Corrected Tech Spec Pages to Amend 92 to License DPR-3 Re Main Coolant Sys,Eccs Subsystems & Vessel Fluence for Weld MetalML20199L752 |
Person / Time |
---|
Site: |
Yankee Rowe |
---|
Issue date: |
06/13/1986 |
---|
From: |
NRC |
---|
To: |
|
---|
Shared Package |
---|
ML20199L750 |
List: |
---|
References |
---|
NUDOCS 8607090600 |
Download: ML20199L752 (5) |
|
|
---|
Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217C1131999-10-0808 October 1999 Amend 153 to License DPR-3,revising TS Section 6.0, Administrative Controls,By Deleting TS Section 6.2.2.f, Which Contains Limits on Working Hours of Plant Staff ML20211J2971999-08-27027 August 1999 Amend 152 to License DPR-3,deleting License Condition 2.C(10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20207F9221999-03-0505 March 1999 Amend 151 to License DPR-3,revising Pol by Changing Submittal Interval for Radioactive Effluent Rept from Semiannual to Annual ML20203G2461999-02-12012 February 1999 Errata to Amend 150 Issued to License DPR-3.Index Page Corrected ML20202H5811999-02-0303 February 1999 Amend 150 to License DPR-3,revising Possession Only License Through Three Changes to TS ML20249A7891998-06-17017 June 1998 Amend 149 to License DPR-3,revising TS Sections Re Min Water Cover Over Spent Fuel,Crane Travel Over Spent Fuel & Related Bases ML20237F1591998-02-19019 February 1998 Amend 147 to License DPR-3,deleting Main Coolant Sys Water Chemistry Limits & Surveillance,Secondary Water Chemistry Monitoring Program & Requirements for Oxygen Monitoring of Waste Gas Holdup Sys ML20058C4011990-10-22022 October 1990 Amend 137 to License DPR-3,modifying Page 3/4 1-27, Surveillance Requirement 4.1.3.4.a,to Delete Ref to Control Rod Group a as Control Group ML20059M0561990-09-26026 September 1990 Corrected Pages to Amend 136 to License DPR-3 ML20059G2371990-09-0606 September 1990 Amend 135 to License DPR-3,modifying Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly & to Remove Min Required Discharge Pressures from Tech Spec ML20058L0281990-08-0202 August 1990 Amend 133 to License DPR-3,incorporating Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 ML20058L6611990-08-0202 August 1990 Amend 134 to License DPR-3,incorporating NRC Guidance in Generic Ltr 88-17 Into Facility Tech Specs & Adding Three New Tech Specs Specifying Plant Conditions & Equipment Operability Requirements to Prevent Core Uncovery ML20055C8581990-06-18018 June 1990 Amend 132 to License DPR-3,changing Title of Technical Svc Supervisor,Establishing New Positions Entitled Maint Support Supervisor & Operations Support Supervisor & Increasing Number of Senior Reactor Operators on Shift to Two ML20247F1231989-09-0707 September 1989 Amend 124 to License DPR-3,moving Onsite & Facility Organizational Charts from Section 6.0 of Tech Specs to Section 401 of FSAR ML20247E6681989-08-31031 August 1989 Amend 123 to License DPR-3,removing Description of High Pressurizer Water Level in Section 2 Re Bases of Tech Specs on Page B2-4 ML20195D6651988-11-0101 November 1988 Amend 120 to License DPR-3,enabling Piping Mods Needed to Allow for Installation of Water Cleanup Sys ML20205G1661988-10-25025 October 1988 Amend 119 to License DPR-3,permitting Increase in Nitrogen Pressure in Safety Injection Accumulator Tech Spec ML20204G4641988-10-17017 October 1988 Amend 118 to License DPR-3,revising Tech Specs Re Specific Values of Boron Concentration ML20205C3961988-10-14014 October 1988 Amend 117 to License DPR-3,changing Tech Specs by Adding Four Isolation Valves,In Two Spare Penetrations,To Table 3.6-1, Containment Barriers ML20207L6891988-10-12012 October 1988 Amend 116 to License DPR-3,permitting Mods to nonsafety-class Portions of Neutron Shield Tank Cavity Leakage Collection Piping ML20195C9941988-10-12012 October 1988 Corrected Page 2 to Amend 116 to License DPR-3 ML20207E8101988-08-0505 August 1988 Amend 115 to License DPR-03 Re Changes in Physical Security Plan ML20151M4861988-07-29029 July 1988 Amend 114 to License DPR-3,making Battery Charger Surveillance Requirements in Tech Specs Same for All Three Battery Chargers ML20151K3691988-07-25025 July 1988 Amend 113 to License DPR-3,revising Tech Specs to Permit Loads Greater than 900 Lbs to Travel Over Plant Fuel Pit to Enable Removal of Control Rods from Spent Fuel Pit ML20151K8531988-07-19019 July 1988 Amend 112 to License DPR-3,revising Shutdown Margin Switching Temp to 470 F & Correcting Typo & Inadvertent Omission of Previously Approved Surveillance Requirement ML20196K2471988-06-28028 June 1988 Amend 111 to License DPR-3,removing Requirement for Plant Operations Manager to Maintain Senior Reactor Operator License from Tech Specs ML20195K1401988-06-17017 June 1988 Amend 110 to License DPR-3,revising Tech Specs Re Control Rod Position Indication & Correcting Minor Error in Tech Specs ML20195C5111988-06-13013 June 1988 Amend 109 to License DPR-3,deleting Refs to Mode 5 in Tech Spec Tables 3.3-2 & 4.3-2 ML20155K5071988-06-0909 June 1988 Amend 108 to License DPR-3,changing OL Expiration Date from 971104 to 000709 ML20154J7621988-05-18018 May 1988 Amend 107 to License DPR-3,adding Surveillance Requirements to Tech Specs Re 480-volt Emergency Buses ML20216J4031987-06-26026 June 1987 Amend 106 to License DPR-3,modifying Tech Spec Requirements on Min Number of Operable Neutron Detector Thimbles for Cycle 19 Operation ML20213G9111987-05-13013 May 1987 Amend 105 to License DPR-3,revising Tech Spec Requirements for Surveillance Testing of Power Range & Intermediate Power Range Neutron Flux Channels ML20213D9511987-05-0707 May 1987 Amend 104 to License DPR-3,revising Tech Specs Re Reporting Requirements on Reportable Events & on Primary Coolant Iodine Spiking ML20211L3561987-02-17017 February 1987 Amend 103 to License DPR-3,revising Tech Specs Re Max Nominal Enrichment of Reload Fuel ML20207N8741987-01-0707 January 1987 Amend 102 to License DPR-3,modifying Tech Specs Re RCS Vent Sys by Allowing Power to Be Removed from Valves During Normal Plant Operations ML20207N4161987-01-0606 January 1987 Amend 101 to License DPR-3,changing Tech Specs to Increase Time Period That Valve CS-MOV-532 May Be Open from 30 Minutes/Wk to 120 Minutes/Wk ML20214X3321986-12-0101 December 1986 Amend 100 to License DPR-3,revising Tech Spec Requirements Re Min Number of Operable in-core Neutron Detector Thimbles for Remainder of Cycle Xviii Operation ML20210S1741986-09-23023 September 1986 Amend 99 to License DPR-3,modifying Portions of Radiological Effluent Tech Specs for Consistency W/Current NRC Guidance on Environ Monitoring ML20212M8441986-08-20020 August 1986 Amend 98 to License DPR-3,modifying Tech Specs Re Required Date for Submittal of Supplemental Dose Assessment & Meteorological Summary Info ML20215E2831986-07-11011 July 1986 Corrected Page to Tech Spec 3/4 6-11 Re Containment Barriers ML20199K4801986-06-27027 June 1986 Errata to Amend 95 to License DPR-3,correcting Tech Spec Page 3/4 3-18 Re Radiation Monitoring Instrumentation ML20206M7181986-06-17017 June 1986 Amend 97 to License DPR-3,modifying Tech Specs to Add Containment Isolation Valves for Containment Breathing Air Sys ML20199L7521986-06-13013 June 1986 Corrected Tech Spec Pages to Amend 92 to License DPR-3 Re Main Coolant Sys,Eccs Subsystems & Vessel Fluence for Weld Metal ML20199D5341986-06-0909 June 1986 Amend 96 to License DPR-3,modifying Tech Specs to Replace Manual Containment Isolation Valve W/Blank Flange ML20211G6791986-06-0505 June 1986 Amend 95 to License DPR-3,modifying Tech Specs to Add Containment high-range Radiation,Pressure & Water Level Monitors & Core Exit & Reactor Vessel Head Thermocouples to Required Instrumentation List ML20198S6371986-05-28028 May 1986 Amend 94 to License DPR-3,changing Tech Specs by Adding Containment Isolation Valves for Containment Breathing Air Sys ML20198C3361986-05-14014 May 1986 Amend 92 to License DPR-3,changing Tech Specs Re Safety Injection Tank Solution Temp,Steam Generator Blowdown Monitors,Containment Isolation Boundary,Eccs Surveillance & Reactor Vessel Fluence ML20141K3191986-01-15015 January 1986 Amend 91 to License DPR-3,deleting Tech Spec Requirements for Insp of Control Rod Shroud Tube Assemblies & Pressurizer Internals ML20136B7971985-12-16016 December 1985 Amend 90 to License DPR-3, Modifying Tech Specs to Define Limiting Conditions for Operation & Surveillance Requirements to Limit ECCS Leakage to 50 Gallons Per Day ML20137Z6131985-11-30030 November 1985 Amend 89 to License DPR-3,revising Tech Spec Surveillance Interval for Second Level (Degraded Grid Voltage) Undervoltage Protection 1999-08-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C1131999-10-0808 October 1999 Amend 153 to License DPR-3,revising TS Section 6.0, Administrative Controls,By Deleting TS Section 6.2.2.f, Which Contains Limits on Working Hours of Plant Staff ML20211J2971999-08-27027 August 1999 Amend 152 to License DPR-3,deleting License Condition 2.C(10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20206B9181999-04-23023 April 1999 Application for Amend to License DPR-3,requesting That Characterization of Revised Review & Audit Function Remain in Plant Defueled TS Rather than Being Transferred to Plant QA Plant ML20205M1391999-03-24024 March 1999 Application for Amend to License DPR-3,deleting Condition 2.C.(10) Re Ffd,From License.Condition No Longer Applies to Plant Since Plant Has Permanently Ceased Operation & Permanently Removed Fuel from Reactor Vessel ML20204D8681999-03-17017 March 1999 Application for Amend to License DPR-3,proposing Deletion of Overtime Restrictions Currently Incorporated in Ynps TSs ML20204E5511999-03-17017 March 1999 Application for Amend to License DPR-3,requesting Transfer of Adminstrative Requirements from Plant Defueled TS to Decommissioning QA Program ML20207F9221999-03-0505 March 1999 Amend 151 to License DPR-3,revising Pol by Changing Submittal Interval for Radioactive Effluent Rept from Semiannual to Annual ML20203G2461999-02-12012 February 1999 Errata to Amend 150 Issued to License DPR-3.Index Page Corrected ML20202H5811999-02-0303 February 1999 Amend 150 to License DPR-3,revising Possession Only License Through Three Changes to TS ML20155A2491998-10-15015 October 1998 Application for Amend to License DPR-3,changing Defueled TS 1.6,page 1-2 & 3/4.4,page 3/4-6 to Revise Title of Radioactive Effluent Release Rept from Semiannual to Annual ML20237E3571998-08-20020 August 1998 Application for Amend to License DPR-3,removing Definition of Site Boundary Contained in Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20249A7891998-06-17017 June 1998 Amend 149 to License DPR-3,revising TS Sections Re Min Water Cover Over Spent Fuel,Crane Travel Over Spent Fuel & Related Bases ML20237F1591998-02-19019 February 1998 Amend 147 to License DPR-3,deleting Main Coolant Sys Water Chemistry Limits & Surveillance,Secondary Water Chemistry Monitoring Program & Requirements for Oxygen Monitoring of Waste Gas Holdup Sys ML20197B0831997-12-18018 December 1997 Application for Amend to License DPR-3,to Approve License Termination Plan to Modify License to Incorporate New License Condition 2.C.11 as Listed ML20216E1721997-09-0505 September 1997 Application for Amend to License DPR-3,modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20059E4261993-10-28028 October 1993 Certificate of Compliance 9256,Rev 0,for Model Ynps SG Package ML20126E7461992-12-21021 December 1992 Application for Amend to License DPR-3,consisting of Proposed Change 259 to Modify Pages 3 & 4 of License & TS to Reflect Permanently Shutdown & Defueled Status.Page 3 of License Re Defueled Security Plan ML20058C4011990-10-22022 October 1990 Amend 137 to License DPR-3,modifying Page 3/4 1-27, Surveillance Requirement 4.1.3.4.a,to Delete Ref to Control Rod Group a as Control Group ML20059M0561990-09-26026 September 1990 Corrected Pages to Amend 136 to License DPR-3 ML20059G2371990-09-0606 September 1990 Amend 135 to License DPR-3,modifying Tech Spec Surveillance Requirement 4.5.2a to Change ECCS Pump Surveillance Frequency from Monthly to Quarterly & to Remove Min Required Discharge Pressures from Tech Spec ML20058L0281990-08-0202 August 1990 Amend 133 to License DPR-3,incorporating Wording from Std Westinghouse Tech Specs Into Util Limiting Condition for Operation Specs 3.10.3 & 3.10.4 ML20058L6611990-08-0202 August 1990 Amend 134 to License DPR-3,incorporating NRC Guidance in Generic Ltr 88-17 Into Facility Tech Specs & Adding Three New Tech Specs Specifying Plant Conditions & Equipment Operability Requirements to Prevent Core Uncovery ML20055D3991990-06-25025 June 1990 Application for Amend to License DPR-3,deleting Redundant Gallons Values for Safety Injection Tank (SIT) from Tech Specs & Revising Section 3/4.5.4 to Show That SIT Increased to 52,000 Gallons ML20055C8581990-06-18018 June 1990 Amend 132 to License DPR-3,changing Title of Technical Svc Supervisor,Establishing New Positions Entitled Maint Support Supervisor & Operations Support Supervisor & Increasing Number of Senior Reactor Operators on Shift to Two ML20247L3481989-09-14014 September 1989 Application for Amend to License DPR-3,eliminating cycle-specific Operating Limits from Tech Specs & Including Operating Limits in Core Operating Limits Rept,Per Generic Ltr 88-16 ML20247F1231989-09-0707 September 1989 Amend 124 to License DPR-3,moving Onsite & Facility Organizational Charts from Section 6.0 of Tech Specs to Section 401 of FSAR ML20246M0261989-08-31031 August 1989 Application for Amend to License DPR-3,revising Tech Specs to Incorporate Main Steam Line Monitors & Primary Vent Stack Noble Gas Monitor,Per NUREG-0737,Item II.F.1-1. Proposed Change Synopsis Encl ML20247E6681989-08-31031 August 1989 Amend 123 to License DPR-3,removing Description of High Pressurizer Water Level in Section 2 Re Bases of Tech Specs on Page B2-4 ML20247M5291989-07-24024 July 1989 Application for Amend to License DPR-3,modifying Tech Spec 3.2.4,Table 3.2-1 to Substitute Limit on Operating Loop Average Temp for Current Limit on Cold Leg Temp ML20246L9031989-07-12012 July 1989 Application for Amend to License DPR-3,modifying Tech Spec Page 3/4 3-19,Table 3.3-4 & Page 3/4 3-21,Table 4.3-3 to Incorporate Main Steam Line Monitors & Primary Vent Stack Noble Gas Monitor,Per NUREG-0737,Item II.F.1-1.Fee Paid ML20244D3801989-04-14014 April 1989 Application for Amend to License DPR-3,consisting of Proposed Change 209,changing Tech Specs Re Control Room Emergency Air Cleaning Sys.Change Proposed to Reflect Compliance W/Tmi Item III-D.3.4 ML20246P0721989-03-21021 March 1989 Application for Amend to License DPR-3,adding Snubber DRH-SNB-1 to Table 3.7-4 of Tech Spec 3.7.9 ML20195D6651988-11-0101 November 1988 Amend 120 to License DPR-3,enabling Piping Mods Needed to Allow for Installation of Water Cleanup Sys ML20205G1661988-10-25025 October 1988 Amend 119 to License DPR-3,permitting Increase in Nitrogen Pressure in Safety Injection Accumulator Tech Spec ML20205L1631988-10-21021 October 1988 Application for Amend to License DPR-3,removing High Pressurizer Water Level Trip Instrumentation from Tech Spec Tables 3.3-1,4.3-1 & Section 2 Bases & Modifying Description of Main Coolant Sys High Pressure.Fee Paid ML20204G4641988-10-17017 October 1988 Amend 118 to License DPR-3,revising Tech Specs Re Specific Values of Boron Concentration ML20205C3961988-10-14014 October 1988 Amend 117 to License DPR-3,changing Tech Specs by Adding Four Isolation Valves,In Two Spare Penetrations,To Table 3.6-1, Containment Barriers ML20195C9941988-10-12012 October 1988 Corrected Page 2 to Amend 116 to License DPR-3 ML20207L6891988-10-12012 October 1988 Amend 116 to License DPR-3,permitting Mods to nonsafety-class Portions of Neutron Shield Tank Cavity Leakage Collection Piping ML20151Z1751988-08-11011 August 1988 Application for Amend to License DPR-3,modifying Tech Specs to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement.Fee Paid ML20207E8101988-08-0505 August 1988 Amend 115 to License DPR-03 Re Changes in Physical Security Plan ML20151M4861988-07-29029 July 1988 Amend 114 to License DPR-3,making Battery Charger Surveillance Requirements in Tech Specs Same for All Three Battery Chargers ML20151K3691988-07-25025 July 1988 Amend 113 to License DPR-3,revising Tech Specs to Permit Loads Greater than 900 Lbs to Travel Over Plant Fuel Pit to Enable Removal of Control Rods from Spent Fuel Pit ML20151K8531988-07-19019 July 1988 Amend 112 to License DPR-3,revising Shutdown Margin Switching Temp to 470 F & Correcting Typo & Inadvertent Omission of Previously Approved Surveillance Requirement ML20196K2471988-06-28028 June 1988 Amend 111 to License DPR-3,removing Requirement for Plant Operations Manager to Maintain Senior Reactor Operator License from Tech Specs ML20196K1041988-06-27027 June 1988 Application for Amend to License DPR-3,adding Tech Spec Section C.2 Re Check Valves to Table 3.6-1,containing Check Valve WC-V-622 & Manual Isolation Valves WC-V-621,VD-V-1170 & VD-V-1171 to Section B.1 of Table 3.6-1.Fee Paid ML20196J2611988-06-27027 June 1988 Application for Amend to License DPR-3,increasing Nitrogen Supply Pressure to Safety Injection Accumulator from 473 to 488 Pounds Per Square Inch Gauge.Fee Paid ML20196K7281988-06-27027 June 1988 Application for Amend to License DPR-3,modifying Tech Spec Table 3.6.1, Containment Barriers to Delete Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, to Add Requirements for Level Switch.Fee Paid ML20150B0311988-06-27027 June 1988 Application for Amend to License DPR-3,changing Tech Specs to Allow for Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys.Fee Paid ML20195K1401988-06-17017 June 1988 Amend 110 to License DPR-3,revising Tech Specs Re Control Rod Position Indication & Correcting Minor Error in Tech Specs 1999-08-27
[Table view] |
Text
' MAIN COOLANT SYSTEM SAFETY VALVES - SHUTDOW LIMITING CCNDITICU FOR OPERATICN 3.4.2 At least the following safety and/or relief valves shall be OPERAELE;
- s. A minimum of one pressurizer code safety valve shall be OPERABLE with a lif t setting of 2485 psis +3%, -3% or 2560 psig
+3%, -3%.
- b. The Main Coolant System (MCS) pressuriser Power-Operated Relief Valve (PCRV) PR-50V-90 shall be OPERABLE in the low pressure made whenever MCS tas:peratuce is 13248F.
- c. Shutdown Cooling System (SCS) Safety Valves SV-204 and SV-205 shall be OPERA 3LE whenever MCS temperature is 1 3000F.
APPLICABILITY: MODES 4 and 5. ,
'~
ACTION:
~
- a. With no pressurizer code safety valve OPERABLE, insnedistely suspend ~
all operations involving positive reactivity changes and place the Shutdown Cooling System into operation.
%. b. With PR-50V-90 inoperable and MCS temperature between 3000F and 3248F:
~
- 1. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either;
- a. Raise the MCS temperature to > 3240 F, or
,b. Lower the MCS temperature to i 3000F and place the SCS safety valves into operation by:
- 1. opening SC-MOV-551, 552, 553, and 554; and
- 2. Verifying that the safety valves are lined up to discharse to either the Low Pressure Surge Tank (LPST) er the Primary Drain Collecting Tank (PDCT);
and
- 2. Restore PR-30V-90 to CPERABLE status within 7 days; or
- 3. Within the next S hours, depressurize and vent the MCS to the atmosphere, the LPST, or the PDCT.
3/4 4-5 Amendment so. If, 40, 85
. YArxxt-towE B607090600 860613 9 PDR ADOCK 0500 P
~
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS LIMITING CONDITION FOR OPERATION 3.5.2 The ECCS subsystems shall be OPERABLE with:
- a. Three OPERABLE independent ECCS safety injection subsystems with each subsystem comprised of:
- 1. One OPERABLE high pressure safety injection pump,
- 2. One OPERABLE low pressure safety injection pump, .
- 3. An OPERABLE flow path capable of taking suction from the safety injection tank on a safety injection signal.
- b. An OPERABLE ECCS recirculation subsystem with an OPERABLE flow l path capable of taking suction from the containment sump and recirculating to the safety injection header.
- c. An OPERABLE ECCS long term het leg injection subsystem with an OPERABLE flow path capable of taking suction from the ECCS safety injection subsystem and discharging to the Main Coolant System #4 hot leg.
APPLICAEILITY: MODES 1, 2, 3, 4* and 5* l ACTION!
- a. With one ECCS safety injection subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN with Main Coolant pressure < 1000 psig within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. In the event the ECCS is actuated and injects water into the Main Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.5 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The pro-visions of Specification 3.0.3 are not applicable.
' Main coolant pressure > 1000 psig.
I
, YANKEE-ROWE 3/45-3 Amendment No.52
' ,.s EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS 4.5.3.1* The ECCS subsystems shall be demonstrated OPERABLE per the ap- l plicable Surveillance Requirements of 4.5.2.
4.5.3.2 The above specified HPSI and LPSI pumps shall be verified to be inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever MCS temperature is
< 324'F by detemining that the associated pcwer supply breakers are open and locked in the racked-out position or are removed from the cubicle. ,'
4.5.3.3 The following valves shall be verified to be in the indicated positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever MCS temperature is
< 324*F, the reactor vessel head is bolted on and both pressurizer -
code safety valves are installed as'specified above.
Valve Number Valve Position
' CS-MOV-536 Closed CS-MOV-537 Closed J CS-MOV-538 Closed CS-MOV-539 Closed SI-MOV-22 Closed SI-MOV-23 Closed
~~
SI-MOV-24 Closed
~
SI-MOV-25 Closed CS-MOV-532 Open
" Main coolant pressure < 1000 psig but y_ 300 psig.
YANKEE-ROWE 3/4 5-11 Amendment No. 59 ,
1000 ap ny pp m..:q im sin r +a Tli r P.eius 1:r im IP en e; T F 1' :11g1, ;
.7 III) jjl im 3 piig en. ci.- F 11 ii 'li 'l r 1.' i +ii r E '!ri t : !; t iTT is 'i: i'7 i: ri e;' ': ; . i .o , t
!!+ '!;;
~
t 'h .i ! , 's ';: . i, i .
W ;'
Wih.cilii f .* t' ! -
-; 1
.p.. jtr
- ii
' =. l...- ,. l..-i iil.
- i:
.:;i i: .:
g .x i, .
gn
" g i,i. .i. .t ....-- . ii er
~
9ll ,ji ;p
' ip if 'i ,i !i j iU; jili - '. .jj :lH $ .. r j ;.l ((. jf I .:- 2 [; . j _
k- f@- -
- , v y '
j m 4
.- r
> o .ui ..
g .r rig-I5 2
tir ,ir..i :ili {i; ljii
- i
'.i- :!" !!/
il[ t 14 li .E 1 ..i hn is: .
r ;
i:
(
3 i.
n!- .
T - -
m @!!p ' ' "
N, h ap n 4:i t J ___{
u y3.d'[Pg;,,f'" f ip' Y ir ,
li- ll g F:
!i,- :. g ;ia ! ll .
-! J1 . _g, "C ;i-. i I! i i i r
'T'Tt
.o
,.ma- ,r!
,c : -
j' 'l : je i .!
,,v ' ..;s il' IIT~ n:: i.
iil
[l- .1 ill
.. . ; l.,i l[r r Il'; ; 18 ;! . . : ll '
i is
.. t -[ 1..
8 i.l "8.) -
l- .
t.l' c s e d t'j8j -
"p
- %:' r .so 1- - 3r res
-t L.
- ts - sw ..i' -rm i .t- 1'+- * -
j9 (:[, .. r
.g , .
FI 3 ?'p ~
i
- i. g_ -, . . i. i i, 'r.; ;;i- 2'-
li i - -
.e
- ., t ,l ;t:i i.- ::gl}
- ,.y;
- i , gl ". .r . ,
- l l pi :! . .;;I I.l i. jl .. 6... .-- ,
'l f '
d,,,.a.y i.
A 'l
' ~
j
- i,i I; 3 ESTIMATED WEl.D DATA i ; .
l i"!;
I: i 4 .t ;
g;- : : l' ..
T;, I Fil , l~:l!ll 11:. lI t
l'll-l p... l, q 1 le g3:-
i g
u J!.i p,, '.j ,,. . _ _
, _rs ,e p 7,- (f,q .
4 F j Dr 4?. .4 g -
,J '
,g.. j -- lj ij u.e;' 1
[l..
> >; i 14 l, Mr,p,.
1:
o , -
c.
i I ue
- i..
i 1 ; -
g i- -5 t
M 9tf z ,1, . i. g :. .- 3 ... .
o 4 4 a I til s 0 26. v. .
ip;. g.j i t
,,,t 0!
e 1 I.ltleill l
z 1
n
. .o .
1 .a .ti .
y m ... y a
- . +
o p i : .; r .; ;; , .
i, 7dA -
-M .. -
p' v- !' l's Ii ..,**" :> n
!% :;;,,gg' . ,1 li !!i ;ni te .
a l:
gl_,
i.s
- 1!i : !- Ir .. ji ss. 3 !
.i41: 1E.i n!i lii>C;; i, i;i
- 1 D "T; d!: ill- tiii !il [ 11 i lf 3
I! til:
i'K;ir,[!.
' -1. .
= g ::: M oi ::: -
l ;. ,," .: j n I:- r .? ..:r: S l ': . .
4 -
i :
- . ;,.. H: ilj ;..1
- s;
- lj; *" b ii !:i ;i. l w
.:- . . . . .. "E;i liP I
. it I
us i;; :r. .u s' 1 :1, i'
i .8 . ; ! l , i. Ja 1..
.i .
g i a '
- lp is.
.l,, t.
r .j r. g
.'lljl, i
F, . ::' ij:i ji tl eia ' 1 i i- g .{ [-
.:. ,1 [,il,[i .n :- :r a i{.
- .j ' 'l li, .I f$..
.i. .s j., Al. !;l. i;h "- gj9 .e :i;: m: ;[. r : sil g. .i, in; .h r. .
.11 .f _ . 1
- - - ;.. l; i it ,,
L'Ni El b h h [N' D O '.),O !d! , :- 'L *" 2
' I d M l' . 5" d :-
i M i!' .
lili !!!,
M '8 p l' l i r !.
- ' . el-; illi +l' f p r Irl 8 ij; 'li 3 iF !!; 'l i -
'.4i l ll? i:
u, i! --II -pl. I l ;'
d y-
- t-
- -I. .- 1
- ;..._.M{ [it' '.j:i L i
-c: : ,.
lij
?
1: j [I .:c :e!. 'c.3-.. -
.s.
r:e .- k. ..._i.
t . :i
[! :
l- ,;. i _-_._._ ._ :
.-}m . 1li.. : .n.
,n .l .1 -
1 j'1 .,g. ' I L ' '
-lly'j lif fc :'-{
.t.
l Il '
' !' d. 'E --
l}t ':l.
" I l l i,,. 3 ~I8 lil l'I i
" i
- '8 !i! y. t
- :';i,i 3:- .
- i E ,-
p u [ :t i l l!
I4r'- l.iM c ii . . .
y T;4. Tii i;i; ;q,y ;} jl r [;[
.g ; ; i ;-
,j j- r;. i :. &
igr : ! ,,ji ;;,, .e .,
.g.r,;.' jp' ;;
~
.. .l;: :-
!p m !,j;;i ;n:,, m p -
ia ..i, .
s.:
- 'I:- .: ik,!2 i i n .ii . :: ,
i uit '
4
- ln?
f;' 1.Ne . 'jil} .
..i ;- '"
7 i
l.- ,r :l .i .i -
- 4. . -r t -
Ii t !i . q 's; '- r.
r .
li. j ! :jl
~j ..l : H. '1 ;; l l 1 i ?! i
!' !!1 I E .
ll ibjll fi! lii!T ii 'l i:;mi! 4
- ip;;Ot"d
- i h[ lll ul[!I l', ti Hi' .liilil at Jdia -
ll1 I i i l l l i 10 20 10 18 10 18 10 10 17 FLUENCE > 1 MEV (n/cm 2g SHIFT IN RT NDT AS A FUNCTION OF VESSEL FLUENCE FOR WELD METAL,1/4t AND 3/4t ,
i BASES FIGURE B3/4 4-2
i 3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMULATOR The OPERABIL*ITY of the accumulator ensures that a sufficient volume of barated water will be immediately forced into the reactor core through each of the cold legs in the event the Main Coolant System pressure falls below the pressure of the accumulator. This initial surge of water into the core provides the initial cooling mechanism during large Main Coolant System pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the acci ,
dent analysis are met. A minimum useable water volume of 700 cubic feet require accumulator water volume to be at least 850 cubic feet. -
The limits for operation with the accumulator inoperable for any reason l except an isolation valve closed or pressurization system inoperable minimizes the time exposure of the plant to a LOCA event occurring concurrently. which may result in unacceptable peak cladding tempera-tures. If a closed isolation valve cannot be immediately opened, the
(_. full capability of the accumulator is not available and prompt action is L' required to place the reactor in a MDDE where this capability is not required.
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS
~
The OPERABILITY of three independent ECCS safety injection subsystems, the recirculation subsystem, and the long term hot leg injection sub-system ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one safety in-jection subsystem. Two safety injection subsystems operating in con- l Junction with the accumulator are capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest Main Coolant System cold leg pipe downward. In addition, the safety injection subsystems, the recirculation subsystem and the long term hot leg injection subsystem provide long term core cooling and baron mixing capability during the accident recovery period.
1 l
I YANKEE-ROWE B 3/4 5-1 Amendment No. #3, 52 W-
- - - - - - - - , - , - - - - -. ..--g,. - - - , - - - - _ . - , - - - - - - - - - - , , - - - - - ,