Revised Proposed Tech Specs Re Power Distribution Limits,Esf Instrumentation,Esf Actuation,Msivs & Radiation/Accident Monitoring InstrumentationML19327B098 |
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Millstone ![Dominion icon.png](/w/images/b/b0/Dominion_icon.png) |
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Issue date: |
10/16/1989 |
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From: |
NORTHEAST NUCLEAR ENERGY CO. |
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Shared Package |
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ML19327B097 |
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References |
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NUDOCS 8910250194 |
Download: ML19327B098 (12) |
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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] |
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< MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION l .
'3.7.1.5 Each main: steam line isolation valve (MSIV) shall be OPERABLE.
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APPLICABILITY: MODE 3 1, 2, 3, and 4.
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ACTION: i L
MODE l:
u .,.. With one- MSIV inoperable but open, POWER. OPERATION may continue ;
l provided the inoperable valve is restored- to OPERABLE status within 1
! 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise be in 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 'i L 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 />. ;
l MODES 2, 3, and 4: )
.L With one' MSIV inoperable, subsequent operation in MODE 2 or 3 or 4 may L' proceed provided the isolation valve is maintained closed. Otherwise, be L in 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 COLD SHUTDOWN within the ,
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. !
SURVEILLANCE' REQUIREMENTS I
- 1 4.7.1.5.1 Each'MSIV shall be demonstrated OPERABLE by. verifying full closure
!. within 5 seconds in Modes 1, 2, and 3 when tested pursuant to Specification 4.0.5. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3. l
, . 4.7.1.5.2 Each MSIV shall be demonstrated OPERABLE by verifying full closure-L~
within 120 seconds in Mode 4 when tested purs.uant to Specification 4.0.5. The I provisions of Specification 4.0.4 are not appl.icable for entry into Mode 3. I s
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N WBSYINWOUSS PROPRIETARY C: ASS 3 Radial Peaking Faster Limit Report Four 1 mop Operation his Radial Peaking Faster Limit Report is provided in asserdance with Paragraph 6.9.1.6 of the Millstens Unit 3 puoloar Plant Toshnical specifiestions.
The four loop operation F limits for RATED THERNAL POUIR within 9
speettic core planse for Cyele 3 shall bei 1, . F"",7 less than or equal to 1.'/9 for all more planes containing Bank "D" oentrol rods, and
- 2. F" less than or equal to 1,67 for all unrodded more planes, Thess'F ,(s) limits were used to confirm that the heat fium het 4 ciaannel fastet F g (s) will be limited to the Toshnical Specification values of:
j F(s)$if][K(s))forP>0.5and, q
Fq (s) 5 l' 641 IK(s)) for Ps o,5 l
assuming that most limiting axial power distributions expected to '
result from the insertion and removal of Control Banks 8, C and D during operation, including the secompanying variations in the axial manon and power distributions as described in the " Power Distribution j
Control and Imad Fellowing Procedures". WCAP 8403, Septeabet,1974.
Therefore, these F , limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ICCS aseeptanas criteria of 10CFR50.46, see Figure 1 for a plot of [Fq T,P ] versus Axial Core Height.
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Three 14ep operation
This Radial Peaking Faster Limit Report is provided in assordamse with' l Paragraph .6.9.1.6 of the Milletone Unit 3 Nuelear Plant Teeknisal :
spoeifications. .
The three loop operation F,7 limits for 656~of RATED THERMAL 70 m within specific sore planes for Cycle 3 shall be:
F 65 RTF less than er equal to 1.64 for all eers planes
- 1. i eentaining tank 'D' eentrol reds, and 65 RTP less than et equal to 1.53 for all unredded eers
- 2. F planes.
- 3. In the reistionship for F,,L the sultiplier M7,7 is equal to A
. 0.312.
I These Fg (s) limits were used to confirm that the heat flux het ehannel factor F q (s) will be limited to the Technical Specification
" values of Fg (s) $ (f) (K(s)) for 0.65 g F > 0.325 and, p
F9(s) $ 15.20] (K(s)) for P s 0.325 i l
assuming that most limiting axial power distributions expected to ;
result from the insertion and removal of control Banks 5, C and D during operation, including the aceospanying variations in the axial L ,
zonen and power distributions as described in the " Power Distribution I Control and Imad Fe11 ewing Procedures', WCJL* 8403, September,1974 l
limits provide assurance that the initial Therefore, these F,7 l eenditions assumed in the thCA analysis are met, sleng with the ECCS t acceptance eriteria of 10CFR50.46. l l
see Figure 2 for a plot of (F . Pg,g) versus Axial Core Height, l
. \
.. ,,_,.1 . . . . . . . , , .- . _ n 1um
3; I WESTrnonobst FRCPRIETARY CLAtt 3 i
! ~ '.- ,
t i is <
e- '1
.< J 1
2.00
\ ~
f.75 0.0. 1.41 0 6.0 1.8to r- ,
~~~"~~~" iti.8, 1.589J ;
y1
~ ~ ~
- - -.-__ _ _ _ h %
- 99 s
~
l 4 mml
,* 4 :
a
@ .. +++ .
++- t p*" + ,F i
+ *
+++ .+++++ r i,
' +
4 4
' i' 7 4a L' .
i .
v -
' i
! x
4 2
1.00 '
12.CI . 0.975
' i 1 '
t f[
l
.750 I i
l
.500 6 10 12 2 4 6 0
COREHEIGHT(FEET)
FIGURE 2 1
MAXIMUM FqT
- PggL VERSUS AXIAL CORE HEIGHT DURING WORMAL CORE 3 LOOP OPERATION r
i
___ e u ,__o_ _ _ _ __.___ _ ___ _ _ ___ _ _, , , , , ,,
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. . . . .. p . 3 . .. 7.. .
p.. ,,
.. ;O . . -
7- .p . , i W38T1313I0085 PROPIL18tARY c1As8 3 y Ii ,
T 0; ,
I ll u 3 s .
5
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ATTAcilNEllT 1 Suggested Revision to Toshnical Specification 4.1.1.2.2.s and navised Three 14ep Radial Peaking Factor Limit Report 5
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6
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__7 t
sy,:
JAN al 1966
, MbER DISTRIBUTION LIMIT 8 )
^ ' '
suRyt!Lumet 'meau!RMNTS -
.4.2.3.2.1 The previsions of Specification 4.0.4 are not applicable.
['
l>, 4.t.8.2.8 F, shall be evaluated to determine if gF (Z) is within its limit by: l
- e. Using'the' movable incere detectors to obtain a power distribution esp at any THERMAL POWER greater than 5 of RATED THEWL POWER, .
- b. Increasing the measured F, component of the. power distribution map by 5 to account for manufacturing tolerances and further increasing the value by N to account for seasurement uncertainties, 0
- c. Comparing the F temputed(F9)obtainedinSpecification 4.2.2.2.26 o
above to: Y
- 1) The F limits for G N of Raft 0 THERMAL POWER (F $ RTP) for the i
, 9 appropriate measured core planes given in Specification 4.2.2.2.te, l and f., below, and
- 2) The relationship L '
8 Fy=F'f887P(1*p ([P)),
V I i
Where F,' is the limit for fractional THERMAL POWER operation 0 65'RTP expressed as a function of F ,My is the F , multiplier, andPisthefractionofRATEDTHERMALPkRatwhichF W was measured.
- d. Remeasuring F, according to the following schedule:
- 1) When F isgreaterthantheFh65RTPlimit for the appropriate esasured core plane but less than the F relationship, additional l
- c 0 power distribution maps shall be taken and F,y compared to F andr;either
's) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 205 of RATED THERMAL POWER er greater, the THERMAL POWER at was last F *C which deterwined, or b) At least once per 31 Effective Full Power Days (EFPD),
whichever occurs first.
3/4 2-12 007075 MILLSTONE - UNIT 3
___m___ _ _ _ _ _ _ _ _ _ _ _ _
__ <._-__._,__o.._._.z. m
- '* , g- '
WRITINB10 DOE PRORIETARY CIASS 3 s . .
Radial Feeking Footer Limit. Report Three 14ep Operation I
- , ;
- This Radial' Peaking Faster Limit Report is provided in asserdance with Paragraph 6.9.1.6 of the Millstone Unit 3 Nualear'Flant Tsehnical r Spesifications.
The three loop operation F limits for 65% of RATED THERNAL P0irER ;
within specifie sore planss for cyste 3 shall bei-
- 1. F 65 RU loss than er equal to 1.81 for all eere planes sentaining Bank "D" control rods, and :
- 2. F 65 RU less than or equal to 1,69 for all unrodded oore !
- Planes. ;
- 3. In the relationship for F I' the multiplier is equal to 0.281. t L'
1 These Fm (s) limits were used to confirm that the heat flux hot channel factor Fg (s) will be limited to the Technical Specification l
values of:
Fq (s) 3 [ ] [K(s)) for 0.45 g P > 0.325 and, !
i Fq (s) 5 (S.20) (K(s)) for P $ 0,325 assuming that most limiting axial power distributions expected to i result from the insertion and removal of control Banks 5, C and D during operation, including the accompanying variations in the axial zonen and power distributions as described in the " Power Distribution Centrol and Lead Fellowing Frecedures", WCAP 8403, September, 1974 Therefore, these F limits provide assurance that the initial senditions assumed in the IDCA analysis are not, along with the Ecc5 aseeptance criteria of 10CFR50.46. .
See Figure 2 for a plot of [F .Phl) versus Axial Core Height.
W _-.-___ m .wa _ _ll _teL_G_c= s ' as t e Q_9EAM ** .** - '*? ?"*-
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x +
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i *
.g
' Docket No. 50-423 d'O '
B13343
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Attachment 3 L.,.
Millstone Nuclear Power Station,. Unit No.' 3
'/, ' L Examples of Fxy.Using the Current and' Proposed Relationships J
f 1
i::
s, i t
f'
'l, a
t.'
October 1989 e
g,' $
(
5 Y
g L
~
i U.S. Nuclear Regulatory Commission
'B13343/ Attachment 3/Page 1 ,
l0ctober 16, 1989 Millstone Nuclear Power Station, Unit No. 3 Examples of F L using the xy ,
Current and Proposed Relationshios n
Current Proposed
.fhy-1.53[1'+.312(1- P)] Unrodded Fhy-1.69[1+.281(.65- P)] Unrodded
L
.65 xy - 1.69 Fhy-1.69 P F 3, P = .5 Fhy-1.76 Fhy-1.76
'l I' (
l F
xy
- 1,64.[1 + .312.(1 - P)] Rodded Fhy-1.81{1+.281(.65- P)] Rodded L
'P .65 F xy - 1.81 Fhy-1.81 o
L P = . 5. Fhy-1.89 F xy - 1.89
<1 Additional surveillance' required when Additional surveillance required when f,. Fhy is between 1.53/1.64 and the limit. Fhy is between 1.69/1.81 and the limit, y
le.
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I l
L I l 1 E j