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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 ML20132E6211996-12-17017 December 1996 Proposed Tech Specs 3/4.7.3 Re Component Cooling Water Sys ML20132B5111996-12-10010 December 1996 Proposed Tech Specs Re Groundwater Level Exceeding Current Maximum Water Level ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML20134H0051996-11-0606 November 1996 Proposed Tech Specs,Modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20134F8781996-09-0404 September 1996 Proposed Tech Specs Requiring Exemption from Certain Requirements of 10CFR50.44, Stds for Combustible Gas Control Sys in Light Water Cooled Power Reactors & 10CFR50.46, Acceptance Criteria for Eccs.. ML20107L3951996-04-25025 April 1996 Proposed Tech Specs,Providing Suppl Info Re Clarification of TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101Q0871996-04-0808 April 1996 Proposed Tech Specs Re EDG Allowed Outage Times ML20101F7971996-03-21021 March 1996 Proposed Tech Specs,Clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguards Area Ventilation Sys ML20097C0171996-01-31031 January 1996 Proposed Tech Specs,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy Portions of SRs Required During Shutdown ML20097J4341996-01-30030 January 1996 Proposed Tech Specs,Modifying Table 3.2-1 of TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9871996-01-23023 January 1996 Proposed Tech Specs,Permitting Use of 10CFR50,App J,Option B performance-based Containment Lrt ML20094N7921995-11-20020 November 1995 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0191995-10-25025 October 1995 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K5921995-10-17017 October 1995 Proposed TS 4.4.5.1,Table 4.4-1,reducing from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20093K6161995-10-17017 October 1995 Proposed Tech Specs,Allowing Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20092J4231995-09-19019 September 1995 Proposed Tech Specs,Increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J3051995-09-19019 September 1995 Proposed Tech Specs,Revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2481995-09-0101 September 1995 Proposed Tech Specs,Allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087A1171995-07-26026 July 1995 Proposed Tech Specs,Increasing Pressurizer Safety Valve Lift Setpoint Tolerance as Well as Reduce Pressurizer High Pressure Rt Setpoint & Allowable Value ML20087A1311995-07-26026 July 1995 Proposed Tech Specs,Clarifying TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20087G3471995-03-30030 March 1995 Proposed Tech Specs Re Changes That Allow One of Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operationin Order to Refurbish Isolated Svc Water Headers 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20211D9201999-08-20020 August 1999 Revised Pages to Third Ten Year ISI Program & Relief Requests ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20195B5881999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna Unit 2 IST Program Plan for Pumps & Valves Second Insp Interval,901214-001214 ML20195B5691999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna,Unit 1 IST Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20205P2511999-05-0101 May 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Program Plan for Third Insp Interval:Components & Component Supports ML20205P2341999-05-0101 May 1999 Rev 0 to Vepc North Anna Unit 1 ISI Program for Third Insp Interval Vol 1:ISI Program for Components & Component Supports for Interval 3 990501-090430 ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20205P2651999-02-0404 February 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Plan for Third Interval for Sys Pressure Tests ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20196K1971998-12-22022 December 1998 Rev 0 to NE-1176, North Anna Unit 1,Cycle 14 Startup Physics Tests Rept, Dec 1998 ML20206N8851998-12-14014 December 1998 Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval ML20206N8711998-11-30030 November 1998 Rev 11,Vol I to ISI Plan for Second Insp Interval for Components & Component Supports ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20236H5311998-07-0101 July 1998 Draft Nuclear Control Room Operator Development Program NAPS Module NCRODP-78 Spent Fuel Dry Storage Cask System. Draft Lesson Plans & Job Performance Measures Included ML20236U8891998-06-25025 June 1998 Rev 0 to NE-1163, North Anna Unit 2 Cycle 13 Startup Physics Tests Rept ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20236H5541998-06-0404 June 1998 Rev 5 to Procedure VPAP-0810, Crane & Hoist Program ML20236H5391998-06-0404 June 1998 Rev 1 to Procedure VPAP-0809, NUREG-0612 Heavy Load Program ML20206N8581998-04-30030 April 1998 Rev 5,Vol 1 to ISI Program for Second Insp Interval & Components & Component Supports,For 901214-010430 ML20236H5701998-04-0202 April 1998 Rev 8 to Procedure VPAP-1901, Industrial Safety & Health ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML20236H5631998-02-10010 February 1998 Rev 11 to Procedure VPAP-0105, Fitness for Duty Program ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20210Q2051997-12-31031 December 1997 1997 Severe Accident Management Tabletop (Scenario 1) Drill Manual ML20203G5191997-12-29029 December 1997 Ultrasonic Exam Technique for Detection of Microbilogically Induced Corrosion in North Anna Stainless Steel Service Water Piping ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20198G5401997-08-31031 August 1997 Rev 0 to NE-1133, North Anna Unit 1,Cycle 13 Startup Physics Tests Rept, Aug 1997 ML20199G5681997-06-30030 June 1997 Rev 5 to VPAP-2001, Station Planning & Scheduling. Even Numbered Pages of Incoming Submittal Not Included ML20210Q1991997-06-10010 June 1997 Rev 0 to VPAP-2604, Severe Accident Mgt Guideline (SAMG) Program Administration ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 1999-08-04
[Table view] |
Text
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O TABLE 3.7-5
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g ALLOWABLE 1DTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES 3
% ALLOWABLE ALLOWABLE TOTAL DIFFERENTIAL
$ SETTLEMENT SETTLEMENT
, SETTLEMENT POINT STRUCTURE POINT STRUCTURE / COMPONENT (FEET) (FEET)
E .
U 130 Containment Unit 1 223 Fuel Building N/A 0.12 w
130 Containment Unit 1 129 Auxiliary Building N/A 0.12
- I43 y .y g Containment Unit 1 142 Unit 1 Safeguards Area N/A 0.04 t3m "
144 "O Containment Unit 1 145 Unit 1 Safeguards Area N/A 0.04 D5 0.12 149 gg Containment Unit 1 239 Unit 1 Main Steam Valve House N/A 09 144 X" Containment Unit 1 243,199,132 Service Building N/A 0.12 II^ O$ Safeguards Area Unit 1 239 Unit 1 Main Steam Valve House N/A 0.07 146 oo Y con 238 Unit 1 Main Steam Valve House N/A 0.08
- ! 128 gpjo Auxiliary Building CD 129 Auxiliary Buildiag 239 Unit 1 Main Steam Valve House 'N/A 0.08-129 Auxiliary Building 223 Fuel Building N/A 0.05 i 123 f.uxiliary Building 224 Fuel Building N/A. 0.05 122 Auxiliary Building 119 Service Buidling Tunnel' N/A 0.07 7 or 10 Service Water Pump House 17,18 North Side of Expansion Joint. N/A 0.22 from 7/77 Service Water Piping at SWPH 243,132 Service Building (E-5, 238 Unit 1 Main Steam Valve House N/A 0.06 1 E-6) 117 '** Service Building 113 Unit 2 Main Steam Valve House. N/A- 0.047 from 7/77 (E-14) 222 Auxiliary Feedwater Pump 240 Pipe Tunnel N/A 0.12 House - Unit I
O g TABLE 3.7-5 M
- x: ALLOWABLE TOTAI. SETTLIGIENT OR DIFFERFNTIAL SETTLEMENT FOR CLASS I STRUCTURES U
x ALLOWABLE AI.LOWABLE TOTA 1. DIFFERENTIAL EE SETTLFMENT SETTLEMENT SETTLEMENT
- POINT STRUCTURE POINT STRUCTURE / COMPONENT (FEET) ___ (FEET) 17,18 North Side of Expansion 0.22 from 8/78 N/A Joint Service Water Piping at SWPil 228 Decontamination Building 250 Pipe Tunnel N/A 0.06 226 Fuel Building 251 Waste Gas Decay Tank N/A 0.06 Enclosure i
114 Service Building (E-17) 0.09 N/A 141 Safeguards Area - Unit 1 253 Unit 1 - Cising N/A 0.12 from 2/79 M
158 *** Turbine Building (B-9 t/2) 0.06 N/A 7
0 245, 246 Fuel Oil Pump flouse 0.03 N/A 206, 207, 208, 209 Boron Recovery Tank Dike 0.03 N/A 204 Circulating Water Intake Structure 0.15 N/A 25,26,27,28 Service Water Valve llouse 0.32 !a- note) N/A 29,30,31,32 Service Water Tie-in Vault 0.12 (see note) N/A i NOTE: From date of Piping Tie-in
- Unless otherw'se indicated, all"wable settlements are from baseline elevations established in May 1976 or. reference elevations ccrrected to the May 1976 survey. ,
- Critical differential settlement is downward movement of Point 117 with respect to Pctnt 113. . -
- Not Class I structure, but settlements affects Class I pipeline.
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TABLE 3.7-5 '
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ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STkUCTURES
.h M
h5 ALLOWABLE ALLOWABLE TOTAL DIFFERENTIAL g SETTLEMENT SETTLEMENT SETTLEMENT
- 4 POIF CTRUCTURE POINT STRUCTURE / COMPONENT (FEET) (FEET) e --
" 224 Fuel Building N/A 0.12 131 Containment Unit 2 131 Containment Unit 2 123 Auxiliary Building N/A 0.05 i
106 Containment Unit 2 105 Unit 2 Safeguards Area N/A 0.07 107 Containment Unit 2 108 Unit 2 Safeguards Area N/A 0.07 131 Containment Unit 2 124 Unit 2 Main Steam Valve House N/A 0.03 107 Containment Unit 2 116 Service Building (E-15) N/A 0.12 N
111 Safeguards Area Unit 2 124 Unit 2 Main Steam Valve House N/A 0.12
$ 122 Auxiliary Building 120 Unit 2 Main Steam Valve House N/A 0.04 123 Auxiliary Building 124 Unit 2 Main Steam Valve House N/A 0.04 123 Auxiliary Building 224 Fuel Building N/A 0.05 129 Auxiliary Building 223 Fuel Building N/A 0.05 122 Auxiliary Building 119 Service Buidling Tunnel N/A 0.07 243,132 Service Building (E-5, 238 Unit 1 Main Steam Valve Houee N/A 0.04 E-6) 117 ** Service Building 113 Unit 2 Main Steam Valve House N/A 0.047 from 7/77 (E-14) 231 Auxiliary Feedwater Pump 249 Pipe Tunnel N/A 0.12 House - Unit 2 228 Decontamination Building 250 Pipe Tunnel N/A 0.06 d
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TABLE 3.7-5 I.
O ALLOWABLE TUTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS I STRUCTURES ,
5
- o ALLOWABLE ALLOWABLE N TOTAL DIFFERENTIAL SETTLEMENT SETTLEMENT SETTLEMENT
3 g POINT STRUCTURE POINT STRUCTURE / COMPONENT (FEET) (FEET) 226 Fuel Building 251 Waste Gas Decay Tank N/A 0.06-h Enclosure a
w 104 Safeguards Area Unit 2 254 Unit 2 Casing Cooling N/A 0.12 Building from 2/79 7, 10 Service Water Pump House 17, 18 Service Water Piping N/A 0.22-at SWPH from 7/77 17, 18 Service Water Piping 0.22 from 8/78 N/A at SWPH North Side of Expansion Joint y 204 Circulating Water Intake 0.15 N/A; A Structure Y
g 158 *** Turbine Building 0.06 N/A (B-9 1/2) 114 Service Building (E-17) 0.09 N/A 245, 246 Fuel Oil Pump House 0.03 N/A.
206, 207, 208, 209 Boron Recovery Tank Dike 0.03 _N/A 25,26,27,28 Service Water Valve House 0.32 (see note) N/A-29,30.31,32 Service Water Tie-in Vault 0.12 (see note) N/A NOTE: From date of piping tie-in
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ATTACHMENT 2 SAFETY EVALUATION l
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Virginia Electric and Power Company l
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, Change to Units 1 and 2 Technical Specification Table 3.7.5, Allowable Total Settlement or Differential Settlement for Class 1 Structure." j l
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DISCUSSION l l
The proposed changes to Technical Specifications Section 3.7.12, Table 3.7.5 deletes the Settlement Monitoring requirements for Service Water lines which were removed from service and replaced with new lines connecting the Service Water System to the new Service Water valve house and spray headers during the Service Water Reservoir Improvement Project in 1987.
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BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION The proposed change to delete monitoring of settlement points no longer in l service does no* involve a significant hazards consideration because operation of North Anna Units 1 & 2 in accordance with this change would not:
l (1) involve a significant increase in the probability or consequence of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any ,
accident previously identified, or (3) involve a significant reduction in a margin of safety, because this !
change only deletes Settlement Monitoring on equipment previously '
replaced. This replacement was approved by the NRC via license I amendment 91 for Unit 1, and license amendment 76 for Unit 2, both '
dated March 27, 1987. '
Therefore it has been concluded that the proposed change does not involve a ;
significant safety hazards consideration.
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DISCUSSION The proposed change will also revise the limit for differential settlement between points 117 and 113 of Table 3.7-5. The differential settlement between settlement monitoring points 117, the Service Building, and 113, the Unit 2 Main Steam Valve House (MSVH), has frequently approached 75% of the allowable value in Table 3.7-5 of Technical Specification Section 3.7.12, and the measured value exceeded 75% of the allowable value in June 1987 and in 1980. A report on exceeding 75% of allowable differential settlement between these two points was submitted to the Commission in 1981 and in August 1987 in accordance with Technical Specifications. ~The report of August 1987 is provided in Attachment 3.
The primary concern of the differential settlement between the Service Building and the Unit 2 MSVH is the effect on. the four buried service water lines running between the two structures. The code allowable stress in the service water lines for differential settlement condition is 45,000' psi. As stated in -
the Technical Specifications, critical differential settlement is downward movement of the Service Building with respect to the MSVH. The results of an engineering analysis show that. . disregarding survey inaccuracies, there has been negligible additional settlement of the Service Building since 1981.
The differential settlement limit of 0.03 feet in the Technical Specification was based upon an estimate of future differential settlement between points 117 ,
and 113. The Service Water pipe stress analysis shows that considerable margin exists before code allowable stresses would be exceeded and, therefore, the differential settlement of the Service Building with respect to the Unit - 2 MSVH has had no significant impact on the service water pipes or on plant operability.
The proposed change will revise the allowable value of differential settlement l between the Service Building and the Unit 2 MSVH from 0.03 feet to 0.047 feet.
This value, 0.047 feet, corresponds to a stress of 44,176 psi in the -service water lines, which is still below the code allowable stress of 45,000 psi.
This action would mean that the 75% reportable threshold would increase.
Therefore, additienni review need only be initiated when there is significant concern. ;
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i BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION The proposed change to increase the Allowable Differential Settlement between points 117 and 113 does not involve a significant hazards consideration as defined by 10 CFR 50.92 because operation of North Anna 1 and 2 in accordance with this change would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated as the stress in the service water lines for the requested value of differential settlement has been verified to be below the code allevable stress. j
- 2. Create the possibility of a new or different kind of accident from any l accident previously evaluated. The proposed increase in differential i settlement will not place the service water lines in a condition that l
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will. compromise the structural integrity of the piping and therefore will'not. introduce'any new or.' unique operational' modes ar accident-precursors.
3.-. Involve'.a .sigtiificant=' reduction in th'e margin of safety because the resulting pipe stress, while increased, will still be .within the code.
allowable stress and therefore the margin of safety, required by the code is. maintained... '8' -
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