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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
_ ._ __ .
I%ed 2 CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY
- I LIMITING CONDITION FOR OPERATION l 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
- a. With the structural integrity of the containment not conforming to i the requirements of Specification 4.6.1.6.1.b,. perform an engineering evaluation of the containment to demonstrate the acceptability of containment tendons within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STAN0BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With the structural integrity of the containment otherwise not conforming to the requirements of Specification 4.6.1.6, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days after completion of the inspection describing the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective actions taken.
SURVEILLANCE REQUIREMENTS 4.6.1.6.1 The structural integrity of the containment tendons shall be demonstrated at the end of one, three and five years following the initial containment structural integrity test and at five year intervals thereafter.
The structural integrity of the tendons shall be demonstrated by:
pstM
- a. Oct r ;ining th:t : =pr==tatin :dpl:* cf :t 1:=t 15 t=d:=
G Je;..e, 5 sciti=1, and 0 h=;) =ch h= ; lif t ;f' f:r= cf ;r=W p1M t.b. a e w;l t; 05% ;f it: S: = ":l = indi nted in .. .. .. _. If 4 ,
the lift off force of a selected tendon in a group lies between the 95% Base Value and 90% of the Base Value, one tendon on each side of
- this tendon shall be checked for its lift off force. If the lift off forces of the adjacent 3-tendons are greater than or equal to 95% of their Base Values T:51: ' 5-15, the single deficiency shall be l
considered unique,and acceptable. For tendon (s) not conforming to "For each inspection, the tendons shall be selected on a random but representative basis so that the sample group will change somewhat for each inspection; however, to develop a history of tendon performance and to corre-late the observed data, one tendon from each group (dome, vertical, and hoop) may be kept unchanged after the initial selection.
SUM ER - UNIT 1 3/4 6-8 8609230219 860916 PDR ADOCK 05000395 p PDR m _. _. -
I September 10, 1986 Attachment I Page 2 of 7 Containment Structural Integrity Determining that for a representative sample
- of at least 21 tendons (6 dome, 7 vertical, and 8 hoop) for the 10 year surveillance, and of at least 9 tendons (3 dome, 3 vertical, and 3 hoop) for the five year surveillance intervals thereafter, each has a lift off force greater than or equal to 95% of its Base Value.
i I
1
m R-tRtA 1.
CONTAINMENT SYSTEMS
'pp 3 '/
SURVEILLANCE REQUIREMENTS (Continued) e these requirements, a determination shall be made as to the cause of the occurrence and the tendon (s) shall be restored to the required
, level of integrity.
If the lift-off force of the selected tendon lies below 90% of its Base Value, the tendon shall be completely detensioned and a determination made as to the cause of the occurrence.
- b. Determining that the average of the Normalized Lift Off Forces for each tendon, group (vertical, dome and hoop) is greater than or equal to the minimum required average tendon force The , ,
minimum requir average tendon force is {gpsthe group.
for vertical tendons, M15F ps for dome tendons, and c ps for hoop tendons.
The Normalized Lift Off Force for a tendon is obtained by adding the '
Normalizing Factor appearing in Tat,le ".5-2 to the lift off force. . 4 Failure to comply with this requirement may be evidence of abnormal degradation of the containment structure.
If the Normalized Lift-Off Force of any tendon is less than the applicable minimum required average tendon force, an investigation shall be conducted to determine the cause and extent of occurrence.
This investigation shall include as a minimum the measurement of lift-off forces of tendons adjacent to the deficient tendon to
^. determine if the average of the tendon lift-off forces in this i region of the containment is equal to or greater than the minimum ,
required average tendon force. Failure to comply with this requirement '
may be evidence of abnormal degradation of the containment structure. l
- c. Detensioning one tendon in each group (dome, vertical and hoop) from the representative sample. One wire shall be removed from each detensioned tendon and examined to determine:
- 1. That over the entire length of the tendon wire, the wire has not undergone corrosion, cracks or damage to the extent that an l abnormal condition is indicated. I
- 2. A minimum tensile strength value of 240,000 psi (guaranteed ultimate strength of the tendon material) for at least three l wire samples (one from each end and one at mid-length) cut from '
each removed wire. ;
l
- d. Determining for each tendon in the above reprdsentative tendon sample, l that an analysis of a sample of the sheathing' filler grease is l within the following limits: "
- 1. Grease Voids j 5% of net duct volume 1
- 2. Chlorides J 10 PPM
- 3. Sulphides 1 10 PPM
- 4. Nitrates j 10 PPM
- 5. Water Content 5 10% by weight SUP94ER - UNIT 1 3/4 6-9 l
t . ., m -
.m _ u
T f SQ wth CONTAINMENT SYSTEMS
]gp 4 g SURVEILLANCE REQUIREMENTS (Qontinued)
If the inspections performed at 1, 3, and 5 years indicate no abnormal degradation of the tendon system, the number of sample tendons may be reduced to 3 dome, 3 vertical, and 3 hoop for subsequent inspections. Upon the comple-tion of the five year inspection, the results of the first three inspections shall be evaluated to determine if an abnormal condition is evident for the tendon system. "e;;d :. th: cent'r:ftr 0' thf: Ord ustfr , "e : -' tr i r,.
. . . . . . , . . . , . . . . . . . . _ . . . . _ . . . _ . . _ . . . , . _ _ _ _ . _ he ;er?'f ed 9'
- : q.:.-t ' :;::t':r.
4.6.1.6.2 At the same inspection frequency as the tendons, the structural integrity of the end anchorages of all tendons inspected pursuant to Specifica4 -
tion 4.6.1.6.1 and the adjacent concrete surfaces shall be determined by a visual inspection and verifying that no abnormal material or structural behavior is evident 4.6.1.6.3 At the same inspection frequency as the Type A containment leakage rate test, the structural integrity of the exposed accessible interior and exterior surface *, of the containment shall be determined prior to each Type A containment leakage rate test (Specification 4.6.1.2) by a visual inspection of these surfaces and verifying that no abnormal material or structural behavior is evident.
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l SUM 4ER - UNIT 1 3/4 6-10 w.
r
/ 9R uv1u wc@
Table 4.6-la. Base value of tendon force '
. SURVEILLANCE TENDONS
[
O 1NseECT10N eEat00 /
1 2
[ 3 Base value Base value Base value Tendon (kips) Tendon (kips) Tendon (kips) 0-104 1275 0-125 / 1230 0-108 1287 0-129 1245 0-21 2 0-121 1225 0-219 1265 0 5 0-213 1223 0-328 1287 1273 0-316 1284 -
V-23 1328 1319 V-23 1313 V-46 13 / 1287 V-37 1299
, V-67 1 2 53 1316 V-60 1294 V-92 V-76 1315 V-83 1314 1299% V-99 1309 V-106 1296 V-115 1322 i 3AC 1318 3AC 1309 3AC 1303 ,
8BA 126 13BA 1278 8CB 1249 13CB 3- 18CB 1259 18BA 1249 P 28CB 260 28BA 1259 28AC 1259 38AC 1250 33CB 1278 33BA 1272 38 1250 41AC 1268 38CB 1226 l
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3/4 6-10a Amendment No. 22
r
%2nd '
L- y a 4, '
- Table 4.6-lb. Base value of tendon force A0JACENT TENDONS ,'
INSPECTION PERIOD [ g 1 2
[3 Base value Base value ase value (kips) Tendon (kips) Tendo (kips)
Tendon 0-124 1284 0-1 1241 0
0-103 1245 0-105 1250 0-126 1262 0- 09 1222 D-128 1296 0-212 1300 -120 1284
, 0-130 1267 D-214 1252 0-122 1264 0-218 1296 0-227 1270 0-212 1294 0-220 1299 0-229 1235 0-214 1248 0-327 1244 0-323 1256 0-315 1266 l
0-329 1237 D-325 1227 0-317 1233 l
V-22 1306 V-22 130 V-22 1295 V-24 1320 V-24 1 7 V-24 1313 l-V-45 1308 V-29 01 V-36 1284 l .
V-47 V-66 1322 W- 1327 1316 V-38 V-59 1293 1308 &
> 1309 Sr52' W V-68 1309 1298 V-61 1309
'I V-82 1297 V-91 V-93 1309 1327 /NQ7 1304 1313 V-84 V-105 1311 1297 V-114 V-1 1
1 Q -98V-100 1280 1300 V-107 1307 2AC 1272\ 2AC 1265 2AC 1260 4AC 1255 4AC 1248 4AC 1242 7BA 1318 12BA 1262 7CB 1298 9BA 1286 14BA 1259 9CB 1275 l 12CB 12 17CB 1268 17BA 1256 14CB 6 19CB 1282 19BA 1284 27CB 273 27BA 1285 27AC 1291 29CB 1276 29BA 1268 29AC 1250 37AC 39A 1278 1290 32CB 34CB 1256 1229 32BA 34BA 1253 1249 37 A 1289 40AC 1272 37CB 1272 BA 1266 42AC 1251 39CB 1286 O
O i
3/4 6-10b Amendment No.22
Y Y L.
Table 4.6-2.
w n41 Normalizing factors (N.F.)
INSPECTION PERIOD
/
O 2
/
N.F.
N.Fj ) [ N.F.
Tendon (kips) Tendon gs /Tdon (kips) 0-104 -24 0-1 36 0-108 -42 0 0-129 0-219 33 10 0-0 N6 -
0-121 0-213 40 46 0-328 -21 0- -12 0-316 -31 V-23 -15 % V-y -15 V-23 -15 V-46 11 V3 31 V-37 -5 -, '
V-67 -2 3 -24 V-60 11
-76 -11 V-83 -15 V-92 7 5.0 -
V-115 3AC g 56 V-99 3AC 5
-56 V-106 3AC 7
-56 8BA 13BA -26 8CB 26 13CB -23 18CB 29 188A 34 28CB 26 28BA 17 28AC 10 38 40 33CB -17 33BA -16 A 40 41AC 0 38CB 54 l O
O Y .
O SUMER - UNIT 1 3/4 6-10c Amendment No. 22
ATTACHMENT ll
. NO SIGNIFICANT HAZARDS DETERMINATION Based on the following evaluation, SCE&G has determined the proposed change does not involve a significant hazards consideration.
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? NO The proposed change involves a revision to the testing program for the Reactor Containment Post-tensioning system. It does not change any of the hardware on this tendon system. It specifies the testing program to be used in the future for containment tendons. The Acceptance Criteria for the tendon forces has been revised. However, this acceptance criteria has been verified to enable the containment tendons to perform their design basis function under all postulated loads and loading conditions.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previous evaluated? NO The proposed change provides for a continued testing pro,g ram for tendons that will adequately ensure containment integrity. It wiu not create the possibility of a different kind of accident.
- 3. Does the proposed change involve a significant reduction in a margin of safety? NO The proposed testing program will continue to provide assurance of the integnty of the containment post tensioning system and will provide for warnm,g and appropriate actions if abnormal degradation should develop.
The mmimum average tendon force values have been reduced due to i
conservatism in the onginal values. However, the reduced values have been verified to enable the containment to meet all postulated loads and loading combinations as required to maintain safety. Therefore, the margin has been t
lowered to eliminate conservatism, but not so as to affect plant safety.
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