Letter Sequence Response to RAI |
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TAC:MF3673, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARGO2-14-043, License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level-High2014-03-24024 March 2014 License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level-High Project stage: Request ML14115A2132014-04-28028 April 2014 Supplemental Information Needed for Acceptance of Requested Licensing Action - License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High Project stage: Acceptance Review GO2-14-076, Supplemental Information Regarding License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High.2014-05-0808 May 2014 Supplemental Information Regarding License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High. Project stage: Supplement ML14129A4242014-05-0909 May 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML14206A0112014-07-31031 July 2014 Request for Additional Information, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High Project stage: RAI ML14254A1772014-08-28028 August 2014 Response to Request for Additional Information Related to License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High. Project stage: Response to RAI ML14262A3412014-09-24024 September 2014 Request for Additional Information, Round 2, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High Project stage: RAI GO2-14-157, Response to Second Request for Additional Information Related to License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, SCRAM Discharge Volume Water Level - High.2014-11-0606 November 2014 Response to Second Request for Additional Information Related to License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, SCRAM Discharge Volume Water Level - High. Project stage: Request GO2-14-171, Supplement to Response to Second Request for Additional Information, Related to License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High2014-12-15015 December 2014 Supplement to Response to Second Request for Additional Information, Related to License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High Project stage: Supplement ML15063A0102015-03-27027 March 2015 Issuance of Amendment No. 232, Request to Revise Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High Project stage: Approval 2014-05-08
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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
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RWAu4 WA 90362-.M I l'4mwgiy.S0T/m4 AUG282014 10 cFR 50.90 G02-14-128 U.S. N e isior Oonwnilen ATTN." Doc~men CotolCelk Wa**Vu n D.C. 209*401 SecO OU tMNSl PAIO SOWATW N.4W TO -0i -- l T VO GWOiTIION1SLC4.
IIISPS~CA!I3TAILE t.1.t4 PWICYIOZ ass* mcwms
- Wn1 RIWS m- WOW Woreis: 1) LOW*QW-14043, dated Mch 24, 2014, AL Javork (Enerw Nor~thAst) to NRC IjWn Ist f or Changing iiiwii-KiAmenmetviii Twhs *ee s flTdn Ta1Te 3.3.1.1-1 Furxcion 7, 'Scram
- e;iarle~ olme WatLevel - Ng" (ADAMS Acoession No.
. 0l~ealet)
- 2) .* talir, M o NRC, doed GM-144M May *,14, * ,AL
&eetitemto Jsm* (ErwgyUcnee Rsgardnog Ailunment Request for ChangingTechwkl s!lo~nTl 3.3.1.1-1 Funto 7, 'ra Dilchwg Voum Water Lt*v -
(AD" A*cmeion No. ML 14141A63*
- 3) Leter died July 31, 2014, CF Lyon (NRC) to ME Redmenn (Energ Northwes), 4%"Asa for Additional OONWrmatioveae to 1111ewe A mendej"t fReus for Cheoq To4nl* feodkat T"l. 3.3.1.1-1 Funcfon 7, 'Sorm Dicftpge Volume Water Leve igh' (TAC No. MF383)"
Ow Sir or Madam:
By PRfrecs 1,Enery NorthW subnied a U Amendment Psewe (LAR) to
,ne change Technical Spe-lhlcon (tS)TOl*e 3.3.1.1-1 FIo 7, Sram Disecharg Volume Water L*v - oh. By R*frnce 2,Eeg frthe prided s e-"met inWmAon to msppon I* Ina LAR at rftem of to NRC. By FRefrenc 3, to IRguW~ry Coritson (NRC) mqumsied oeUtnl Nucilar ki#nftn related to the Enry NaoW *AmnWf. Transtd lhermwh InAt~omt 1 is the Enerw Northestm repmoe to the requeWt fr atnal ftrmatlon.
TSPW TOAow=NI'. VGRWMTMROA~ TO TABIE S.8mm.1-1W M S1COI4CH1aGEflaw WS L3LN
'Pape 2o 2' No new reguWory comrnments are being made inthis subnraW.
Should you hewe wny questons or requi addhon o reg._ng this mAntr,
~ v l Ms.LL Wlams, UcnnSipgwvor, at (09)3774*48.
I den.- nmder penty of 0uXYOw ft fore$g904 end ooremat A.L. Javai Vims PnsMI En*i*imng NWA w-o-
-I 8mo4(
WA NoMk - Winsfton &Straw (email)
"Juw- WOE4~mI A '44 4$'
4 ()~ )I~4
- ~ ~ C 444 r~ A '~ 3/4 3/4 *~ *~44 (
4"-'> C 1 ~ '"-~'
4 4 ~ 4, ~1 1'-" - A 4\A
--. 4' ~ ~,, , '
A .- 4
V115O L,*_.*A Ai*l Toin 1lký N**I1L n1l~11 m OH~in TECIUC UPST Y
TMlSt 36U.t.114 - T10M, 'M-S-- VOLUMS WA t LEVEL-papIla 5 The c alonk e*uncy In the TU ftr *0 is defined as 18 month. In the supplenieMtea let dted May C, 2014, Vde
=ooesslve A of 24r= monl oIoed for the Instrueno uncertainties and l--on. Pism **anwhy akroquency of 24 nm* was ect** ,
9n1e ft is n#the eurovllnos freqM ied In fe T&,*4 ft f, t*ot
-u19lc0 i uuIwpt wel lmno sfequenc. AomV oxpsnW "w,1hrmon frquoey was usd to sm at Ireurunent drft.
The Calbra~od fro~uancy $&or sniwdicr b~Teton i m Is 18 onth~s. The *Ift pu*W by ftemwt for ft 31 52ND2 trS tr* +/- (0.1 % Up.arRangLUr*t +
0.1% 01*0 value* 01heverl qw,3a Forths.
qeler llmn pulishe *Ilt
- cosdee *,xwiw of I looplve.* f4er takkn uwwWefly, do 44 A*ing~hte full v*Mu of'lftopos non- vatve for calculation of the as found calibration tolerance. Therefore, M is rema uang the as found teranco using the drift 18 monhMs.
In adidition, a reylow ot sit scalisons associated wtth fte TSTF-493 fqonions klnostes thoo the Tehnscal, t, frequency with the exception of three flvali%#W the d was .t Mundr the(I mo*fis plsi2t% extensionper TS Suwrafl6nc RquiM(3.0-2). COS$Isrecactkxiag the As found cdtbrdn tOleranre. Ictft toteesofihmctlons using the drift associated with their assoclated TS callbration end Ag-Poun Tql~e4A1 analy*lic lfttnWt~here&$4l~.~
t ,std~
4une 19, 2014, tlqrgy Northwett iespndeti lo this request MofIorinteo.).~h response referenc.ed the descriptlon of tha nv~dtod6tgy that was provided previous in i*>UrG.14-0 78 (Refoerenc 1.4). Specifically, Energy Northwest stated that "pages 7 Viroua 13 oft he encwoir to OWt letter prwviled 4 descriptiop of ft rnalhpodot used to d~terr~lothe AFT, ALT. and LTSP for aproposed dih'a ito thq all he fu*ndons that will Include
RESPONS TO UGOUEST FOR ADDITIONAL INFORMATION RMATED TO IUCENSE h REUEST FO CHANINM FMIL SPE -ITIOM TAMBLE . FUN-ON 7, "SCAM DISCHARGE VOWL WATER LEVEL
~; HIGH" Page 2 of 5 Surnielance Nofts I and .'As such, fth response provide above to Ofts lates RAI applies to te Pefence 1.1 and 1.3 s*xnfta as well.
S1.1 Leoer Q)2-1-136, dated Mker 2,2013, AL.Javorik (Enrgy Norhwest) ft WR, %*am*e Mienewo RequMs for Adopti on QTS-4%Revisfon 4, Opfon 1.2 Letter, dMed Apr# 30,2014, CF Lyon (NRC) lo ME Redkman(Energy
,vi - rin Mmuon - - fMl-*-I-ortati 1roated . onensem1nmort Rlquest to Adop TS-F493, Revision 4, Opthon A (TAC NO. MF28)'
1.3 *
- D2-t4-103, dated June 19,2014, AL Java*o( r 1)to NRC, URWpOW PAsiuln to License Amendment ReustMr AponoffSTF-4B, ROOMxI4, Cpton Aand Response to AequWs for Addlonl Ioraton 1.4 Low, 40244W76 0" hWA 2014, AL Jvmk (Eey Nothwst V NC#
swInformalln Regdl Lcnse Anleridmenit Reques for Changing
+ m T*hn! SpecificdnTbe3A .1-1 Functdon 7, 'Scratm Discharge Volume wLeveI-High-
- Tables *A.I*d 2.2 of thesupplemental lnfomn providd kaut uncerainties and d I I ie*Ints iterm of acur of olllbrated ll. Pluses provide the vendorptwised values represendnq fte pr1a ourlS s@t wh the minimrutt **rtd spanIth maximum cal *axtpar,, proposed
,, I4th's Tab~sS.A &M2.2 below provids the requested informnation for CRD-LT-1 30 &Dand
+ CROD413040, r0espetively. NO t unetant An cMft input'swhih are Idepwownt of to design of %i nIc~nn~~raumefts are not Wki&ded inthe tables.
l-SFor eacb deolgK~ut, the Wae show~s Wivgnx* pubfis*Id'dab4 *vlatlons at (ySminimufli, m&axlAIk and pqmjtd spaqq. :.: %Whee
++ + appropuiat,
" :: + uMwpdons are listed o + w+ *+.
W+ :+... e dat Ttvus #0"II . ++ +C, of pcentage of tlbrated span) which ii "W, re :o"" ~8feren"2.1 ieioipW~byboxedtJ
- 2. 1~L~e, (QW.14-76,deatd May go 2014, AL. Javoulk (Energy Northwest) to NRC,
'SupleetalInfrmaionRegrd~g Lcei~AiendentReqestfor Changing TechnioA Secld***o Table 34~.1.1 -1 Funcb 7, 'Scr~ii Discharge Volume Water Lei44Ifgh
MO iI@ oIn W OCAMU M114 34,1.$4 OVNCN 7, 1CI MOSLUR wAUrn ~guW T" 2.1 - hutnumt Wes -taln an&W Ca~bration am! Drif DOW ipt W CO.T-113C a 0 0"#Vnk~~~~~~~~~o0pn(5" wm S f"C Ps"Wdm s
POPWspa (66")
t02%~~~ 0.% o C 2%
10.05" o.5+/-0t132*
Dft*,M 1 A0.%VA. t(0.1%x250+0.1%x25) +/-f(0.1% x250 +0.1% x250) 1 (0.1% x250 +0.1% x66) 0,4t%spa) per m+O0275m -*0.f *0.316' imOM -f0.275+ 25X1 00 a tOs+250 X100 1+/-0.31 + 66 x1100 C
I________
a____ -+/-i =0.2%C t0.1%o Drift for 18 (VuiOr~k +/-0275 x18 40 +/-0.sx18a30= t 0.316 x 18+30 ffonfl thS@*~ 0.16W3O u+/-.OAS' mi.1I030um+/-L+21 +/-t8 1
________ C7_________*_4_0__-%- C S AC PSE = Power +/-11.8M6 of span 00%aftpms2.4 +/-0 .012%o(CS I .1%o SuplyEffctpo V*t Y.12%ofs 0.012% x250 .0.012%x66
-t +/-.~2 0:t.*S t 0.0792 RE - 10m2t-aURL +/-0.25% of URL x 6.84o +/-0.25% of UAL x 0.84 +/- 0.25 d UAI. x 0.84 Radiamo duito and after =025% x250 x0.84 +/-.%x 02 250 x 0.4 =0.2Mx250 x0.84 Effect = 0.625" - +/- 0.525 - i 0.525 a T of 1 tM*ad -+/-O0.525-v2SW*W O..*1WxlO00 Ut.Rt0-at adose rate of -*2.1 %CS w+/-0.21 %CS - 0*%d
_________ A 0.1 Mradsihr. __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
bMW -OA np*l *ahy is asaucd to be *10% of Owe smotun 24 VDC nlooppy voltap cTIM& amý 5228 is o(OARS .k *m '*.~fefu ts bnewty prapstmal to 170, it wMl be .2$ %of URL x &4EFMW
v, TAW 2.1- Iwunottme Unceralntid andIO Mi o RDTI ,(cn~ud k i~ a W-o _ _ _ _ _ MA~u TE* Transmitter:
Tyarstmre +/-(015% URL + t (0.S%URL + 0.6% span) = +/-(0.15% URL + 0.6% span) . 5%U + 0.% span)
Effs' *S%span) per +2' +2 +2-100F =+/-(0.15%x250+0.6%x25) .,(0.1S%x250+0.6%x250) m+/-(0.15%%x250+0.6%x8)
-* trperaWrs, +2 - +2 +2
-+/-0.2620 ,..s- 0 -+/- 0.385 Remote seal with OC7O sificone (+/-$1.4in forfirst 5ft =O+/- 3.1r(RIsnot span i 3.W*(fkis not span
-1(1.A4 uVg for capillary + 0.7 in wg for each dependen) dependent) r> ft o addtonal 5 ft of csoilyy + 2 cmwy* 0.7i =+/- [1.4" + 0.7 x (40-5)+ 51+ 2 vor awk. s +/- 3.15" aMd*" 5 f of nokmined terrfrature TtMt Thetm tenpeatw The conbined t~mmtur effect is: effect is: is:
Iffct
- -(.2622+3.152)/2 -(0.937 2+315 2)12 (0.3852+3.15 2)"2
+/- 3.16 =3.2" =t3.1r
=3.16+25 x100 =3.29+250 x100 =3.17+66 xlOO -+/-4.80%
=_ 12.64.% of CS =1.32.%of CS of CS.
- SpwfIfi..m fo vI[ sod the r-aswagcan te Wmaely murpd&W dmm to 50IP Nohoc .1p~iw=yaI.6 iC h dmg ~%.( s~t wspe.~Mciicadns on the Rgaucte Diaphragm Seal veaf
RESPMONIE TO REQUEST POR WS1NA E_,R-- -ON RELATW TO UK i WM IMN T REQUEST FOR TECHNIA SPECICATION T# WA3.1.1-1 PIJCMIOSS?, A DSC"W VOIUM WATER LEVEL- IIOH" Atachfme I Page 5 of 5 Tale 22 - ftwmrus aIt m b mid DuWf" Design hIpt for CRD-LS13C &D
- * ~ ~ WtI IM"4,J- FLO OWN * *m*(
k~ !.value__
DesI" Vendo Publehe nmh unM 8pM W) AxhuMM SWa (2Wn CBS Prupese Spa (6 RA-=+0.1% Of CS 10.1%of CS -.0250 t+/-0IoOS=0.25' I50.1%ofOS-+/-O.066 Reference Accu.racy*
DR = Drift None . 1.0% Of CS = 0.25" 1.0% of CS - 23*i1= 0.66" PSE0 +/-o.15%of spefW 0.1,%,x 2.4 ,0.36%of CS 0.3S Of Cs Power power variation +/- 0.38% of CS - 0.036% x 250 -0.3% x 66 Supply -0.36% x 25 - 0.9" +/-0.2376" Effect = +/- 0.09" RE - None 0.0% of CS 0.0% of CS D Radiation The component is Effect located within the control room an radbaon effect Is negkt. _____
TE Ambtient Tenperaohw 0.0% Of CS 0.0% Of CS 0.0% of C8 Temperature Rang,,
Effect 0OF 1Oto140F Trip PoWt Stalbiy and Dri, r For25 IFto 125 TF
+/- 0.01%/F maximnum
+/-0.004%1 typic _
Per Eaajy Ndihwest's setpoiat methodology, in the absence of a mambwags expressio oftdf, or a calcidaW exjwcssion of *ift as danvW kom Aiul perfr*rmace hisotis, the defmit valve of 1.0% of CS bias shod be used
'The power supply stability is assumed to be
- 10% of the wmuiad 24 VDC loop supply vokWe.
JThe componen is located within the control room, ud is calibrated within die noma temperaftre ymp of #w cowr room. Mw teuputw c t is zero.