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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20202G6891998-02-0909 February 1998 Proposed Tech Specs Requesting Removal of Table 4.8-1, Diesel Generator Test Schedule & SR 4.8.1.1.3,Repts ML20141K2481997-05-21021 May 1997 Proposed Tech Specs Revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Emergency Safeguards Features Air Handling Units ML20140C0641997-03-26026 March 1997 Proposed Tech Specs 3.8.1.1 Re AC Sources - Operating ML20140C1401997-03-26026 March 1997 Proposed Tech Specs Re Change to Core Alteration Definition ML20140C1071997-03-26026 March 1997 Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves ML20107G3511996-04-16016 April 1996 Proposed Tech Specs 3/4.6 Re Containment Sys,Per App J, Option B ML20101E6461996-03-19019 March 1996 Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR ML20097F4721996-02-10010 February 1996 Proposed Tech Specs,Revising Testing Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation ML20078B6121994-10-20020 October 1994 Proposed TS Page,Incorporating Approved Amend 116 & Requested SR Replacement TS Change ML20076J6691994-10-17017 October 1994 Proposed Tech Specs,Reflecting Relocation of Seismic Monitoring Instrumentation Lco,Srs & Associated Tables & Bases in TS Section 3/4.3.3.3 to FSAR or Equivalent Controlled Document ML20073D4111994-09-20020 September 1994 Proposed TS Pages,Including Page 6-16a,revising Rev Level & Date of WCAP-10216-P-A to Reflect Updated Methodology Used in Determining Plant Core Operating Limits ML20149G1301994-09-20020 September 1994 Proposed TS 3/4 5-6 Re Charging Pump Runout Flow Limit ML20071K3761994-07-22022 July 1994 Proposed TS Page 3/4 3-56,reflecting Required Action to Restore One Inoperable Hydrogen Monitor Channel to Operable Status,W/Less than Min Number of Channels Operable ML20070J7561994-07-20020 July 1994 Proposed Tech Specs,Permitting Alternative Equivalent Testing Methods to Be Performed on Diesel Fuel Purchased for EDGs & Changing Rev Level of WCAP-10216-P-A,that Will Be Used to Determine Core Operating Limits for Future Cycles ML20070J7881994-07-20020 July 1994 Proposed TS Pages for TS Tables 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints & 3.3-4, ESFAS Instrumentation Trip Setpoints ML20065B8361994-03-25025 March 1994 Proposed Tech Specs Pages for Missing Page Numbers of TS Pages Submitted in ML20064H9591994-03-11011 March 1994 Proposed TS 4.8.4.1.a.3,deleting Fuses Used as Penetration Overcurrent Protection Devices from SRs & from Bases B 3/4.8.4 ML20064H9251994-03-11011 March 1994 Proposed Tech Specs 3/4.4.9.3,changing AOT for RHR Suction Relief Valves from 7 Days to 72 H ML20064H4501994-03-11011 March 1994 Proposed Tech Specs Re Steam Generator Replacement ML20064G5541994-03-11011 March 1994 Proposed Tech Specs Re Limiting Safety Sys Settings for Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint ML20064C6421994-02-25025 February 1994 Proposed Tech Specs,Incorporating Current Provisions of 10CFR50.36(a)2 Re Semiannual Radioactive Effluent Release Rept to Be Submitted Annually Rather That Semiannually ML20062K6321993-12-13013 December 1993 Proposed Tech Spec Figures 3.9-1 & 3.9-2,permitting Storage of Fuel Assemblies in Regions 2 & 3 of Spent Fuel Storage Racks,Respectively ML20059G2901993-10-29029 October 1993 Proposed Tech Specs Supporting SG Replacement ML20056F7951993-08-24024 August 1993 Proposed Revised TS Re Emergency Feedwater Per 10CFR50.59 ML20045F7771993-06-30030 June 1993 Proposed Tech Specs SR 4.7.1.2 for Performance of Turbine Driven EFW Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig ML20045C3441993-06-16016 June 1993 Proposed Tech Spec 4.7.1.2.a.2 Supporting Request to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig ML20044G7551993-05-25025 May 1993 Proposed Tech Specs Revising Page 3/4 7-4,re Changing TS 4.7.1.2.a.2,to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psi ML20128H9781993-02-12012 February 1993 Proposed TS Modifying Insp Requirements of TS 3/4.4.5 Re SGs & LCO for 3/4.4.6.2 Re Operational Leakage to Establish Interim Plugging Criteria ML20128K1821993-02-10010 February 1993 Proposed Tech Specs Re Main Steam Safety Valves 1999-08-19
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20212H4651999-05-0404 May 1999 Amend 17 to Training & Qualification Plan ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20202C3271998-08-31031 August 1998 Amend 16 to Training & Qualification Plan ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20153F9241998-04-23023 April 1998 Change A,Rev 10 to FEP-1.0, Fire Emergency Procedure Selection ML20153G7081998-03-30030 March 1998 Rev 2 to FEP-4.1, Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire in Control Building ML20153F9691998-03-25025 March 1998 Rev 3 to FEP-3.1, Train B Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire ML20153F9341998-03-23023 March 1998 Rev 3 to FEP-2.0, Train a Plant Shutdown to Hot Standby Due to Fire ML20202G6891998-02-0909 February 1998 Proposed Tech Specs Requesting Removal of Table 4.8-1, Diesel Generator Test Schedule & SR 4.8.1.1.3,Repts ML20203H5741998-02-0505 February 1998 Rev 31,change C to EPP-002, Communication & Notification ML20203H5981998-02-0202 February 1998 Rev 3 to EPP-105, Conduct of Drills & Exercises ML20203H5831998-01-27027 January 1998 Rev 5 to EPP-103, Emergency Equipment Checklist ML20153F9461997-10-22022 October 1997 Rev 2 to FEP-2.1, Train a Shutdown from Hot Standby to Cold Shutdown Due to Fire, Change B ML20153F9511997-10-22022 October 1997 Rev 2 to FEP-3.0, Train B Plant Shutdown to Hot Standby Due to Fire, Change B ML20153F9931997-10-22022 October 1997 Rev 2 to FEP-4.0, Control Room Evacuation Due to Fire, Change D ML20210V2481997-06-30030 June 1997 Amend 15 to Training & Qualification Plan ML20217H3521997-06-16016 June 1997 Amend 14 to, Training & Qualification Plan ML20141K2481997-05-21021 May 1997 Proposed Tech Specs Revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Emergency Safeguards Features Air Handling Units ML20140C1071997-03-26026 March 1997 Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves ML20140C1401997-03-26026 March 1997 Proposed Tech Specs Re Change to Core Alteration Definition ML20140C0641997-03-26026 March 1997 Proposed Tech Specs 3.8.1.1 Re AC Sources - Operating ML20137F8501997-02-0404 February 1997 Change E,Rev 7 to Inservice Testing of Pumps Second Ten Year Interval RC-96-0229, Startup Report for VC Summer Nuclear Station Power Uprate1996-09-23023 September 1996 Startup Report for VC Summer Nuclear Station Power Uprate ML20138H7191996-09-0606 September 1996 Rev 22 to ODCM for VC Summer Nuclear Station ML20134J9741996-06-0505 June 1996 V C Summer Fuel Assembly Insp Program ML20107G3511996-04-16016 April 1996 Proposed Tech Specs 3/4.6 Re Containment Sys,Per App J, Option B ML20138H7141996-03-25025 March 1996 Rev 21 to ODCM for VC Summer Nuclear Station ML20101E6461996-03-19019 March 1996 Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR ML20097F4721996-02-10010 February 1996 Proposed Tech Specs,Revising Testing Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20093F6131995-08-31031 August 1995 Rev 7 to General Test Procedure (Gtp) GTP-301, IST of Pumps Second Ten Yr Interval ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20107L8771995-01-31031 January 1995 Rev 19 to Offsite Dose Calculation Manual ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation 1999-08-19
[Table view] |
Text
r o n A %<_L d A q A -
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- g. I Allt.L 3.6-1 (Chnlinuetl}
m E
eo ruill Al..tlH.l. l.l.i . I.S..O..L_ ail 0tl VALVES OM .
o* VALVE tillHilER MAX 1 HUM C. ItLAClillTBUILDlHG PURGE Sill'Pl.Y ISOLATION TIME OO ANu. LxTl50sn SOLAt loti- ~ ItlNCIION
' - ~ -
(SEC) 00 .
a8@ 1. 0001 A- All 1:cactor fluililing Purge Supply 5 gM 2. 00010- All 1:carlor llui bling Purrie Supply 5 .
ui 3. 0002A-All 1:".u. tor flui hiing Purge Exhaust 5
- 4. 00020-All Ib actor fluililing Purge Exhaust 5 5 ." 6056-ilR Alternate Reactor fluiltling Purge Supply Line 5
- 6. 6057-IIR .
Alternate licaclor Building Purge Supply Line 5 .
- 7. 6066-ilR Alt ernate Reactor iluililing Purge Exhaust Line 5
- 8. 6067-IIR Alt ernate Reactor 11uililing Purge Exhaust Line 5 D. MANUAL O) *
l. 8767-DN llemineralii.cti Waler Line N/A
- 2. 8768-1)N Hemineraliicti Wat er 1.ine N/A
'l- 3. 6772-FS I ire Service llose Heel Supply N/A
'1 4. 6773-FS I ire Service llose Heel Supply N/A a- 5. 2679-IA lircathing Air Supply Line N/A
- 6. 2680-IA fireathing Air Supply Line ,N/A
- 7. 6587-NG llilrogen Supply To Steam Generators 'N/A i
G. 3000A RC lL ...l L ul'l les;ci E/A
- 3. G0000 "C ;;c.n; E 'u;'l I':de* N/A
- 10. 2912-SA 1:c.ictor ilui kling Service Air N/A
- 11. 6671-SF 1:eIncling Cavity Drain Line N/A J2. 6672-SF Refueling Cavity Drain Line N/A k Relueling Cavity Fill Line
~
,. 13. 6697-SF N/A
,' 14, 6698-SF liclueling Cavity Fill I.ine N/A
- 15. 7135-WL lb actor Coolant Drain Tank Discharge To Waste N/A E. REMOTE MANUAL I2) t j ,
- 1. 9602-CC Component Cooling To R. C. Pumps N/A l 2. 8102A-CS ## ' . cal injection To Reactor Coolant Pump A N/A l
.: 3. 810211-C5 4# '. cal injection lo Reactor Coolant Pimp B N/A
- 4. 8102C ,C5 4# ' cal injection lo Reactor Coolant Pump C N/A
( I y
k v'
i TA01E 3.6-1 (Continued) ,
p '
] CONTAINHENT ISOI.ATION VALVES
'e
. NAXIMUM c- VALVE NUMBER ISOLATION T;ME
}
L. REMOTE MANUAL (Continued). TUNCTION . (SEC)
... 5. 0107-CS Charging Line To Regenerative lleat Exchange N/A
- 6. 60500-IIR llydrogen Analyzer Return Line N/A
- 7. 6051A-flR Ilydrogen Analyzer Supply line N/A
- 8. 60510-flR llydrogen Analyzer Supply Line N/A
- 9. 6051C-IIR llydrogen Analyzer Supply line N/A
- 10. 6052A-IIR llydrogen Analyzer Return Line N/A
- 11. 60528-IIR llydrogen Analyzer Return Line N/A
- 12. 6053A-IIR llydrogen Analyzer Supply Line N/A
- 13. 60538-ilR Hydrogen Analyzer Supply Line 'N/A i 14, 8701A-Ril-## RilR Pump Suction From Reactor Coolant loop A N/A
- 15. 87018-Ril# RIIR Pump Suction from Reactor Coolant loop C N/A
.., 16. (1801 A-S I linran injection Tank To Reactor Coolant loops N/A l ',', 17. Bl1010-SI (1oran injection Tank To Reactor Coolant toops N/A 1 m III. 8811A-SI Rllir Pump A Suction From Recirculation Sump N/A 4
- 19. fl811B-SI RilR Pump B Suction From Recirculation Sump N/A i [f 20. 8804-SI liigh llcad Sarcty Injection To Reactor Coolant loops N/A
- 21. T1885-51 liigh llead Safety Injection To Reactor Coolant Loops N/A 3
, 22. 11886-51 liigh lle;ui' Safety Injection To Reactor Coolant loops N/A
- 23. f1880A-S i Iow ! lead Safety Injection To Reactor Coolant loops N/A
- 24. 88880-51 l.ow licad Safety Injection To Reactor Coolant Loops N/A
- 25. 8889-SI 1.ow Ilead Safety injection To Reactor Coolant Loops N/A 2fi. 3003A-SP Supply To Reactor Duilding Spray Nozzles N/A g
- 27. 30030-SP Supply To Reactor Dullding Spray Nozzles N/A
- 20. 3004A-SP 5 pray Pump A Suction From Recirculation Sump N/A
- 29. 30048-SP Spray Pump B Suction From Recirculation Sump N/A
- 30. 3103A-SW Service Water From Reactor Dullding Cooling Unit A N/A
- 31. 3103D-SW Service Water From Reactor Building Cooling Unit B N/A
- 32. 3106A-SW Service Water To Reactor Building Cooling Unit A N/A
- 33. 31068-SW Service Water To Reactor Building Cooling Unit B N/A
- 34. 3110A-5W Service Water To Reactor Building Cooling Unit A N/A
' 35. 31100-SW Service Water To Reactor Building Cooling Unit 0 N/A
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Attachment B l
Proposed "No Significant Hazards Determination" The changes to Table 3.6-1, " containment Isolation Valves" being requested by SCE&G have been determined by the Licensee to involve a no significant hazards d e te rminat ion. The deletion of the two valves (8090 A and B) from the table is a result of a modification to be perforced to eliminate the valves. The requested relief from Type C testing for the eight additional valves included in this submittal is justified based on the fact that these valves do not fall under any of the criterion for Type C testing in accordance with 10CFR Part 50, Appendix J. SCE&G considers these changes to be consistent with the present regulations contained in 10CFR50, Appendix J and therefore proposes that they involve a no significant hazards determination.