Proposed Tech Specs,Clarifying LCO by Indicating in Section 3.7.1.3, Demineralized Water Storage Tank That Total Vol of 334,000 Gallons Consists of Usable & Unusable Vol in TankML20083R037 |
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Millstone ![Dominion icon.png](/w/images/b/b0/Dominion_icon.png) |
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Issue date: |
05/19/1995 |
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From: |
NORTHEAST NUCLEAR ENERGY CO. |
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Shared Package |
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ML20083R035 |
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References |
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NUDOCS 9505260322 |
Download: ML20083R037 (8) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F ML20154A3701998-09-28028 September 1998 Proposed Tech Specs Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1, 3.6.5.1,3.7.6.1 & 3.9.15,revising Info Re Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA ML20154C0491998-09-28028 September 1998 Proposed Tech Specs Revising FSAR Separation Requirement of Six Inches Which Is Applied to Redundant Vital Cables, Internal Wiring of Redundant Vital Circuits & Associated Devices ML20151V5011998-09-0909 September 1998 Proposed Tech Spec Changing TS Definitions 1.24,1.27,1.31, 3.0.2,4.0.5,3.2.3,3.3.2.1,3.4.1.1,3.4.11 & Adding TS 3.0.6 B17385, Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified1998-08-12012 August 1998 Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified B17341, Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval1998-08-0606 August 1998 Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval ML20236Y0831998-08-0404 August 1998 Proposed Tech Specs Changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atmospheric Steam Dump Valves ML20236X2521998-07-30030 July 1998 Proposed Tech Specs Bases 3/4.9.1,3/4.1.1.3,3/4.7.1.6, 3/4.7.7,3/4.5.4 & 3/4.3.3.10,resolving Miscellaneous Condition Repts ML20236W0201998-07-30030 July 1998 Proposed Tech Specs Bases Section 3/4.6.1.1,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling ML20236T2681998-07-21021 July 1998 Proposed Tech Specs Re Reactor Protection & ESFs Trip Setpoints ML20236T5301998-07-17017 July 1998 Proposed Tech Specs Pages for TS Bases Section 3/4.4.9, Pressure/Temperature Limits ML20236T7331998-07-17017 July 1998 Proposed Tech Specs Modifying DG Testing Requirements ML20249A2811998-06-10010 June 1998 Proposed Tech Specs Re Post Accident Access to Vital Areas (Plar 3-98-6) ML20249A3121998-06-0606 June 1998 Proposed Tech Specs Re SLCRS Bypass Leakage (Plar 3-98-5) ML20249A2681998-06-0505 June 1998 Proposed Tech Specs Re Revised Steam Generator Tube Rupture Analysis (Plar 3-98-4) ML20248M2221998-06-0404 June 1998 Revised Tech Specs Pages,Changing TS Bases Section 3/4.7.1.5 to Reword Section Which Describes Limiting Temperature Case for Containment Analysis ML20247G6841998-05-14014 May 1998 Proposed Tech Specs,Modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time B17211, Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage1998-05-0707 May 1998 Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage ML20247B9411998-05-0101 May 1998 TS Change Pages for TS Bases Section 3/4.5.4,modifying Wording Associated W/Refueling Water Storage Tank Minimum Boron Concentration ML20217D5941998-04-30030 April 1998 Proposed Tech Specs Re Change to Basis 3/4.6.4 Which Modifies Accuracy Range Associated W/Measured Std Cubic Feet Per Minute & Corrects Listed Component Number ML20217N9441998-04-29029 April 1998 Proposed Tech Specs Replacing Two low-range Pressurizer Pressure transmitters,PT-103 & PT-103-1,which Will Identify That Two low-range Pressurizer Pressure Instrument Channels Are Independent & Redundant Only 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
[Table view] |
Text
Docket No. 50-423 )
B15146 ,
1 l
l n
Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Domineralized Water Storage Tank Marked Up Pages May 1995 9505260322 950519 PDR ADOCK 05000423 l p PDR
. 1
.~
.- PLANT SYSTEMS '
JAN 31 1986 DEMINERALIZED WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.-l.3 The domineralized water storage tank (DWSI) shall be OPERABLE with a contained water volume of at least 334,000 gallonfof water.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With the DWST inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. Restore the DWST to OPERABLE status or be in at least HOT STAND 8Y ,
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 HOT SHUTDOWN within the following !
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or !
- b. Demonstrate the OPERABILITY of the condensate storage tank (CST) as a ;
backup supply to the auxiliary feedwater pumps and restore the DWST ;
to OPERABLE status within 7 days or be in at least HOT STANOBY 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS !
4.7.1.3.1 The DWST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by :
verifying t.he contained water volume is within its limits when the tank is the ,
supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> bv verifying'that the combined volume of both the DWST and C CST is at least 634.00D3 gallons of water whenever the condensate storage tank and DWST are the supply source for the auxiliary feedwater pumps.
3%H , 00 0 '
f 5
N e i
MILLSTONE - UNIT 3 3/4 7-6 ,
63/f
=
. PLANT SYSTEMS JAN 311986 BASES . . -
SAFETY VALVES (Continued) .
109 = Power Range Neutron Flux-High Trip Setpoint for four loop r operation, t
80 = Maximum percent of RATED THERMAL POWER permissible by i P-8 Setpoint for three loop operation, '
X = Total relieving capacity of all safety valves per steam '
line in 1bs/ hour, and Y = Maximum relieving capacity of any one safety valve in !
lbs/ hour 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM l
I
. The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating or j
accident conditions coincident with a total loss-of-offsite power.
The auxiliary feedwater system is capable of delivering a total feedwater l flow of 480 gpa at a pressure of 1236 psia to the entrance of at least three ;
steam generators while allowing for (1) any spillage through the design worst-case break of the Normal feedwater line, (2) the design worst-case single fail- i ure; and (3) recirculation flow. This capacity is sufficient to ensure that '
adequate feedwater flow is available to remove decay heat and reduce the Reactor ;
Coolant System temperature to less than 350*F at which point the Residual Heat ~
Removal mAy cowem os System may be placed into operation.T e w m rssov4me. w m l ro ope 4 Arc W fA S A aEL. u m* vc em ww -
stemosA w srce rott. c o'c==.s a ,sewov a so* y, i 3/4.7.1.3 DEMINERALIZED WATER STORAGE TANK The OPERABILITY 3 the domineralized water storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offsite power, and with an additional 6-hour cooldown period to reduce reactor coolant temperature to 350*F. The contained water discharge volume linelimit includes location an allowance or other for water not usable because of tank )
physical characteristics.
k j[ m i 3/4.7.1.4 SPECIFIC ACTIVITY e
The limitations on Secondary Coolant System specific activity ensure that-the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture.
This dose also includes the effects of a coincident 1 gpa primary-to-secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses. .'
4 MILLSTONE - UNIT 3 B 3/4 7-2 03M
Insert 'A' to Page B 3/4 7-2 The OPERABILITY of the demineralized water storage tank and the volumetric requirements are based upon Safety Grade Cold Shutdown (SGCS). The water volume that is required ensures that sufficient water is available to maintain the RCS at HOT STANDBY condition for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offsite power, and with an additional 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> cooldown period to reduce the reactor coolant temperature to 350*F when RHR is introduced, and for the cooldown below 350*F when steaming continues in *
)arallel with the RHR operation for approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> until the entire leat load can be cooled by RHR. The contained water volume limit of 334,000 gallons in the DWST includes an allowance for water not usable because of the tank discharge line location, or other physical characteristics of the tank and an allowance for 30 minutes of spillage from the tank.
When combining the volume of the condensate storage tank (CST) with the DWST, an unusable CST volume of 30,000 gallons must be included. Thus the combined volume of both the CST and the DWST must be at least 364,000 gallons to satisfy the requirements of Section 4.7.1.3.2 of the Technical Specification.
1
)
. I Docket No. 50-423 B15146 i
I Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Domineralized Water Storage Tank Retyped Pages f
t i
May 1995
. PLANT SYSTEMS :
DENINERALIZED WATER STORAGE TALK LIMITING C0lWITION FOR OPERATION 3.7.1.3 The domineralized water storage tank (DWST) shall be OPERABLE with a contained water volume of at least 334,000 gallons
- of water. l APPLICABILITY: NODES 1, 2, and 3.
ACTION:
With the DWST inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
, a. Restore the DWST to OPERABLE status or be in at least HOT STANDBY 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or
- b. Demonstrate the OPERABILITY of the condensate storage tank (CST) as a backup supply to the auxiliary feedwater pumps and restore the DWST to OPERABLE status within 7 days or be in at least HOT STANDBY 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The DWST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volume is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The condensate storage tank shall be demonstrated OPERABLE av least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the combined volume of both the DWST and CST is at least 364,000 gallons of water whenever the condensate storage tank l and DWST are the supply source for the auxiliary feedwater pumps. ;
I
,
- Includes unusable volume. l l l
NILLSTONE - UNIT 3 3/4 7-6 Amendment No.
0310 i
PLANT SYSTEMS RASES SAFETY VALVES (Continued) 109 = Power Range Neutron Flux-High Trip Setpoint for four loop operation, 80 - Maximum percent of RATED THERMAL POWER permissible by P-8 Setpoint for three loop operation, X - Total relieving capacity of all safety valves per steam line in 1bs/ hour, and ;
Y - Maximum relieving capacity of any one safety valve in 1bs/ hour 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM i The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating or accident conditions coincident with a total loss-of-offsite power.
The auxiliary feedwater system is capable of delivering a total feedwater flow of 480 gpm at a pressure of 1236 psia to the entrance of'at least three steam generators while allowing for (1) any spillage through the design worst-
, case break of the Normal feedwater line, (2) the design worst-case single fail- .
ure; and (3) recirculation flow. This capacity is sufficient to ensure that I adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350'F at which point the Residual Heat Removal System may be placed into operation. The auxiliary feedwater system may
!. continue to operate in parallel with the residual heat removal system for cooldown below 350*F.
3/4.7.1.3 DEMINERALIZED WATER STORAGE TANK The OPERABILITY of the demineralized water storage tank and the volumetric requirements are based upon Safety Grade Cold Shutdown (SGCS). The water volume
, that is required ensures that sufficient water is available to maintain the RCS at HOT STANDBY condition for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offdte power, and with an additional 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> cooldown period to reduce the reactor coolant temperature to 350*F when RHR is introduced, and for the cooldown below 350*F when steaming continues in parallel i with the RHR operation for approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> until the entire heat load can i be cooled by RHR. The contained water volume limit of 334,000 gallons in the DWST includes an allowance for water nc,t usable because of the tank discharge i line location, or other physical characteristics of the tank and an allowance for 30 minutes of spillage from the tank.
When combining the volume of the condensate storage tank (CST) with the DWST, an unusable CST volume of 30,000 gallons must be included. Thus the combined volume of both the CST and the DWST must be at least 364,000 gallons to satisfy the requirements of Section 4.7.1.3.2 of the Technical Specification. I
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MILLSTONE - UNIT 3 8 3/4 7-2 Amendment No.
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. PLANT SYSTEMS BASES 3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture.
This dose also includes the effects of a coincident 1 gpm primary-to-secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.
MILLSTONE - UNIT 3 B 3/4 7-2a Amendment No.
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