valves. (CN-2135) [3.8.2.7, l 3.9.3.2.1.1, 3.9.6.1, 3.9.6.2] I
8. Corrected description of cask handling area in the Fuel Handling Building to indicate that the l stainless steel liner has not been installed. (CN-2151) [3.8.4.1.3,3.8.4.4.3] l
9. Removed reference to " design pressure" in psig for the Auxiliary Feedwater Storage Tanks and left reference to the equivalent pressure in inches of water column. (CN-2229)  ;

[3.8.4.4.7] j

10. Removed a non-existent stmeture and associated elevations from the plan for consistency with as-built plant and general arrangement drawings. (CN-2229) [ Figure 3.8.4-1]
11. Removed the " actual" system pressure used for the primary side leakage test to avoid potential conflicts with ASME Section XI requirements. (CN-2201) [3.9.1.1.6.12]
12. Removed reference to Chiller Supply Header check valves for Unit I due to a hardware modification that removed the valve internals. (CN-2147) (Table 3.9-1.2]

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Updated Final Safety Analysis Report, Revision 6

13. Listed the exceptions to the Regulatory Guide 1.25 assumptions used for the fuel handling O accident ie the neector Centaiement 8eiidi 8 wnen exteeded ser ePf ei is ioeded. <C"-

2149) [ Table 3.12-1]

14. Replaced " Westinghouse" with "STPEGS" for Regulatory Guide 1.121 and deleted the exception to Regulatory Guide, Positions C.2.a(2) and C.2.a(4) because their use is not anticipated. (CN-2181)[ Table 3.12-1]
15. Updated commitment to Regulatory Guide 8.29 from Revision 0 to Revision 1. (CN-2164)

[ Table 3.12-1]

16. Corrected IEEE-388 to IEEE-338 in Note 69 (typographical error). (CN-2212) [ Table 3.12-1]
17. Corrected typographical and formatting errors. (CN-2088) [ Table 3.12-1]
18. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[3.1.1, 3.1.2.1.1.1, 3.2.C.1, Table 3.2.C-1, 3.6. A.6, 3.6. A.7, Table 3.12-1]

19. Revised Table 3.12-1 to delete notes that are not used and added a note that refers to the Operations Quality Assurance Plan to provide the current status regarding certain Regulatog Guides. (CN-2223)[ Table 3.12-1]
20. Corrected typographical / editorial errors, and provided clarifications where deemed necessary, to text, tables and figures associated with Section 3.4.1, Flood Protection. (CN-2128)

[3.4.1.1,3.4.2.2.1.1,3.4.3.2, Table 3.4-1, Figure 3.4-2]

21. Corrected editorial errors, and provided clarifications where deemed necessary, to text involving cranes and stmetures. (CN-2240) [3.8.1.3.1,3.8.3.1.6,3.8.3.1.7,3.8.3.3.3.1, 3.8.3.5.2]
22. Corrected typographical / editorial and format errors in, and provided clarifications for, Section 3.9.3. (CN-2237) [3.9.3.1.2.2,3.9.3.2.1.1,3.9.3.2.1.2,3.9.3.4.1, Table 3.9-6]
23. Removed Essential Cooling Water Check Valves EWO262, EWO263 and EW0264 from Table 3.9-1.2. (CN-2166) [ Table 3.9-1.2]
24. Corrected the RCS temperature at which refueling may be started from "less than 150 F' to "140 F or less". (CN-2289) [3.9.1.1.6.10]
25. Corrected erroneous information concerning the non-safety related space heaters in the ECWIS Ventilation System. (CN-2214)[ Table 3.11-1]
26. Corrected editorial errors, and clarified text descriptions, in Section 3.9.1.2.2. (CN-2302)

[3.9.1.2.2.1,3.9.1.2.2.8,3.9.1.2.2.11,3.9.1.2.2.12,3.9.1.2.2.13 and 3.9.1.2.2.27]

27. Revised Table 3.12.1, Note 26 regarding performance testing for batteries. (CN-2265)

] 28. Added clarifying note to Tables 3.2.B-2 Notes to indicate that Reactor Cavity Filtration System components listed in Table 3.2.B-1 are installed in Unit 1 only. (CN-2271)

- Page 3 of 18 -

Updited Finil Sity AnIlysis Report, Rsvisirn 6 O ca 9ter 4 "ae c'e<"

1. Added reference to the VANTAGE + fuel assembly which includes ZIRLO fuel cladding, intermediate spacer grid straps, guide tubes, and instrument tubes; a protective bottom grid design; and longer fuel rod end plugs. (CN-2197) [4.1, Table 4.1-1,4.2,4.2.1,4.2.1.1, 4.2.1.3, 4.2.1.4, 4.2.1.5, 4.2.2, 4.2.2.1, 4.2.2.2, 4.2.2.2.1 a, 4.2.2.2.2a, 4.2.2.2.3, 4.2.2.2.4, 4.2.3.1, 4.2.3.5.1, Figure 4.2-1, Figure 4.2-2B, Figure 4.2-3, Figure 4.2-5A, Figure 4.2-5B, Table 4.3-1]
2. Removed reference to negative temperature moderator coefficient in previous fuel cycles.

Removed cycle specific detail from fuel rod diagram. (CN-2136) [4.2.2.3, Figure 4.2-3]

3. Revised description of secondary neutron sources to reflect double encapsulation as a result of hardware modification. (CN-2125) [4.2.2.3.3, Figure 4.2-14]
4. Deleted duplicate line - editorial. (CN-2163) [4.2.2.3.3b]
5. Added brief discussion of incomplete control rod insertion experienced in recent fuel cycles  ;

and editorial corrections. (CN-2133) [4.2.3.5.2,4.2.3.6]

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6. Changed 'he frequency of partial movement checks of the rod control cluster assemblies for consistency with the Technical Specifications. (CN-2116) [4.2.4.3]
7. Changed the description of new fuel rod and control rod inspections to reflect current practices. (CN-2137)[4.2.4.6]

Chapter 5. " Reactor Coolant System and Connected Systems"

1. Changed the ASME Code Class I component requirements for preservice examination and the first 10 years ofinservice examination and inservice testing for consistency with the response to UFSAR Question 121.5. (CN-2189) [5.2.4]
2. Deleted reference to heat exchangers as there are none as part of the ASME Code Class I boundary. (CN-2189)[5.2.4.1]
3. Clarified the 4 inch nominal pipe size exemption applicable to the internal inspection of ASME Code Class 1 valves versus the generic 1 inch nominal pipe size exemption for other valve examinations. (CN-2189) [5.2.4.2.6]
4. Clarified that approved ASME Code Cases may be used to satisfy system pressure test requirements of ASME Code Section XI. (CN-2189) [5.2.4.7]
5. Changed the Unit 1 primary-to-secondary leakage limit for consistency with license amendment 83. (CN-2163) [5.2.5.1.2]

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L

1 Updated Final Sr.fety An-lysis Report, Revision 6 I

6. Clarified compact tension (CT) testing requirements for reactor vessel specimens to indicate 0s as desirabie". (CN-2134) [5.3.1.e,5.3.2.13

.7. Updated the reactor vessel material properties and parameters related to pressurized thermal shock to reflect the analysis results of the most recent surveillance capsule. (CN-2178) [5.3 References, Table 5.3-3, Table 5.3-7]

8. Updated the discussion of Steam Generator tubing corrosion control to reflect current practices and added a discussion of F* criteria and voltage based repair limits for consistency with recent license amendments. (CN-2181) [5.4.2.1.3,5.4.2.2,5.4.2.3]
9. Changed the description of when the Residual Heat Removal system is placed in operation to remove the four hour requirement after reactor shutdown and replace .vith following reactor shutdown. (CN-2094) [5.4.7.1,5.4.7.2.3, Figure 5.4-7 Notes]
10. Clarified diat the Low Head Safety Injection pumps are used to fill the reactor cavity prior to refueling. (CN-2155)[5.4.7.2.3]
11. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[5.2.3.3.1, 5.2.3.4.1, 5.3.1.3.1]

12. Corrected editorial errors, and inputted minor format changes for clarity, in Table 5.4.A-2.

(CN-2297) [ Table 5.4.A-2]

13. Corrected the description of the RCP anti-reverse rotation device to reflect actual design as shown on RCP Motor Drawing 0125(01)00107-BWN. (CN-2098) [5.4.1.3.9]
14. Incorporated "Y" capsule surveillance test data and best estimate weld wir chemistry, updated WCAP reference numbers to "14849" and "14980", added reference to CE Report NPSD-1039. (CN-2292) [5.3, Table 5.3-4, Table 5.3-8]
15. Corrected the RCS temperature at which refueling may be started from "less than 150 F' to "140 F or less", and corrected erroneous RCS cooldown duration in Table 5.4-7. (CN-2289)

[5.4.7.2.3, Table 5.4-7]

16. Corrected erroneous description of the mass input considerations for the low temperature overpressure transients. (CN-2274)[5.2.2.11.2]
17. Added clarifying statement of power lockout feature employed on valves

-A1(2)RHMOV0066A and B. (CN-2257)[5.4.7.2.4]

- 18. Revised description of RHR suction isolation valve operation to reflect removal of auto-closure interlock. (CN-2301) [5.4.7.1,5.4.7.2.1,5.4.7.2.4]

19. Revised Table 5.1-1 to indicate the range of RCS liquid volume and the range RCS pressure drop across the steam generators due to steam generator tube plugging from 0% to 10%.

(CN-2194) [ Table 5.1-1]

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Upd:ted Fin:1 Ssf:ty Analysis RIport, Rsvisirn 6

' 20. Added text statements and table information to indicate that steam generator defective tubes O max be regaired by iaser welded sieeves. (CN-2194) [5.2.3.3. 5.4.2.1.i. 5.4.2.1.4,5.4.2.2 and Table 5.2-2] l

21. Added clarifying note to indicate that RCS volume ranges, PCS thermal / hydraulic data, and RCS pressure drops specified on Table 5.1-1 are nominal & agn values only and will vary as l a result of steam generator tube plugging, changes in RCS flow rates and RCS full load '

operating temperatures. (CN-2100) [ Table 5.1-1] ,

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Chapter 6. " Engineered Safety Features" l

l. Added transndttalletterreference number. (CN-2088)[6.1.2.1]

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2. Added reference to General Design Criteria (GDC) for fluid lines penetrating containment, valve numbers, and additional isolation valves; corrected valve type, normal position, fail position, and electrical train designation; corrected branch line connection points, and provided component name to which the main lines connect. (CN-2123) [6.2.4.2, Figure j 6.2.4-1] '
3. Changed the Main Steam Isolation Valve closing time for consistency with Table 16.1-1.

(CN-2146) [Figme 6.2.4-1 sheets 2,3,4, and 5]

4. Corrected calculated peak differential pressures, time to peak differential pressures, and j design margins for short-term Main Steam Line Break in the Reactor Containment Building subcompartment analysis.

(CN-2120) [ Table 6.2.1.2-13]

l 5. Deleted reference to section 1.3.1 because the referenced material has been removed. (CN-2088)[6.3.1]

6. Revised the maximum allowable boron concentration, following one hour after shutdown, to 3500 ppm to allow for rod drop testing and to prepare for refueling activities. (CN-2142)

[6.3.2.5,6.5.2.3, Table 6.5-3]

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7. Clarified Inservice Testing Program requirements for valves. (CN-2135) [6.3.4.2.1, Table 6.3-11]
8. Corrected boron concentration limits for Refueling Water Storage Tank and Accumulators l for consistency with license amendment 54/43. (CN-2127) [ Table 6.3-1, Table 6.3-9, Table 6.5-4]
9. Corrected boron concentration limits for Refueling Water Storage Tank and Accumulators that were erroneously changed by CN-2127. (CN-2288) [ Table 6.3-1, Table 6.3-9, Table 6.5-4]
10. Corrected description of instrumentation from " pressure differential indicating transmitter" to

" pressure differential transmitter" for the Fuel Handling Building Exhaust Subsystem. (CN-2088)[6.5.1.5.1]

- Page 6 of 18 -

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Updtted Fin 1 Sr.fety Analysis R: port, R:visi n 6

11. Editorial changes to reflect the transfer of operating asponsibility to STPNOC. (CN-2249)

~O. [e.1.2.1, Tabie e.1-3, e.2.1.4.7]

12.- Added statement concerning monitoring of cable quality in the RCB for organic decomposition effects. (CN-2222)[6.1.2.2]

L I Chapter 7. " Instrumentation and Controls" l 1. Corrected a subscript on the time constants defined for the Overtemperature AT trip. (C * -

2207) [7.2.1.1.3.2.a]

l 2. Deleted turbine trip for on low electrohydraulic control fluid pressure as a result of a hardware modification. (CN-2117,2159)[ Figure 7.2-17] i i

3. Clarified how equipment qualification is used to ensure that plant equipment are always capable of performing their safety function. (CN-2069) [7.3.1.2.2.5.2]
4. Added that testing of the containment sump isolation valves requires that the Refueling l - Water Storage Tank be isolated from the safety injection train being tested. (CN-2112)

[7.3.1.2.2.5.4.7] <

t 5. Corrected system designation from CV to CH for Chilled Water Outlet Valve TV-9497A and TV-9497B. (CN-2088,2179) [ Table 7.3-5]

6. Corrected mispagination and duplication of components listed for the Auxiliary Shutdown l

. Panels. (CN-2212) [ Table 7.4-2]

7. Changed the instrument range for letdown flow from 0-500 gal / min to 0-300 gal / min in Unit 1 as a result of a hardware modification. (CN-1411) [ Table 7.5-1]
8. Clarified that the C-20 permissive setpoint (ATWS Mitigation System Actuation Circuitry; AMSAC)is approximately 40% reactor thermal power which is determined by measuring the first stage turbine impulse pressure. (CN-2243) [7.8.1.1.9]
9. Changed the time required to purge the Auxiliary Feedwater lines during the Rupture of Main Feedwater Pipe for consistency with UFSAR section 15.2.8. (CN-2238) [7.A.II.E.1.1]
10. Deleted reference to Q&R 022.5 because Q&R 022.5 was previously removed. (CN-2123)

[7A.II.E.4.2]

t j - 11. Corrected the numbers of UFSAR sections referenced. (CN-2088) [7.A.III.D.3.4]

1 i 12. Updated the description of the Detailed Control Room Design Review to include the j: operational phase Control Room Design Review Program. (CN-2216) [7.A.S.5]

i 13. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

. [7.1.2.7, 7.7.1.9.2, I. A.1.2, I. A.1.3, I.C.1, I.C.2, I.C.3, I.C.4, I.C.5, I.C.6, I.C.7, I.C.8, I.G.1, h

i II.B.3, II.K.3.3]

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,- 9'Tyr # - -

l Upd ted Fin:1 S:f:ty An: lysis Report, R: vision 6 n 14. Changed the on-line testing description of the RHR isolation valve pressure interlocks. (CN-() 2300)[7.6.2.2]

l

15. Corrected Clarification (6) of STPEGS Responses on Page 7A.II.E.3.1-3 for Class IE interfaces for main and control power for the two pressurizer heater banks. (CN-2291)

[ Appendix 7A, Item II.E.3.1)

16. Revised Position (3) of STPEGS response on Page 7A.II.E.3.1-2 concerning pressurizer heater manual start time after LOOP if an SI signal is not present. (CN-2290) [ Appendix 7A, Item II.E.3.1]
17. Revised text description for communications to specify Operator Communications Panels, instead of dedicated telephones. (CN-2268) [7.4.1.9.4]
18. Changed Table 7.3-5 system designator for SDG Feeder Breaker from 'SP' to 'PK', and system designator for ESF Load Sequencer from 'SP' to 'SF'. (CN-2294) [ Table 7.3-5] l
19. Revised / clarified text description for solid-state logic testing time limits and methodology.

(CN-2295) [7.2.2.2.3.10]

20. Corrected specified voltage variance from "il10 percent" to "i10 percent" on Page 7A.S.8-
14. (CN-2263) [ Appendix 7A, STPEGS Response for Technical Support Center (TSC)]
21. Revised description of RHR suction isolation valve operation to reflect removal of auto-(w) closure interlock. (CN-2301) [7.6.6.4]

Chapter 8. "E!ectric Power"

1. Changed the description of the Electric Reliability Council of Texas and South Texas Interconnected System to reflect current members and planning criteria. (CN-2217)[8.1.1, 8.2.1,8.2.2.2, Table 8.2-3]
2. Corrected the wording for the breaker interrupting capability because the value given is the minimum acceptable rating, not a maximum. (CN-2200)[8.2.1.2]
3. Changed switchyard bus and circuit breaker arrangement information, protective relaying, and incoming 345 kV lines from owner facilities to reflect current configuration including a pilot wire transfer tripping hardware modification. (CN-2244) [8.2.1.2,8.2.1.4, Figures 8.2-1,8.2-2,8.2-2A,8.2-3 and 8.2-3A]
4. Clarified that the rate-of-pressure relay (63SP/ET) is for monitoring (i.e., alarm) and not a protective function. (CN-2231)[8.2.1.4]
5. Changed the description of the switchyard circuit breakers to reflect replacement of the existing breakers with breakers that store energy in a compressed spring instead of compressed air for breaker closure. (CN-2200) [8.2.6.1]

b(~'

- Page 8 of I8 -

Upd ted Finil Sifety Analysis Report, Revisi:n 6

6. Corrected tne aumber of battery chargers that power the four independent channels of the  ;

Class IE 125 volt DC system for consistency with license amendment 73/62. (CN-2103)

[8.3.2.1.1]

7. Clarified that the Channel II a ad III Class IE 125 volt DC system battery chargers are mechanic'a lly interlocked, and the Channel I and IV battery chargers are administratively controlled, to prevent parallel operation of the two battery chargers in each channel. (CN-2215)[8.3.2.1.1]
8. Clarified the intent of Table 8.3-6 by specifying the calculated 125 VDC battery loading without including margin used for surveillance test acceptance values. (CN-2162,2225)

[8.3.2.1.2, Table 8.3-6]

9. Moved " LOOP" and " Emergency Shutdown" from the " Plant Operating Mode" column to the " General Remarks" column because these terms are not plant operating modes. (CN-2173)[ Table 8.3-9]
10. Added protective devices for a 480 volt receptacle installed for a jib crane inside the Reactor Containment Building to reflect hardware modification. (CN-2077,2156) [ Table 8.3-14]
11. Added protective devices for a 480 volt receptacle installed for a 2nd jib crane inside the Unit 1 Reactor Containment Building to reflect hardware modification. (CN-2140) [ Table 8.3-14]
12. Revised protective device number and location for Reactor Coolant pump oil lift pumps to O refiect chaesin8 the gewer eeerce te switch8ear feedins the reeeective Reacter Ceeiant pump. (CN-2052,2141) [ Table 8.3-14]
13. Revised breaker setting for two motor opeated valves located inside Containment to reflect hardware modification. (CN-2095,2157)[ Table 8.3-14]
14. Corrected typographical errors in tag numbers and breaker ratings, i.e., latters 0, I, and L y used instead of numbers 0 and 1. (CN-2212) [ Table 8.3-14]
15. Corrected electrical component designations and main generator reactance values. (CN-2263) [8.2.1.4,8.3.1.1.3 and Table 8.2-2]
16. Added the word " nominal" to the stated float voltage of 130 Volts. Added "as noted in Section 8.3.2.2.5" after tested in accordance with Technical Specifications. Deleted sentence regarding " testing in accordance with RG 1.129 is performed." The additional testing is covered in section 8.3.2.2.5. Removed incorrect reference. Added reference to Table 3.12.2 Note 26. (CN-2265) [8.3.2.1.3] [8.3.2.1.3] [8.3.2.2.3] [8.3.2.2.5]
17. Added clarifying phrase to 480 V MCC Protective Device for the Reactor Cavity Filtration System on Table 8.3-14 to indicate that it only applies to Unit 1. (CN-2271)
18. Corrected typographical error. (CN-2342) [8.3.2.2.3] .

- Page 9 of 18 -

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Upd ted Fin 1 Sdtty Analysis Report, Revision 6 I

u O ca 9'er9 ^=xiiirvsvstems-  !

1. Added description of effect that Control Rod Drive Mechanism binding, which occurred during 1RE07. 'ias on the rapid refueling sequence. (CN-2202) [9.1.4.2.2.1]

i 2.' Corrected description of cask handling area in the Fuel Handling Building to indicate that the i stainless steel liner and permanent removable gates have not been installed. (CN-2151)

.[9.1.4.2.3]

3. Revised the description of refueling machine to reflect removal of the failed fuel detector.

(CN-2106,2158) [9.1.4.2.4.1]  ;

4. Revised the description of the fuel assembly transfer car to reflect removal of the hold down

{

1atch mechanism. (CN-2206) [9.1.4.3.1.4]

5. Deleted the number of Closed loop Auxiliary Cooling Water system pumps that are normally in operation to allow flexibility for low-load oper ation. (CN-2148) [9.2.1.1.2]
6. Removed reference to Essential Cooling Water Intake Structure Gantry Crane as a result of I hardware modification. - (CN-1960) [9.2.1.2.2, 9.2.1.2.3]
7. Removed reference to Chiller Supply Header check valves for Unit I due to a hardware modification that removed the valve internals. (CN-2147) [ Table 9.2.1-2] '

, ,O -

8. Revised the operator actions following a loss of offsite power such that isolation of the non-safety Component Cooling Water header and excess letdown heat exchanger branches is not required before restoring Component Cooling Water flow to the Reactor Containment Fan Coolers. (CN-2144)[9.2.2.2.1) i
9. Clarified that a plant shutdown is not required by Technical Specifications until the Main Cooling Reservoir level is less than 25.5 feet. (CN-2174) [9.2.5.1.1.5]

l 10. Changed the Essential Cooling Pond dividing dike freeboard during the maximum flood of the Colorado River from 6.0 feet to 3.9 feet for consistency with section 2.4.4.2.3. (CN-2175)[9.2.5.3]

11. Corrected Essential Chilled Water System Expansion " Tank" to " Tanks". (CN-2088)  ;

[9.2.6.1] '

l

12. Changed the description of the Reactor Makeup Water Storage Tank to reflect replacement of the Unit I diaphragm with a different material. (CN-2177) [9.2.7.2.1]
13. Addet reference to the FHB HVAC chiller condensate drain flow path to reflect a hardware modification. (CN-2048) [9.3.3.2.6, Table 9.3-14]

i-

14. Clarify that the train-related HVAC fire dampers are associated with the F V AC equipment room. (CN-2218)[9.4.1.1]

, O.

5

- Page 10 of 18 -

Upd:ted Final Safety Analysis R: port, Revisi:n 6

15. Changed the description of operation of the Control Room Envelope HVAC system from h7 " trains required to function" to " trains required to be operable" for consistency with Technical Specification requirements. Deleted the number of trains required to function in the description of the EAB Main Area HVAC system for consistency with Technical Specification requirements. Corrected typographical error in TSC HVAC system component description. (CN-2220) [9.4.1.2.1]
16. Clarified method that the Fuel Handling Building Supply Air Subsystem supply air damper utilizes to maintain negative building pressure. (CN-2088) [9.4.2.2.1]
17. Clarified that the Fuel Handling Building main exhaust fan motors are fan-cooled. (CN-2088)[9.4.2.2.3]
18. Corrected the description of the Fuel Handling Building Ventilation system to reflect that fire dampers are not installed in the exhaust ductwork. (CN-2236) [9.4.2.2.4]
19. Clarified that HVAC system maintenance is performed in accordance with the preventative maintenance program, i.e., past experience and manufacturer recommendations as described '

in UFSAR section 13.1.1.1.2.4. (CN-2088) [9.4.3.4]

20. Changed the description of the Reactor Containment Fan Cooler Subsystem to reflect the number of units that are required to be " operable" rather than " operating" for consistency with Technical Specifications.

p (CN-2088) [9.4.5.2.1]

V

21. Removed the statement that airfiow is directed around the periphery of the reactor refueling pool because HVAC ductwork has been removed to facilitate Reactor Coolant Pump motor replacement. (CN-2153, -2154) [9.4.5.2.6]
22. Revised fire protection design bases to indicate that a single train or pathway of plant equipment will be available to achieve post fire safe shutdown. (CN-2097) [9.5]
23. Corrected "FHAR" to "UFSAR" for figure numbers. (CN-2212) [9.5.1.1]
24. Clarified that the Emergency DC Lighting system sealed beam battery pack units are seismically supported, but are not seism'ically qualified. (CN-2196) [9.5.3.2.3]
25. Updated inspection and testing requirements for the Emergency DC Lighting System to reflect commitments made in prior correspondence. (CN-2188) [9.5.3.4]
26. Changed the moisture trap and drain valve configuration of the Standby Diesel Generator starting air receivers to reflect hardware modification. (CN-2171, CN-2172) [ Figure 9.5.6-1]
27. Corrected a typographical error on a data reference number, added a calculation number because the preliminary study has been finalized, removed "geotechnical" because the walkdowns were not performed by the Geotechnical group, and corrected a typographical error on a Technical Specification section number. (CN-2198) [ Appendix 9A]

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Upd ted Fin:1 Saf:ty An: lysis Report, R: vision 6

28. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

(g

[9.5.1.4, 9.5.1.6, 9.5.1.6.2, Appendix 9A]

29. Clarified the tonnage rating of the polar crane. (CN-2240) [9.1.4.3.1.6]
30. Corrected inconsistencies between UFSAR and actual plant conGguration/ operation involving the Main Cooling Reservoir and the Essential Cooling Pond. (CN-2280) j

[9.2.5.2,9.2.5.3.2]

31. Removed references to Toxic Gas Analyzers since the Toxic Gas Monitors have been removed. (CN-2299) [9.4.1.2.1.1.a,9.4.1.2.1.3.a 9.4.1.2.1.3.e,9.4.1.3]
32. Removed Essential Cooling Water Check Valves EWO262 EWO263 and EWO264 from Table 9.2.1-2. (CN-2166) [ Table 9.2.1-2]
33. Changed " operability" to "operabilty/ functional capability", and added clarification for NUREG-0452 Specification 3/4.3.3.8, Fire Detection Instrumentation on Page 9.5-29. (CN- l 2277)[9.5.1.2.11, 9.5.1.2.16,9.5.1.2.19.10, 9.5.1.6.1] '
34. Deleted redundant information, added missing component tag numbers, and corrected typographical errors / incorrect information on Table 9.2.2-3. (CN-2298) [ Table 9.2.2-3J
35. Corrected erroneous information concerning the non-safety related space heaters in the ECWIS Ventilation System. (CN-2214)[ Table 9.4-2.7]

A U 36. Clarified text description for water treatment of the Auxiliary Cooling Water System. Deleted Table 9.2.2-2 (CN-2293) [9.2.1.1.2, 9.2.2.2.1, 9.3.4.1.2.4, 9.5.5.3]

37. Removed an exception to the requirements of NFPA 72D. (CN-2032) [9.5.1.2.19]
38. Clarified / updated descriptions of plant communication systems. (CN-2268) [9.5.2.2, 9.5.2.2.1, 9.5.2.2.3, Table 9.5.2-1]
39. Changed Figure 9.5.6-1 to reflect site specific, as-built information. (CN-2230) [ Figure 9.5.6-1]
40. Clarified description of use of the undenvater camera systems with the Refueling Machine.

(CN-2132) [9.1.4.2.4.1]

l

41. Added description of secondary air source connection. (CN-2192) [9.3.1.2.2 and 9.3.1.2.3]
42. Corrected figure number 9.4.4.3 to 9.4.4-3. Changed the number of window air conditioners from three to two. (CN-2232) [9.4.4.2,9.4.4.2.2 paragraph 7 and 9 and Table 9.4-2.4]
43. Revised text and Table 9.1-2 to indicate that Reactor Cavity Filtration System applies only to Unit I and operation cf the system only pertains to Unit 1. (CN-2271) [9.1.3.1.3,9.1.3.2, 9.1.3.2.1 and Table 9.1-2]

)

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- Page 12 of 18 -

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4

' Upd:ted Final Safety Analysis Report, R visi:n 6

44. Corrected dewpoint and particulate requirements for the Compressed Air System and added

)O; description of supplementary air lines that have been installed. (CN-2186) [9.3.1.1,9.3.1.2.1,

, 9.3.1.2.2 and 9.3.1.2.3]

45.' Added clarifying phrase to indicate that a diesel engine-driven fire pump is automatically tripped during a test run if a low fuel oil level condition in its day tank occurs. (CN-2187)

[9.5.1.2.19.2]

Chapter 10. " Steam and Power Conversion System"

1. Deleted turbine trip on low electrohydraulic control fluid pressure as a result of a hardware modification. (CN-2117,2159)[10.2.2.9]
2. Changed section referenced from 10.4.1.3 to 10.4.1.3.4. (CN-2088) [10.2.5]
3. Clarified that the strap-on radiation monitors on the steam generator blowdown lines are capable of detecting large primary-to-secondary leakage, i.e., a steam generator tube rupture, .

rather than small amounts of primary-to-leakage. (CN-2180) [10.4.1.3.4,10.4.8.2]

4. Changed the outlet temperature of the steam generator blowdown regenerative heat exchanger to reflect a hardware modification that optimizes thermal efficiency when the mixed-bed demineralizers are bypassed. (CN-2139) [ 10.4.8.2,10.4.8.4]

h 5. Replaced out-dated Circulating Water system figure with reference to updated controlled drawing reference number *. (CN-2130) [ Figure 10.4.5-1]

6. . Corrected the number of battery chargers that power the four independent channels of the

. Class 1E 125 volt DC system for consistency with license amendment 73/62. (CN-2103)

[10A.2.3]

7. Revise description of operation for the EH System with respect to using variable displacement constant pressure pumps and dropping references to unloading type of operation. (CN-2264)[10.2.2.7.3]
8. Revised descriptive destination of exhausted resin transferred from the mixed-bed l'

demineralizers in the Stearn Generator Blowdown System. (CN-2296) [10.4.8.2]

l 9. Added AFW pump surveillance requirements for minimum discharge pressure and flow rate.

l (CN-2323) [10.4.9.4]

Chapter 11. " Radioactive Waste Management"

1. Revised description ofliquid waste processing systems options and philosophy. Each process is an option which already exists by system design. (CN-2119) [l1.2.1,11.2.2, 11.2.3, Table 11.2-3, Table 11.2-5, Table 11.2-5A, and 11.4.1.2, Table 11.4-4]
g -

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Upd .ted Finil S:f ty An: lysis R: port, Revision 6

2. Deleted general description of Mobile Filtration /Demineralizer Unit from section 11.2.2.1 (j and incorporated more specific information in other appropriate sections. (CN-2160)

[11.2.2.1,11.2.2.1.1,11.2.2.2.1,11.2.3.1, Table 11.2-3]

3. Deleted reference to the high pressure alarm for the Waste Monitoring Tanks in Unit 2 as a result of a hardware modification. (CN-2091)[11.2.2.2.2]

l

4. Clarified the description for radioactive waste storage to reflect current practices. (CN-2219)

[11.4.2.3,11.4.2.3.1,11.4.2.3.2, and 11.4.2.3.3]

5. Clarified that the strap-on radiation monitors on the steam generator blowdown lines are capable of detecting large primary-to-secondary leakage, i.e., a steam generator tube rupture, '

rather than small amounts of primary-to-leakage. (CN'-2180) [11.5.2.5.4]

i

6. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[l 1.4.2.4]

l

7. Corrected typographical / editorial errors in Section 11.5. (CN-2283) [11.5.2.1,11.5.2.6, 11.5.3]
8. Revised Section 11.3.1 to reflect current operational practices for use of the Reactor Coolant Vacuum Degassing System during refuelings, and revised various instrument ranges to reflect as-built conditions. (CN-2099) [11.3.1, Table 11.3-6]

O Chapter 12. " Radiation Protection"

1. Changed " staging" to " scaffolding" for clarification. (CN-2088) [12.1.2.1]
2. Clarified the description for radiation protection design features to reflect current operating practice and philosophy, revised 10CFR20 terminology, and as-built plant configuration.

(CN-2185) [12.3.1.3,12.3.1.6,12.3.2.1,12.3.2.2.1,12.3.2.2.2,12.3.2.2.2.4,12.3.2.2.2.5.1, Table 12.3.2-1, Table 12.3.4-1,12.5.3.4]

3. Clarified that criticality in the spent fuel pool is prevented by administrative controls, in addition to design, for consistency with section 4.3.2.6. (CN-2122) [12.3.4.1.2]
4. Corrected section reference from 11.5.2.1.4 to 11.5.2.1.5. (CN-2122) [12.3 4.2]
5. Corrected the Containment High Range Radiation Monitor range from milliroentgen per hour to roentgen per hour. (CN-2122) [ Table 12.3.4-1]
6. Clarified that the minimum detectable concentrations are calculated values; clarified that there are two minimum detectable concentrations for Cesium-137 which are dependent on the paper speed; and corrected the minimum detectable concentration for Iodine-131. (CN-2161)

[ Table 12.3.4-2]

g 7. Clarified requirements for respirator fit testing. (CN-2115) [12.5.3.5]

V

- Page 14 of 18 -

Updited Fin:] S:rety Antlysis R: port, Revision 6

8. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

O v [12.1.1.1,12.1.1.2,12.1.1.3]

9. Changed channel functional test frequency for non-safety related area radiation monitors to

" periodically", instead of every 18 months or refueling outage for inaccessible monitors.

(CN-2284) [12.3.4.1.4]

Chapter 13. " Conduct of Operations"

1. Updated commitment to Regulatory Guide 8.29 from Revision 0 to Revision 1. (CN-2164)

[l3.2.3.11]

2. Changed the description of the Independent Safety Engineering Group to indicate that the engineers are not within the same organizational " group." (CN-2239) [13.4.2.2]
3. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[13.0,13.1, 13.1.1.1.1.1,13.1.1.1.1.4, 13.1.1.1.2.4,13. 1.1.1.3,13.1.1.2.1,13.1.1.2.2, 13.1.1.3,13.1.1.1,13.1.2.4,13.1.2.6,13.1.2.7, Figures 13.1-1 through 13.1-6, added figures 13.1-7 through 13.1-9, 13.2,13.2.2.6.1,13.4.2.1,13.4.2.2,13.4.3,13.5.2.1,13.5.2.2]

4. Revised 13.5.2.2 to reflect the applicablity of 10CFR50.59 to procedures for graded Quality Assurance and Comprehensive Risk Management. (CN-2253) [13.5.2.2,13.5.2.2.13]

(' Chapter 14. " Initial Test Procram"

1. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[14.2, 14.2.2, 14.2.2.1, 14.2.2.2, 14.2.2.3, 14.2.2.4,14.2.2.5, 14.2.2.6, 14.2.3, 14.2.8, 14.2.12.1]

2. Revised description of RHR suction isolation valve operation to reflect removal of auto-closure interlock. (CN-2301) [14.2.12.2, Test No. 78]

Chapter 15. " Accident Analyses"

1. Revised the boron dilution event to indicate that makeup to the Reactor Coolant system i during refueling operations can also be supplied from the boric acid tank by the centrifugal charging pumps. (CN-2129) [15.4.6.2]
2. Corrected the low population zone distance from "48,000 meters" to "4,800 meters" for consistency with Table 15.4-5 and other UFSAR sections. (CN-2088) [15.4.8.3.3]
3. Added reference letter for ATWS system basis. (CN-2089) [15.8]

(]

\

4. Updated the peak cladding temperature analysis penalties and benefits for the Small Break Loss of Coolant Accident. (CN-2111)[ Table 15.6-9]

- Page 15 of 18 -

l

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u Updated Final Safety Analysis R: port, Revision 6

'5. Divided the fuel handling accident into two separate discus., ions for the Fuel Handling

~

Building and Reactor Containment Building, added an analysis for the Reactor Containment Building fuel handling accident that assumes that both personnel airlock doors are open at the time of the accident, and added assumptions and results for extended burnup fuel. (CN-2149)

[15.7.4.2,15.7.4.3, Tables 15.7-7,'15.7-9,15.7-10,15.7-11,15.7-12, and 15.7-13, Appendix 15.A]

6; Corrected the assumed radionuclide transit time to the Colorado River due to a radioactive ground release. (CN-2280) [15.7.3.2)

7. Incorporated revisions to the boron dilution analysis accounting for 10% steam generator tube plugging. (CN-2245) [15.4.6.2,15.4.6.3 and Table 15.4-1]
8. Revised SBLOCA analysis description to reflect AOR Reconstitution and the automatic actuation of the steam generator PORVs. (CN-2287) [ Table 15.0-3, Table 15.0-6,15.6.5.2, 15.6.5.4.1,15.6.5.4.2.15.6.5.4.3, Section 15.6 References, Table 15.6-5, Table 15.6-8 and Table 15.6-9]

Chaoter 16. " Technical Soecifications"

1. Revised lead Factors and Recommended Withdrawl Times (based on latest surveillance test results), as well as referenced WCAPs, in Table 16.1-2. (CN-2292) [ Table 16.1-2]
2. Added clarifying note to Item 12 of Table 16.1-4 indicating that the specified response times include diesel generator starting delay, but not sequence loading delay. (CN-2258)

Chanter 17. "Ouality Assurance" No changes Response to NRC Ouestions

1. Deleted exception to NRC Regulatory Guide 1.121. (CN-2181) [ Chapter 3 - Question 110.24]
2. Updated the reactor vessel material properties and parameters related to pressurized thermal shock to reflect the analysis results of the most recent surveillance capsule. (CN-2178) .

[ Chapter.5 - Question 121.8] '

3. Corrected the description of the Auxiliary Feedwater Storage Tank volume to reference 485,000 gallons as the Technical Specification minimum volume. (CN-2209) [ Chapter 5 -

Quations 440.30N]

[ 4. Revised response to Question 430.37N to describe battery charger qualification with and '

without the battery connected. (CN-2104) [ Chapter 8 - Question 430.37N]

- Page 16 of 18 -

q y , r -- -

Updated Final S:f ty Analysis Report, Revisi:n 6

,, 5. Updated and relocated the normal inspection and testing requirements for the Emergency DC Q Lighting System to Section 9.5.3.4. I_cft reference to section 14.2.12.2 for historical startup testing. (CN-2188) [ Chapter 9 - Question 430.83N]

6. Revised the response to Question 331.6, which pertains to As Low As Reasonably Achievable (ALARA) design considerations, to reference the Final Safety Analysis Report for design and l construction phase information and section 12.1 for operation phase information. (CN-2176)

[ Chapter 12 - Question 331.6]

7. Revised the design basis accident discussion to include a scenario where the Personnel Airlock is open during a fuel handling accident in Containment. (CN-2149) [ Chapter 15 - i Question 211.42] I
8. Editorial changes to reflect the transfer of operating responsibility to STPNOC. (CN-2249)

[ Chapter 5 - Question 250.3N]

9. Incorporated best estimate weld wire chemistry, and added reference to CE Report NPSD-1039, Rev. 2, to Table Q121.8-2b. (CN-2292) [ Chapter 5 - Question 121.8] i
10. Changed response to Question 232.9 to utilize peaking factor presented in COLR, and corrected description of CAOC offset band due to Technical Specification Amendment No.

9/1 in response to Question 491.1N. (CN-2309) [ Chapter 4 - Questions 232.9 and 491.N]

I1. Rewrote response to Question 450.4N to reflect removal of toxic gas monitors and control  :

(. ) room envelope auto-isolation feature. (CN-2309) [ Chapter 6 - Question 450.4N]

12. Changed numerical pcm value in response to Question 232.7 to agree with the current Technical Specifications. (CN-2309) [ Chapter 15 - Question 232.7]
13. Rewrote response to Question 430.92N for enhancement purposes. (CN-2224) [ Chapter 9 -

Question 430.92N]

14. Deleted final sentence from question response concerning pre-license commitment to provide written manufacturer confirmation regarding the acceptability of the location and mounting of the DG panels from a vibration standpoint. (CN-2303) [ Chapter 8 - Question 430.25N]
15. Revised responses to Questions 430.9N,430.10N,430.20N,430.38N,430.117N and 430.119N to correct editorial errors and bring the responses up to date. (CN-2304) [ Chapter 8

- Questions 430.9N,430.10N,430.20N,430.38N,430.117N and 430.119N]

! 16. Clarified Response (b) to Question 430.19N, concerning splicing of cables, and corrected UFSAR section number referenced in the question statement. (CN-2270) [ Chapter 8 -

Question 430.19N]

j 17. Revised description of RHR suction isolation valve operation to reflect removal of auto-closure interlock. (CN-2301) [ Chapter 5, - Question 440.29N]

g 18. Responses to several Chapter 4 and Chapter 15 NRC Questions have been classified as ,

V ' Historical Information'. (CN-2341) [ Chapter 4 - Questions 221.6,221.7,221.9,492.1N, 1

l - Page 17 of 18 -

l

l l Upd ted Final S:fety Antlysis Riport, Rsvision 6 j l

492.3N,492.5N,492.6N,492.7N and 492.8N; Chapter 15 - Questions 211.44,211.46, h : 21 1.48, 21 1.51, 21 1.53, 21 1.56, 21 1.57, 21 1.85, 21 1.86, 440.2N, 440.3N, 440.5N, 440.6N, 440.7N,440.50N. 440.51N,440.69N,440.72N and 440.80N]

19. Revised response to Question 282.1N to update manager title and UPRI document number, and to indicate chemistry sampling frequency and action level requirements will be developed in accordance with industry experience, not vendor recommendations. (CN-2311)
20. Indicated response to NRC Question 260.9N as ' Historical Information'. (CN-2267)- l l 21. Deleted NRC Questions 372.10 and 372.11 since they no longer apply to current

' Meteorological System equipment. (CN-2276)

! l l

i l

)

l l

l l

A

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- Page 18 of 18 -

O Attachment 3 Updated Final Safety Analysis Report, Revision 6 0

A O

O Instruction Sheet for STP Updated Final Safety Analysis Report O

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Instruction Sheet for STP Uodated Final Safety Analysis Report - Revision 6 Remove Panes /Firures

~ Insert Pancs

~

TABLE OF CONTENTS TC 1-1 through TC 1-6 TC 1-1 through TC 1 TC 4-1 through TC 4 TC 4-1 through TC 4-2 TC 4-7 through TC 4 TC 4-7 through TC 4-8 TC 5-3 through TC 5-6 TC 5-3 through TC 5-6 TC 6-5, TC 6-6 TC 6-5, TC 6-6 TC 7-9, TC 7-10 .TC 7-9, TC 7-10 TC 8-1, TC 8-2 TC 8-1, TC 8-2 TC 8-5, TC 8-6 TC 8-5, TC 8-6 TC 9-1 TC 9-2 TC 9-1, TC 9-2

- TC 9-11, TC 9-12 TC 9-11, TC 9-12

TC 10-7, TC 10-8 TC 10-7, TC 10-8

. TC 11-1 through TC 11-8 TC 11-1 through TC 11-8 TC 13-1, TC 13 TC 13-1, TC 13-2 TC 13-5 TC 13-5.

TC 15-5 through TC 15-12 TC 15-7 through TC 15-12 TC 15-21, TC 15-22 TC 15-21, TC 15-22 Chapter 1 ,

.TC 1-1 through TC 1-6 TC 1-1 through TC 1-6 1.1-1 through 1.1-37.. '1.1_-1 through 1.1-37 1.2-9,1.2-10 1.2-9,1.2 1.2-13,1.2-20 1.2-13,1.2-14 Figure 1.2-27 (sheet 3 of 4) Figure 1.2-27 (sheet 3 of 4)

.1.4-1 through 1.4-4 1.4-1 through 1.4-4 1.6-4 1.6-4 1.7-2 through 1.7-60 1.7-2 through 1.7-68 Chapter 2 2.1-1, 2.1-2 -- 2.1-1, 2.1-2 2.2-1 through 2.2-14 2.2-1 through 2.2-14 2.2-16 2.2-16 Figure 2.2-1 Figure 2.2-1 -

Page 1 of 13

. -.- - -_ . - . _ _ - - - - . ~ - . - - - -. . .. . . . . . - - - - . - - .- -

Instruction Sheet for STP Updated Final Safety Analysis R;oort - Revision 6 L Remove Pages/Finures Insert Panes 2.3-19,2.3-20 2.3-19,2.2-20 2.4-3, 2.4-4 2.4-3, 2.4-4 2.4-45 through 2.4-48 2.4-45 through 2.4-48 2.4-55,2.4-56 2.4-55,2.4-56 2.4-71,2.4 2.4-71,2.4-72 2.5.1-141 ,2.5.1-142 2.5.1-141 ,2.5.1-142 2.5.4-61,2.5.4.-62 2.5.4-61, 2.5.4.-62 2.5.6-1 through 2.5.6-4 2.5.6-1 through 2.5.6-4 Chaptei 3 3.1-1, 3.1-2 3.1-1, 3.1-2 3.1-17,3.1-18 3.1-17,3.1-18 3.1-23,3.1-24 3.1-23,3.1-24 L 3.1-31,3.1-32 3.1-31,3.1-32 L 3.2-3 through 3.2-6 3.2-3 through 3.2-6 l- 3.2-8 3.2-8 l 3.2-16,3.2-17 3.2-16,3.2-17 l' 3.2-23 3.2-23 l 3.2-30 3-2-30 3.2-37, 3.2-38 3.2-37, 3.2-38

l. 3.2-43 3.2-43 3.2-52 3.2-52 3.2-61 through 3.2 3.2-61 through 3.2-64 3.4-1 through 3.4-4 3.4-1 through 3.4-4 3.4-7, 3.4-8 3.4-7, 3.4-8 3.4-12 3.4-12 Figure 3.4-2 Figure 3.4-2 Figure 3.6.1-1 Sheet 8A Figure 3.6.1-1 Figure 3.6.1-1 Sheet 8B Figure 3.6.1-1 Sheet 8B Figure 3.6.1-1 Sheet 8C Figure 3.6.1-1 Sheet 8C 3.6. A-11, 3.6.A-12 3.6. A-11, 3.6.A-12 3.7-27 through 3.7-30 3.7-27 through 3.7-30 L 3.7-33,3.7-34 3.7-33,3.7-34

[ - 3.8-5,3.8-6 3.8-5,3.8 l 3.8-9,3.8-10 3.8-9,3.8-10

!~

3.8-49 through 3.8-52 3.8-49 through 3.8-52 3.8-57,3.8-58 3.8-57,3.8-58

3.8-63,3.8-64 3.8-63,3.8-64 3.8-69,3.8-70 3.8-69,3.8-70 3.8-79,3.8-80 3.8-79,3.8-80 s(

i I

. Page 2 of 13

Instruction Sheet for l STP Updated Final Safety Analysis Report - Revision 6 1 w

I Remove Panes /Fieures Insert Panes j i

3.8-83,3.8-84 3.8-83,3.8-84 j 3.8-102 3.8-102 1 3.8-110 3.8-110 l 3.8-111 3.8-111 Figure 3.8.4-1 Figure 3.8;4-1 3.9-5, 3.9-6 3.9-5 , 3.9-6 3.9-15 through 3.9-20 3.9-15 through 3.9-20 3.9-23,3.9-24 '3.9-23,3.9-24 3.9-47 through 3.9-54 3.9-47 through 3.9-54 3.9-63,3.9-64 3.9-63,3.9-64 3.9-85 through 3.9-87 3.9-85 through 3.9-87

! 3.9-97 3.9-97 3.9-128 3.9-128 3.11-24 3.11-24 3.12-1 through 3.12-3 3.121 through 3.12-3 L 3.12-5 3.12-5 3.12-7 through 3.12-10 3.12-7 through 3.8-10 3.12-12,3.12-13 3.12-12,3.12-13 3.12 15 3.12-15

.p 3.12 3.12-20 d 3.12-22 3.12-22 3.12-24 3.12-24 3.12-26 through 3.12-28 3.12-26 through 3.12-28 4 3.12-31through 3.12-36 3.12-31through 3.12-36 Chapter 4 TC 4-1, TC 4-2 TC 4-1, TC 4-2 TC 4-7, TC 4-8 TC 4-7, TC 4-8 4.1-1 through 4.1-11 4.1-1 through 4.1-11 4.2-1 through 4.2-46 4.2-1 through 4.2-46 Figure 4.2-1 Figure 4.2-1 Figure 4.2-2b Figure 4.2-2b Figure 4.2-3 Figure 4.2-3 Figure 4.2-5a Figure 4.2-5a Figure 4.2-5b Figure 4.2-5b Figure 4.2-3 Figure 4.2-3 Figure 4.2-14 Figure 4.2-14 4.3-5, 4.3-6 4.3-5, 4.3-6 4.3-51,4.3-52 4.3-51,4.3-52 O

Page 3 of 13 l

Instmetion Sheet for STP Updated Final Safety Analysis Report - Revision 6 f-- Remove Panes /Finures Insert Pages Chapter 5 TC 5-3 through 5-6 TC 5-3 through 5-6 5.1-5 5.1-5 5.1-6 5.1-6 5.1-7 5.1-7 5.2-5, 5.2-6 5.2-5, 5.2-6 5.2-11,5.2-12 5.2-11,5.2-12 5.2-13, 5.2-14 5.2-13,5.2-14 5.2-15,5.2-16 5.2-15,5.2-16 5.2-21,5.2-22 5.2-21,5.2-22 5.2-25, 5.2-26 5.2-25,5.2-26 5.2-32 -

5.2-32 5.3-1 through 5.3-4 5.3-1 through 5.3-4 5.3-11,5.3-12 5.3-11,5.3-12 5.3-18 5.3-18 q 5.3-22 5.3-22 V 5.3-23 5.3-23 5.3-37 5.3-37 5.3-38 5.3-38 5.4-5, 5.4-6 5.4-5, 5.4-6 5.4-9 through 5.4-45 5.4-9 through 5.4-45 5.4-53 5.4-53 Notes to Figure 5.4-7 Notes to Figure 5.4-7 5.4.A-8 5.4.A-8 5.4.A-14 5.4.A-14 5.4.A-17 5.4.A-17 Chanter 6 TC 6-5, TC 6-6 TC 6-5, TC 6-6 6.1-3, 6.1-4 6.1-3, 6.1-4 6.1-10 6.1 10 '

6.2-23, 6.2-24 6.2-23,6.2-24 6.2-41 to 6.2 44 6.2-41 to 6.2-44 6.2-147 6.2-147 Figure 6.2.4-1 Sheet 2 of 100 Figure 6.2.4-1 Sheet 2 of 100 Figure 6.2.4-1 Sheet 3 of 100 Figure 6.2.4-1 Sheet 3 of 100

/ Figure 6.2.4-1 Sheet 4 of 100 Figure 6.2.4-1 Sheet 4 of 100 Page 4 of 13 i

Instruction Sheet for STP Updated Final Safety Analysis Report - Revision 6 Remove Panes /Figums Insert Pages Figure 6.2.4-1 Sheet 5 of 100 Figure 6.2.4-1 Sheet 5 of 100 Figure 6.2.4-1 Sheet 6 of 100 Figure 6.2.4-1 Sheet 6 of 100 Figure 6.2.4-1 Sheet 11 of 100 Figure 6.2.4-1 Sheet 11 of 100 Figure 6.2.4-1 Sheet 19 of 100 Figure 6.2.4-1 Sheet 19 of 100 Figure 6.2.4-1 Sheet 30 of 100 Figure 6.2.4-1 Sheet 30 of 100 Figure 6,2.4-1 Sheet 41 of 100 Figure 6.2.4-1 Sheet 41 of 100 Figum 6.2.4-1 Sheet 50 of 100 - Figure 6.2.4-1 Sheet 50 of 100 Figure 6.2.4-1 Sheet 51 of 100 Figure 6.2.4-1 Sheet 51 of 100 Figure 6.2.4-1 Sheet 52 of 100 Figure 6.2.4-1 Sheet 52 of 100 Figure 6.2.4-1 Sheet 63 of 100 Figure 6.2.4-1 Sheet 63 of 100 Figure 6.2.4-1 Sheet 67 of 100 Figure 6.2.4-1 Sheet 67 of 100 Figure 6.2.4-1 Sheet 69 of 100 Figure 6.2.4-1 Sheet 69 of 100 Figure 6.2.4-1 Sheet 72 of 100 q;ure 6.2.4-1 Sheet 72 of 100 Figure 6.2.4-1 Sheet 75 of 100 e igure 6.2.4-1 Sheet 75 of 100 Figure 6.2.4-1 Sheet 80 of 100 Figure 6.2.4-1 Sheet 80 of 100 Figure 6.2.4-1 Sheet 81 of 100 Figum 6.2.4-1 Sheet 81 of 100 Figure 6.2.4-1 Sheet 86 of 100 Figure 6.2.4-1 Sheet 86 of 100 Figure 6.2.4-1 Sheet 88A of 100 Figure 6.2.4-1 Sheet 88A of 100 Figure 6.2.4-1 Sheet 89 of 100 Figure 6.2.4-1 Sheet 89 of 100 Figure 6.2.4-1 Sheet 90 of 100 O Figure 6.2.4-1 Sheet 92 of 100 Figure 6.2.4-1 Sheet 90 of 100 Figure 6.2.4-1 Sheet 92 of 100 Figum 6.2.4-1 Sheet 94 of 100 Figure 6.2.4-1 Sheet 94 of 100 Figure 6.2.4-1 Sheet 95A of 100 Figure 6.2.4-1 Sheet 95A of 100 Figure 6.2.4-1 Sheet 95B of 100 Figure 6.2.4-1 Sheet 95B of 100 Figure 6.2.4-1 Sheet 95C of 100 Figure 6.2.4-1 Sheet 95C of 100 Figure 6.2.4-1 Sheet 95D of 100 Figure 6.2.4-1 Sheet 95D of 100 Figure 6.2.4-1 Sheet 97 cf 100 Figure 6.2.4-1 Sheet 97 of 100 Figure 6.2.4-1 Sheet 99 of 100 Figure 6.2.4-1 Sheet 99 of 100 Figure 6.2.4-1 Sheet 100 of 100 Figure 6.2.4-1 Sheet 100 of 100 6.3-1 through 6.3-6 6.3-1 through 6.3-6 6.3-15 through 6.3-32 6.3-15 through 6.3-32 6.3-42 6.3-42 6.3-48 6.3-48 Figure 6.3-8 Figure 6.3-8 6.4-1 through 6.4-4 6.4-1 through 6.4-4 Figure 6.4-1 Figure 6.4-1 6.5-3 through 6.5-8 6.5-3 through 6.5-8 6.5-14, 6.5-15 6.5-14, 6.5-15 LO-

l. Page 5 of 13

Instruction Sheet for STP Updated Final Safety Analysis Report - Revision 6 q Remove Panes /Finures ' Insert Panes b

Chanter 7 TC 7-9, TC 7-10 TC 7-9, TC 7-10 7.1-19,7.1-20 7.1-19,7.1-20 7.2-5, 7.2-6 7.2-5, 7.2-6

~ 7.2-13 through 7.2-16 7.2-13 through 7.2-16 7.2-19,7.2-20 7.2-19,7.2-20 7.2-25,7.2-26 7.2-25,7.2-26 Figure 7.2-17 Figure 7.2-17 Figure 7.2-17A Figure 7.2-17A Figure 7.2-17B l Figure 7.2-17B Figure 7.2-18 Figure 7.2-18 7.3-11,7.3-12 7.3-11,7.3-12 7.3-15 through 7.3-26 7.3-15 through 7.3-26 7.3-39 7.3-39 7.3-46,7.3-47 7.3-46,7.3-47 7.3-51 7.3-51 Figure 7.3-23 Figure 7.3-23 L(q):

7.4-15,7.4-16 7.4-15,7.4-16 l 7.4-38,7.4-39 7.4-38,7.4-39 l 7.4-41,7.4-42 7.4-41,7.4-42 i-7.4 7.4-44 l 7.4-46 through 7.4-48 7.4-46 through 7.4-48 l 7.4-51 7.4-51 7.4-54,7.4-55 '7.4-54,7.4-55 7.5-23 7.5-23 7.6-3, 7.6-4 7.6-3, 7.6-4 L

~

7.6-11,7.6-12 .7.6-11,7.6-12 7.6-14 7.6-14 7.7-15,7.7-16 7.7-15,7.7-16 Figure 7.7-4 . Figure 7.7-4 1

7.8-5, 7.8-6 7.8-5, 7.8-6 L 7.8-9 7.8-9

, 7A.I. A.1.2-1 7 A.I. A.1.2-1

_ 7A.I.A.1.3-1, 7A.I. A.1.3-2 7A.I. A. I .3- 1, 7A.I.A.1.3-2 7A.I.C.1-3 7A.I.C.1-3 7A.I.C.2 7A.I.C.2-1
. 7A.I.C.3 7A.I.C.3-1 7A.I.C.4-1 7A.I.C.4-1 7A.I.C.5-1, 7A.I.C.5-2 7A.I.C.5-1, 7A.I.C.5-2 Page 6 of 13 4

l Instruction Sheet for STP Uodated Final Safety Analysis Report - Revision 6 Remove Pares / Figures Insen Pages Os 7A.I.C.6-1, 7A.I.C.6-2 7A.I.C.6-1, 7A.I.C.6-2 7A.I.C.7-1 7A.I.C.7-1 l 7A.I.C.8-1 7A.I.C.8-1 7A.I.G.1-1 7A.I.G.1-1 7A.II.B.2-3,7A.II.B.2-4 7A.II.B.2-3, 7A.II.B.2-4 7A.II.B.3-11,7A.II.BS-12 7A.II.B.3-11,7A.II.B.3-12 7A.II.E.1.1-7, 7A.II.E.1.1-8 7A.II.E.1.1-7, 7A.11.E.1.1-8 j 7A.II.E.3.1-1 through 7A.II.E.3.1-3 7A.II.E.3.1-1 through 7A.II.E.3.1-3 7A.II.E.4.2-5 7A.II.E.4.2-5 7A.II.K.3.3-1 7A.II.K.3.3-1 7A.III.D.3.4-3,7A.III.D.3.4-4 7A.III.D.3.4-3, 7A.III.D.3.4-4 7A.S.5-7 7A.S.5-7 7A.S.8-13, 7A.S.8-14 7A.S.8-13,7A.S.8-14 Chapter 8 l l

TC 8-1, TC 8-2 TC 8-1, TC 8-2 n TC 8-5, TC 8-6 TC 8-5, TC 8-6 l

V 8.1-1 through 8.1-5 8.1-1 through 8.1-5

~

8.2-1 through 8.2-14 8.2-1 through 8.2-14 8.2-17 8.2-17 8.2-18 8.2-18 Figure 8.2-1 Figure 8.2-1 Figure 8.2-2 Not Used Page Figure 8.2-2A Not Used Page Figure 8.2-3 Figure 8.2-3 Figure 8.2-3A Sheet 1 of 2 Figure 8.2-3A Sheet lof 2 Figure 8.2-3A Sheet 2 of 2 Figure 8.2-3A Sheet 2 of 2 8.3-3, 8.3-4 8.3-3, 8.3-4

- 8.3-35 through 8.3-40 8.3-35 through 8.3-40 8.3-56 8.3-56 8.3-65 8.3-65 8.3-66 8.3-66 8.3-69 8.3-69 8.3-78 8.3-78 8.3-83 8.3-83 8.3-85 through 8.3-88 8.3-85 through 8.3-88 l

lOu l

Page 7 of 13

Instruction Sheet for STP Updated Final Safety Analysis Recon - Revision 6

, - Remove Panes /Finures Insert Panes Chapter 9 4

TC 9-1, TC 9-2 TC 9-1, TC 9-2 TC 9-11, TC 9-12 TC 9-11, TC 9-12 9.1-5 through 9.1-10 9.1-5 through 9.1-10 9.1-15 through 9.1-42 9.1-17 through 9.1-42 9.2-1, 9.2-2 9.2-1, 9.2-2 9.2-5 through 9.2-14 9.2-5 through 9.2-14 9.2-21 through 9.2-30 9.2-21 through 9.2-30 9.2-38 9.2-38

( 9.2-48 9.2-48 9.2-53 through 9.2-56 9.2-53 through 9.2-56 9.2-61 9.2-61 9.2-62 9.2-62 9.3-1 through 9.3-4 9.3-1 through o 3-4 9.3-21,9.3-22 9.3-21,9.3-22 9.3-33,9.3-34 9.3-33,9.3-34 9.3-108 9.3-108

- O5 9.4-3 through 9.4-10 9.4-3 through 9.4-10 9.4-13 through 9.4-18 9.4-13 through 9.4-18 9.4-21 through 9.4-26 9.4-21 through 9.4-26 9.4-33,9.4-40 9.4-33,9.4-40 9.4-43,9.4-44 9.4-43,9.4-44 9.4-97,9.4-98 9.4-97,9.4-98 9.4-107 9.4-107 9.5-1, 9.5-2 9.5-1, 9.5-2 9.5-9 through 9.5-18 9.5-9 through 9.5-18 9.5-23 through 9.5-40 9.5-23 through 9.5-40 9.5-45,9.5-46 9.5-45,9.5-46 9.5-71 9.5-71 Figure 9.5.6-1 Figure 9.5.6-1 Figure 9.5.7-1 Figure 9.5.7-1 9.A-1 through 9A-4 9.A-1 through 9A-4 Chapter 10 TC 10-7, TC 10-8 TC 10-7, TC 10-8 10.2-5,10.2-6 10.2-5,10.2-6 10.2 -11 through 10.2-13 10.2 -11 through 10.2-13 l.

Page 8 of 13

l' Instruction Sheet for {

l_ SIP Updated Final Safety Analysis Reoort - Revision 6 - l i <

g Remove Panes /Firures In_ sert Paees I V 10.3-9,10.3-10 - 10.3-9,10.3-10 4 10.4-3,10.4-4 .

10.4-3,10.4-4 10.4-?5 through 10.4-28 10.4-25 through 10.4-28 10.4-31,10.4-32 10.4-31,10.4-32 l

Figure 10.4.5-1 Figure 10.4.5-1 (ref. sheet) l 10A-7,10A-8 10A-7,10A-8 Chapter 11  !

i TC 11-1through 11-8 TC 11-1 through 11-8 11.2-1 through 11.2-40 11.2-1 through 11.2-40 11.3-1,11.3-2 11.3-1, 11.3-2 '

11.3-24 through 11.3-27 11.3-24 through 11.3-27 11.4-3 through 11.4-10 11.4-3 through 11.4-10  :

11.4-13 11.4-13 l 11.5-5, 11.5-6 11.5-5, 11.5-6 11.5-15,11.5-16 11.5-15,11.5-16 O Chanter 12 12.1-1 through 12.1-4 12.1-1 through 12.1-4 12.3-3 through 12.3 123-31hrough 12.3-12 12.3-17,12.3-18 12.3-17,12.3-18 12.3-21 12.3-21 12.3-30 12.3-30 12.3-33 12.3-33 12.3-34 12.3-34 12.5-9 through 12.5-12 12.5-9 through 12.5-12 1 1

Chapter 13 TC 13-1, TC 13-2 TC 13-1, TC 13-2 TC 13-5 TC 13-5 13.1-1 through 13.1-10 13.1-1 through 13.1-10 {

Figures 13.1-1 through 13.1-7 Figures 13.1-1 through 13.1-9 I 13.2-1, 13.2-2 13.2-1,13.2-2 l

, 13.2-7 through 13.2-10 13.2-7 through 13.2-10 -

Page 9 of 13 y -f . - ~ - , ,e w --

Instruction Sheet for STP Updated Final Safety Analysis Report - Revision 6 Remove Panes / Figures Insert Panes 13.4-1, 13.4-2.. _

13.4-1, 13.4-2

~ 13.5-7 through 13.5-10 13.5-7 through 13.5-10 Chapter 14 -

14.2-1, 14.2-2 14.2-1, 14.2-2 14.2-5 through 14.2-8 14.2-5 through 14.2-8 14.2-13,14.2-14 14.2-13, 14.2-14 4.2-17,4.2-18 4.2-17,4.2-18 14.2-89 14.2-90 14.2-89 14.2-90 Chapter 15 TC 15-5 through TC 15-12 TC 15-7 through TC 15-12 TC 15-21, TC 15-22 TC 15-21, TC 15-22 15.0-18 15.0-18

'O 15.0-26 Figure 15.0-25 15.0-26 Figure 15.0-25 15.4-19,15.4-22 15.4-19,15.4-22 15.4-35,15.4-36 15.4-35,15.4-36 15.4-39 15.4-39 15.6-13 , 15.6-14 15.6-13 ,15.6-14 15.6-17 through 15.6-41 15.6-18 through 15.6-42 Figure 15.6-41 through Figure 15.6-58 Figure 15.6-41 through Figure 15.6-58 15.7-3 through 15.7-20 15.7-3 through 15.7-20 15.8 15.8-1 15.A-1,15.A-2 15. A-1,15. A-2 Chapter 16 16.1-15 16.1-15 16.1-20 16.1-20 16.1-22 16.1-22 Page 10 of 13

Instruction Sheet for STP Updated Final Safe _1y Analysis Repon - Revision 6 -

Remove Panes /Finures Insert Pages Resoonses to NRC Ouestions i

TABLE OF CONTENTS l

TC Q&R 2-1 TC Q&R 2-1 TC Q&R 4-1 TC Q&R 4-1 i TC Q&R 15-1, TC Q&R 15-2 TC Q&R 15-1, TC Q&R 15-2 1 TC Q&R 17-1 TC Q&R 17-1 l I

Q&R Chapter 1 TC Q&R 2-1 TC Q&R 2-1 Q&R 2.3-23, Q&R 2.3-24 Q&R 2.3-23, Q&R 2.3-24 Q&R Chapter 3 Q&R 3.9-9,3.9-10 Q&R 3.9-9,3.9-10 Q Q&R Chapter 4 TC Q&n 4-1 TC Q&R 4-1 Q&R 4.3-5 thro 9gh 4.3-7 Q&R 4.3-5 through 4.3-7 Q&R 4.4-1 through Q&R 4.4-12 Q&R 4.4-1 through Q&R 4.4-12 Q&R Chapter 5 Q&R 5.2-13,5.2-14 Q&R 5.2-13,5.2-14 Q&R 5.2-17, Q&R 5.2-18 Q&R 5.2-17, Q&R 5.2-18 Q&R 5.2-33,5.2-34 Q&R 5.2-33,5.2-34 l Q&R 5.4-7, Q&R 5.4-8 Q&R 5.4-7, Q&R 5.4-8 Q&R 5.4-11 through Q&R 5.4-14 Q&R 5.4-11through Q&R 5.4-14 Q&R Chapter 6 l Q&R 6.1-1, Q&R 6.1-2 Q&R 6.1-1, Q&R 6.1-2 Q&R 6.4-5 Q&R 6.4-5 Q&R Chapter 8 ,

Q&R 8.2-1, Q&R 8.2-2 Q&R 8.2-1, Q&R 8.2-2 -

Page !I of 13

,. _ .- ._. -~_ _. __ . . _ _ _ . . - _ _

l Instruction Sheet for STP Updated Final Safety Analysis Report - Revision 6 L Remove Pages/Ficutes Insert Pages Q&R 8.3-5, Q&R 8.3-6 Q&R 8.3-5, Q&R 8.3-6 l

Q&R 8.3-11, Q&R 8.3-12 Q&R 8.3-11, Q&R 8.3-12 Q&R 8.3-23, Q&R 8.3-24 Q&R 8.3-23, Q&R 8.3-24 Q&R 8.3-31, Q&R 8.3-32 Q&R 8.3-31, Q&R 8.3-32 Q&R 8.3-37, Q&R 8.3-38 Q&R 8.3-37, Q&R 8.3-38 Q&R Chapter 9 Q&R 9.5-27 through 9.5-32 Q&R 9.5-27 through 9.5-32 Q&R Chapter 12 Q&R 12.1-1 Q&R 12.1-1 Q&R Chapter 15 TC Q&R 15-1, TC Q&R 15-2 TC Q&R 15-1, TC Q&R 15-2 Q&R 15.0-3, Q&R 15.0-4 Q&R 15.0-3, Q&R 15.0-4 l s _

Q&R 15.0-7 through Q&R 15.0-10 Q&R 15.0-7 through Q&R 15.0-10

, Q&R 15.0-13, Q&R 15.0-14 Q&R 15.0-13, Q&R 15.0-14 l Q&R 15.0-27, Q&R 15.0-28 Q&R 15.0-27, Q&R 15.0-28 Q&R 15.0-34 through Q&R 15.0-37 Q&R 15.0-34 through Q&R 15.0-37 Q&R 15.0-44, Q&R 15.0-45 Q&R 15.0-44, Q&R 15.0-45 Q&R 15.4-5, Q&R 15.4-6 Q&R 15.4-5, Q&R 15.4-6 Q&R 15.6-5 through Q&R 15.6-12 Q&R 15.6-5 through Q&R 15.6-12 Q&R 15.6-15 through Q&R 15.6-17 Q&R 15.6-15 through Q&R 15.6-17 Q&R 15.7-1 through 15.7-3 Q&R 15.7-1 through 15.7-3 Q&R Chapter 17 TC Q&R 17-1 TC Q&R 17-1 l Q&R 17.2-1 through Q&R 17.2-9 Q&R 17.2-1 through Q&R 17.2-5 I

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Instruction Sheet for I STP Updated Final Safety Analysis Report - Revision 6

_ ' Remove Panes /Finures Insert Panes List Of Effective Pages l

LOEFI through LOEF 88 - LOEFl through LOEF 90 I Note: Pages may not have change bars for one or more of the following reasons:

Corrections of Typographical Errors 1 Information Carried over to a New or Different Page j i

(O v

I Page 13 of 13

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