|
---|
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
. .- _ . - _ _ _ . _ , -. . _ - .
i i ,
i l
Docket No. 50-336 B14924 ,
Attachment 1 I Millstone Nuclear Power Station, Unit No. 2 1
Proposed Revision to Technical Specifications Generic Letter 90-06 Marked Up Pages !
i l
t t
l l
l l i l l I I l
i l September 1994 D OS 94o973 p
fDOCK0500o336 PDR
( ;
i 4 February 26, 1991 I
' REACTOR C00tlNT SYSTEM RELIEF VALVES i
LIMITING CONDITION FOR OPERATION S
3.4.3 %oTH valves shall be OPEPABLE. power operated relief valves (PORVs) and their associated block :
APPLICABILITY: MODES 1, 2, and 3. !
pf 1 '
ACTION: !
)
C t. With ;bo4hr.c o ~.c Awo W C-@^M o' EtisA Wouw c rcoco ed t, d e c the PQRV M. to OPERABLE inoperable ^ withinlK hourX either restore PORV(s) valveMl[ and remove power status from or theclose blockthe associated valved Other idg block
,abe 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 COLO C':UT006, within the following )6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Nur snurhV ,
6 d.4. With one or *b.A ere block valve (s) inoperable, withinla' hourX citScr restore
.;i.m(.;; .d .ve~,e valve (s) to OPERABLE statust;c cl m the L; a the block rm T. v... 1l. Liv a vol,s(a ; otherwise, 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 /> an)d in COLO S;;UTOOWN
- within the following M hours. WT 3NTDr*M G
SURVEILLANCE REOUIREMENTS la Act4hou Tu Tue Iteweec.c.cr5 c., weC.sFac AYi40 9.Q.%
4.4.3.1 vfach PORV shall be demonstrated OPERABLE:
a.
Once excluding per valve 31 days by performance operation, and of a CHANNEL FUNCTIONAL TEST, l
b.
- c. Once 9=*.
owe per 18 months by performance of a CHANNEL CALIBRATION.
to wow s Tw pows 36it h hed+<ht i 4.4.3.2 operating Each block valve shall be demonstrated OPERABLE once per 92 !
the valve through one complete cycle of full travel.
c
[
demonstration is not required u > PDFV hinck valve This '
removed to m et Specifi tinn s closei and power l
ov- PL*ZE sts A550c.t ATr.b FC5VN ccMv=h 5M U* . b1Totitt af LeasT 04h.ccx- vAs ve to OT'ETtA3UE waM iaimic w wm m its som tka.lc vawes i Ait6 14 0Pt:1tADtM re1 torts AM( REN AWlb8 W GPCItA44( &.uc.Ic d A VI TO O M NA A C wAtus i.at wo *)L hourM _
~
e, ne pnovistows c# SDec IPtc.Aw 10.9 p re war' Ap>Lic.AOLs*
MILLSTONE - UNIT 2 3/4 4-3 Amendment No. /E, EE, EE,151
- s l
, s.
4 .
iIoas.wr 1 i
i,
! I
! A. WiM om cA 13o1% PORVs twoPERABl4 AW CAPAE60F BetM s
kA @ CYCLE D , Wgyngd l HovR,' ElfMER. R63TcRd 4
m _ ,e _, - ~,~, . . ~ , - .
4
~
OTHER.Qtis . Bs 14 AT' LEA 3T-HOT ,STAN@ WLTht@ 1ME ot<T' j 6 44caAts Am so ROT MK3TM catTwic TWr Fou.a.)<b6 l
i b. Wau o.* %E\/ idoper Aace Ae c40aBL4' GS EctK 94oeu.f i
J C 4 ct.c D , w,7s: 4 ( $4ooit. EtrNcR. ?d57en( yng 76R/
"fD @EMD 3T's4TL/1 oR. C.L,o36 174 A33ccid7ED Stock. UALOi f
1 AW TE440 VIE PCd.JER. FROM THIE BL,0ck. VALA)f i ?.t11 ORE THf I
w cesEAIR4 swnus eemiu twe FotwWW6 7Z. Hour $ OR. RE" / AJ i
) b STAQDRY wtws4 TMF OtxY C hours Awo in hot SHM
! WITkt0 THE Fowool6% 6 hovra.
I
- i i l l i i
l j
- b. .
i i
l d
i*
1
~-
l .~
i -
j February 26, 1991
} .
l . e < I
{;. RfACTOR COOLANT SY$ TEM I DVERPRESSURE PROTECTION SYSTEMS 1
l LIMITING CONDITION F0't OPERATION 3.4.9.3 j
.i..jw. shall
- . . . . . . . . . . . . ............,....y....... y...u....
j beOPERAEl.y k [
]
l Q gust .,K C Whower 4 3J4 psigr-ee-operated relief valves (PORVskwith a lift setting of less 4 Lad or
~
-D . '.. r;;;t;r 00;l;r.1 ;Jeti; .ust .7 g. a. .gues s u m.s rc a .
1 APPLICABILITY: it;; th; t;;;;r;t;r; ;f r.; ;r ;;r; Of th; ".00.;;ld I;i, i; f
i s "S*f, ;:::;t "h:2 th: r:::ter '!:::01 h::d h r;;;'t;d.
j hoot $4 s,.,wtw 3 a Te wanuar oc ** 1tc5 es a i c4 is un hwoat, h.vo tW. .
A,[TJQH:
T esos 5~, e Mung 6.,y Ea 5 8 dsen d ou *d 'Aa**** V"" no we u ,a **r-j vemzo we.i,4w A 9r'F aa.ses susu s.a Laessa.vesJr.
4
- a. With one PORV inonerables ;ither restore the inoperable PORV to l l
_ OPERABLE statu u tthin 7 days or depressurire and vent the RCS l
] Qirthrough a 2 3.Qquare inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />;. !
~
} I' - ' '
N'[* ' ."
. .N3br.1".- . ..' '['.. . "'
! S !
& e. w s.*'8' W.o j C K. Wit ti PORVs inoperable,vdepressuriz't and vent the RCS through c.4 lees 4~
a2 ""! i ;-
! veat re-68tice ht!' S(th ^^a3; h;;; h; . r;;t;r:d t; 0*;=;.Esquare inch vent
- j .......
I c. t. In the event either the PORVs or the RCS vent (s) are used to j mitigate aniRCS pressure transient, a Special Report shall be i
prepared and su>mitted to the Commission pursuant to
! Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient the effect of the PORVs or Rc5 vent (s) on the transient jand any correc,tive action necessary to j prevent recurrence.
t
- k. kJ.wt aus DuW swowsunut ew HobES Ts.,6. ei&r-C0 ns4c,re 6a adorsa. Ant g PO1W 4o OPElt.ADL4 averros w.w u 7 M Leur1. or (U l l C.cnas wre sle nvessa.#itc.4tud ed ve04 . THE 'itC1 neoucN e Lem1T l , <~ d% Scavnee io a ue.,r om,, , wr.C. e, xi. saans.
l d tA.):wn WE TCS vtswth Pen. AC.T'l005 a b.se c., veciary we ugg unwoAY arr t tAs'r e wes Det. '31 c4cvs s Hess4 ses Paws)* t& Dam buh tv .4 vac vtil5) i Tww n u.smann . stauch.ua. aprinassi had' 3sc.uk.sb w we cAarn.) harr'uM;
} . vecin we sm:r newmany away it. m as. '
- 4. %e. Muus w s,s > sc.: Arl&hJ *d.C).N Cft 6.88f A DhUC A k t.CS.
4 i
' 3/4 4 21a Amendment No. 50,151 j
_ _ _ _ _ _ . . _ . _ _ _ . _ . - _ . _ _ _ _ . ~ . _ _ _ _ . _ _ _ _ _ . . _ ,
Docket No. 50-336 B14924 5
l :
I Attachment 2 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Generic Letter 90-06 l
Retyped Pages f
l l
l r
l ..
i September 1994
-- .. _ ....--.__- _ _ _ . = - . . . _ , . ..__ _-
i I
i .
l REACTOR' COOLANT SYSTEN i
l- RELIEF VALVES I LINITING CONDITION FOR OPERATION i 3.4.3 Both power operated relief valves (PORVs) and their associated block l j valves shall be OPERABLE.
] APPLICABILITY: N0 DES 1, 2, and 3.
j-j ACTION: ;
I f a. With one or both PORVs inoperable and cmable of being manually i cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s)_to OPERABLE status i or close the associated block valve (s) with power maintained to the 1 block valve (s); otherwise, be in at least HOT STANDBY within the ;
j 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 />. i 1
4 b. With one PORY inoperable and not capable of being manually cycled,
- within I hour either restore the PORV to OPERABLE status or close 4
its associated block valve and remove power from the block valve; *
- restore the PORY to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or
! 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 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 />.
I j c. With both PORVs inoperable and not capable of being manually cycled.
- within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or j close the associated block valves and remove power from the block
. valves and 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 />.
! d. With one or both block valves inoperable, within I hour restore the
- block valve (s) to OPERABLE status or place its associated PORV(s)
- controls in the "close" position. Restore at least one block valve j to OPERABLE status within the next hour if both block valves are ,
inoperable; restore any remaining inoperable block valve to OPERABLE 4 status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise be in at least HOT STANDBY within j 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 />.
i I
I I l
I d
i i
NILLSTONE - UNIT 2 3/4 4-3 Amendment No. JJ, JJ, JJ JJJ, oose 1
REACTOR COOLANT SYSTEM l
SURVEILLANCE REQUIREMENTS 4.4.3.1 In addition to the ree.uirements of Specification 4.0.5, each PORY shall be demonstrated OPERABLE: l
- a. Once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and
- b. Once per 18 months by performance of a CHANNEL CALIBRATION.
- c. Once per 18 months the PORVs shall be bench tested at conditions ,
representative of NODES 3 or 4. !
4.4.3.2 Each block valve shall be demonstrated OPERABLE once per 92 days by operating the valve through one complete cycle of full travel. This demonstration is not required if a PORV block valve is closed and power removed to meet Specification 3.4.3 b or c. l f
?
l i
l l
l
- NILLSTONE - UNIT 2 3/. 4-3a Amendment No. JJ, JJ.
0098
I s e
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION l 3.4.9.3 Both power operated relief valves (PORVs) shall be OPERABLE with a l lift setting of less than or equal to 450 psig. ,
l i' j APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than or equal to 275*F. MODE 5 and MODE 6 when the head is on the reactor vessel and the RCS is not vented through a 2.8 square inch or larger vent.
I ACTION-
- a. With one PORY inoperable in MODE 4 restore the inoperable PORV to l ;
l OPERABLE status within 7 days or depressurize and vent the RCS
! through a 21.4 square inch vent (s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. l l
! b. With one PORY inoperable in MODES 5 or 6, either (1) restore inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurization and vent the RCS through at least a 1.4 square inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
- c. With both PORVs inoperable, complete depressurization and vent the RCS through at least a 2 2.8 square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
! d. With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve (s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i
- e. In the event either the PORVs or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.
)
l l
1 l
l l
MILLSTONE - UNIT 2 3/4 4-21a Amendment No. Jp, JJJ, i 0099 l
!