GO2-15-041, Cycle 22 Core Operating Limits Report, Revision 1
| ML15079A214 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/11/2015 |
| From: | Gregoire D Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GO2-15-041 | |
| Download: ML15079A214 (20) | |
Text
DNnRTW.GONO" P.O. Bao 968, PE20 aw nRichW4 WA 99M52-09%8 Ph. 509.377.8161 F.500.377.4096 dWegor O energy.nolmhwgst.oom 002-15.041 MAR 1 1:2015 U. S. Nuclear Regulatory Commission "
ATTN: Document Control Desk Rockville, MD 20852
Subject:
COLUMSIA GENERATING STATION, DOCKET NO. 50-397 CYCLE 22 CORE OPERATING LIMITS REPORT (COLR), REVISION 1
Dear Sir or Madam:
In accordance with the Columbia Generating Station Technical Specifications (TS) 5.6.34d, Energy Northwest herewith submits the Cycle 22 COLR, Revision 1. The operating limits in the COLR revision were d.ve" in accordance with the requirements of TS 5.6.3.a, b, and c. The changes to the COLA have been reviewed by the Columbia Generating Station Pant Operations Committee.
No new regulatory commitments are made in this letter. If you have any questions or require additional information, please contact Ms. L. L. Williams at (509) 377-8148.
Executed on this /L day of Aa-reV, ,2015.
Respectfully,
-R.
D. W. Gregoire IS Vi Manager, Regulatory Affairs
Enclosures:
As stated cc: NRC RIV NRC NRR Project Manager NRC Senior Resident Inspector - 988C CD Sonada - SPA - 1399 (email w/o enclosures)
WA Horin - Winston & Strawn (email w/o enclosures)
COLR 13-22 Revision I
. 4. ,,
Columbia Genbrtng Station Cycb 22 Cw* Operatig Umbf fteport A.
44 Februay 2016
Columbia Generating Station Core opeathng LUnits Report List of Effective Pages i............................................................................... I.......................... .............................. 0 1................. ..... ........... :..................................... ............... ...... ..I.................................... :.......
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- , ., + .. O.lumbia Generating Station Cycle 22
" :: : *: ". .*, . , ".\'Cor 'Oi:fu ting .LirnlWRepE ll*1s e' ,:,,r:.. *,.i".. :* ' *-"
1.0 .t* . , um n and . ar ...
+... .....:.... *.......o
,. ,+; .-
. +.* ;. . . + * *+ * . . ++ . ...... , . ... . .. . . . ,
2.0 Average, Plana One r Meat Generation...... Rate, (APUIR.) Limits............. .. 3 for Use in Technical Specific.aton.2.1 *.+..
3.0 Minimumn Crftcal Power Ratio (MCPR) Operat~ing. Uimi-ts for Us InTechnical Speclficdon 3.... 2........ .................... I..... . ..... ... .............................. 5 4.0 Linear Heat Generation Ra*t (LmGR) Limits for Use in Technical Specification 3.2Te ..... p... ................ 3.....
5.0 Oscillation Power Range Mntir (OPRM) Instrumentation Limits ..
forUsein LCO 3.3.1.3 .... .. ........................................................................ ..........1 5 6.0 References ................................................................ .......................... . ............... ...16 Columbia Generating Station COLR 13-22 Rovislon 0
1.0 Introduction and Summr*r . ,
This report provides the Average Planar Linear Heat Generation Rate (APLHGR) limits,'the Milnimum Critical Power Raft JMUCRY limits; the tmileor Heot Generaton Rate (LHNGR limitsand,4h Osc~llatIon Pewr Rango nltoRlt PtlM),
Inetbimentatlon limits for Columbia Generating Station Cycle 22 as required by Techmica SpeWcat5453. Asi quired by Tochnic:tSpectficatioo ,6A,3these.limits,,
Were dtermined-using .NRCeapproved mathPdloWy:enda re'stablished so that all applicable limits of the plant safety analysis ae met LOCA analyses were performed with.meModologles tha result la Single Loop Opwation (*L.O) APL.GR lim.it as well as Two Loop Operation (TLO)"APLNGR:imitb. TheAPLHGR and LHGR limitsffor., -
ATRIUM-10fuel given in this report are documented in Reference 6.1. The APLHGR limits for GE14 fuel given in this report are documented InReference 6.4. The LHGR limits for GEl4 fueW given in this report aedocumented in References 6.5 and 6.10. The f full power MCPR limits for all Cycle 22 fuel typs,(GE14 as well as ATRIUM-10 fuel) am documented In References 6.4 end G.11. The power and flow dependent MCPR limits are documented in References 6.6 and 6. 1t.. The basis for the OPRM Instrumentation limi is documented in References 6.3 and 6.4.
Th.MCPR limit is the mximum of (a) the epplicable exposure dependent. full power MCPR limit, (b) the applicable power dependent MCPR iimit, and (c) the applicable flow dependent MCPR limit specified in this report. This stipulation assures that the safety limit MCPR will not be violated during say-staf operation and anticipated operational occurrences throughout the Columbia Generating Station operating regime. Full power MCPR limits are specified to define operating limits at rated power and flow. Power dependent MCPR limits are specified to define operating limits at otherthan rated power conditions. A flow dependent MCPR Is specified to define operating limits at other than rated flow conditions. The flow dependent MCPR limit, set by the limiting Recirculation Flow Increase event, provides bounding protection for all events at reduced flow...
The LHGR limit is the minimum of (a) the applicable, exposure depedent, specified LHGR limit for that bundle type and (b) the applicable power dependent LHGR limit. The Proure Regulator Out of Service (PROO$) MCPR and LHGR limits are applicable If two (2) of the throe (3) Digital Electro-hydraulic (DEM) pressure controllers are not functional,,.
The reload licensing analyses for this cycle provide operating limits for Extended Load Line Limit Analysis (ELLLA) operation which extends the power and flow operating regime for Columbia Generating Station up to the 108% rod line which at full power corresponds to 88% of rated flow. The MCPR limits defined in this report are applicable up to 100% of rated thermal power along and below the 108% rod line. The minimum flow for operation at rated power Is88% of rated flow, the maximum is 106%.
The Reference Loading Pattern referenced in FSAR 4.3.2 is documented in References 6.4 and 6.9.
The specific topical report revisions and supplements which describe the methodology utilized in this cycle specific analysis are shown in Table 1.1.
Columbia Generating StationR COLR 13-22 Revision, I
Table 1.1
~114itiben Toploat Reports
- 1. XN.NF-.81.-58(P)(A).Revislon 2an: onpplements I end'2; RODEK(2FueIR6dThermal-Mecai ,icalResponse.EvaluationAodel, Exxon 'Nuclear Company, March 1984*.,,.
- 2. .,XNINF5-67(P)(A) Revision ,., Genriw.MeantilDesignfor..A NuclearJet Pump
.BWRRelo&adFuel, Exxon Nuclear Company, September 1986.
- 3. EMF-88-74(P) Revileoh OSippl~hent I(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-MechanIcalEvaluationModel, Siemens Power Corporation, February 1998W.
- 4. ANF-89-98(P)(A) Revision I end Supplement 1, Genetic MechanicalDesign Criteriafor BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1998.
- 6. EMF.2292(PXA) Revision 0, ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
- 7. NEDO-32465-A, 8WR Owners' Group ReactorStability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, August 1996.
- 8. NEDC-33419P, GEXL97 CorelationApplkable to ATRIUM-10 Fuel,Revision 0, June 2008.
9, NEDE-2401 1-P-A and NEDE-2401 1-P-A-US, GeneralElectric StandardApplication for ReactorFuel (GESTAR II) and Supplement for the UnitedStates, Revision 19, May 2012.
- 10. NEDE-24011-P-A and NEDE-24011-P-A-US, GeneralElectric StandardApplication for Reactor Fuel (GESTAR Ii) and Supplement for the United States, Revision 20, December 2013.
Columbia Generating Station COLR 13-22 Revision I
2.0 Avers.g9 Plenar.Linear qe *ep&ioRt PtG Use ftiTcfiwkcit8peolfk .
The APLHGR limits for use in 1*1"r*nfi S'lifiton 3.2.1, as a function of Average Planar Exposure,- shall not exceed -the limitsshown in the foow1ng,tdles..APLHGR limit, for slngI*'jj,. o f-Afd GET4e!l are o1=aind, oot*g*jn O .00 Multiplier to the two Ioop oviation APLHGR irWltARL.HGR Iimits for sirgle19pop operation for ATPRIUMl10Rfuel APLHG RIim b . !... ..
obtained.. by .applyirig s 090n multiplier-to tht~o
... .. i. .. .... .'
loop-operation
- a. .T...ble2.1 -GEI4 Relad f L(4
- b. Table 2.2 - ATRIUM-10 Reliad,.Fuel Columbia Generating Station COLR 13-22 Revision 0
~h~'~TnnA*:* Planar Linear Heat Generation Rift (MAPLKOR)
Venaus Average Planar Exposure
- ° >, .~j
.o F~b-
, JJr. " ~
' 0.00 000 28 16.00 14.51 12.82 21.10 19.14 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Tale 2.2 Maximum Aveage Planar Linear HNet Generation Rate (MAPLHGR)
Vrasu Average Planar Expoeure ATRIUM-tO Reload Fuel Average Planer TLO GiOWSe )
(iM~mdO MAPLHGR (kW" 0 12.5 15000 12.5 67000 7.3 Columbia Generating Station COLR 1342 Revision 0
3.0 Minkmum Cric Power Ratio (lW*,UOP ratlng Limits for Use InTechnical Specication 32.2 , , ,, .. .
The MCPR operating limits fqiuelq I T ification 3.2.2 shall be greater than or equal to the bounding liMrrs dUetnii:nEf rWThbI% 3.1 through Table 3.7.
. The MCPR safeylimit for Cyd...22 is 1.09 for two Ioop Qhin(TLO) anlmts*lO.fr -
single loop operabf(St0).' Th power and flow depeh~ ht MCPR limits fr SW require a 0.01 adder to the TLO MCPR limitsdue'to theji spice .. in the MCP., ,t
,.*lim it . . . . . . . . . . . . . .. . ... . . . . . . . . . . . .. . . . ...
- t ...ynt.. - . . . ...- ;
S. , 1 .
S..,'*i .
C..
V Columbia Generating Station Is, COLIR 13-22 Revision 0
Table 3.1 Coluep a Opneratip ton' Exp" sure Ran' .,Option V
S" All "Fuil AN Fdo' Full !.PowtumLMi (SC.)C .. o .I.4, 1.39 Full Power Limits (MOC to EOC) 1.44 1.41 Flow Dependent Umlts' Table 3.7
....Power Dependet Limits5 fgaes 3.2 2 EOC MPT Out of SeIce (,RPTOos) 7 __.... ..
Fuli Power Umls (SOC to MOC) 1.54 1.43 Full Power imts (MO to EOC) L,_, 1.48, 3
Flow.Dependent Power Dependent Umtts5 Tur*.ne Bypos VlW Out of Svice,(1UVOOsr ..
j' Table 3.7 Table 3.3 Full Power Umi (SOC to MOC) 1.44 1.41 Full Power ULmit (MOC to EOC) 1.48 1.45 Flow Dependent Lmis Table 3.7 Power Dependent Limirs Table 3.4 4 TUVOOS' ar tapOo . . ...... .. ._ . .. .... ... _
Full Power Limits (1OC to MOC) 1...7.. 1.4 Full Power Umits (MOC to EOC) 1.68 1.51 Flow Dependen ulmt s, Tae 3.7 Power Dependent'Lim -ts Table 3.5 5 Prmre Reguator Out of Service (PROOB. __._ _....
Full PowerrLimits (BOC to MOC) .. 1.42 .1.39.
Full Power Uml (MOC to EOC) . 1.49 1.41 Flow Dependent Limitsb Table 3.7 Power Dependent Limits ., ... .. Table 3.6,. -
Columbia Generating Station COLR 13-22 Revision 1;
Notes fdi, Tulbw'l x t . ', . .:;,.::,*. : .:
Note 1: For Single Loop Operation (SLO), ýfe. SLWMPR increases by 0.01. This 0.01 Increase must also be applied to the Two Loop Operation (TLO, MCPR perating Limit to obtain the SLO Operating Um : .
Note 2: The cycle exposure range designation is defined in Table 3.1-1. End of Rated (EOR) is definetla the cycle exp6W 1respodlfo all O ok,&100% pofwr, 100% flow and normal fiedwater t*enper*tute:'-The IM 6tilts4 A"Ippliblebfor 06otmal feedwater temperature, feedwater heaters'oiit-bf Mce',:lialfeM'watm.:'
temperature reduction and coastdown.
Tabe M.-1 Cycle Exposure Range Oesign 130C to MOC s EOR-2344 dI~V MTU (2126 MWdIST)
,MOctoEOC > EOR-2344 MWd/MTU (2126 MWd.ST)
Note 3: The NRC has concluded that a statistical approach (Option B) may be used for pressurization events analyzed with ODYN (References 6.7 and 6,8). In order to take credit for conservatism in the scram speed performance, it must be demonstrated that there is Insufticient reason to reject the plant-specific scram speed as being within the distribution assumed In the statistical analysis.
The procedure described below determines the full power MCPR limit based on the scram times of SR 3.2.2.2. Ifthe scram speed distribution is not within the assumed distribution, the MCPR for pressurization events must be re-established based on an interpolation between the applicable limits for Option A (scram times of LCO 3.1.4, "Control Rod Scram Times") end Option B (realistic scram times) anrlyses.
The surveillance information for thelfuil dycle Is the number of active control rods measured for each surveillance test (the first test is at the BOC and Is denoted N1; the P test denoted M*) and the average scram time to Notch 39 for the active rods measured In test Idenotedr,r . . ,
The equation used to calculate the oviprfl! avaserge of all~th scram data gonerated to date In the cycle ....... .....
-.. '='- (1)
Nr, Columbia Generating Station COLR 13-22 Revision 0
wh~ere:
jnRnbq 1suvllpe4sts pmfrm4 t9 date in the cycle; ftotl numbet;?f active rods messjred to date in rN, the cycle; and mWnf thie -Screts tV to Notc 39.ofal" ctiive
== *rods *astekdtd date in the,-*yc1 tC*Mply
,With the Techni.al S06cification surveillance
, . .. ".e 7.g
. . ..n.al...y,,. mean -usn
- th.
Ift gla the *ýlsl mean usig #
The avnge scram time, following equation:
- .,w 5 TO (2) where:
(3)
T =# + 1.65 (4 SNI 0.672 seconds (mean scram time to Notch 39 used in the Option 0 analysis) 0a= 0.016 seconds (standard deviation of p)
N, = total number of active rods measured at SOC to comply with the Technical Specification surveillance requirements.
If the cycle average scram time satisfies the Equation 2 criterldo, continued plant operation under the ODYN Option B MCPR for preasurization events is permitted.
If not, the MCPR for pressurization vents must be re-established, based on a linear interpolation between the Option 1 and Option A MCPRs.
(
The equation to establish the new operating limit is giveffbefow:
' o"~ ,* . -.. .*- ., . .. . .
OLMCPR.I = ,0 + ITA -TO ,----- AM CPR (4)
Columbia Generating Station Me- COLR 13-22 Revision 0
where: Tr
- I and 3, respectiv ly rA , 9
- J'iv 8sebnds '( Technical Specification limit
...... . on average scram timeto Notch139) .
AMC'PR= . QR.AMCPRq0=&#tt .df.prnc
.. . ... . between the MCPR calculated using Option A
' ..... .. . .... . .... ev nts~fmmTable3 . 1q) . .. . .... ........ ..
. MCPROPUW 1AU t" t mlting pressurization evient Opition A
- . . .. ..... . . . .. .. .. .. MCP R . . . . . .. . . . . ...
MCPfop.. . = . the limiting pressurization event Option B.
MCPR Note 4: Flow dependent MCPR limits are applicable to TLO and require the SLO 0.01 .
adder when operating in 8LO.
Note 5: Power dependent MCPR limits are provided for core thermal powers greater than or equal to 25% of rated power at all we flows. The power dependent MCPR limits for core thermal p m lesethen 30% of rated powe are subdivided by core flow. Umits are provided for core'fbAos greater then 50% dfwratsd flow and less than or equal to 50% of v*tbd flow. A step O " in the power dependent MCPR limits occurs at 30% of rated power bcaube direct scrams on turbine throttle valve closure and turbine governor valve fast closure are automatically bypassed below 30% of rated power and not applicable per Technical Specification 3.3.i.i.
The power dependent MCPR limitsnln Tables 3.2 through 3.6 are provided as Kp multipliers above the direct scram bypass power level (Pbypass) and as absolute.
MCPRp limits below Pbypess. MCPRp limits above Pbypass are determined through the following equation: MCPRp = Kp x OLMCPR(Futl Power Umit). Power dependent MCPR limits ar applicable to TLO ard require the SLO 0.01 adder when operating in SLO.. .
Note 6: A step change in the power dependent MCPR limits occurs at 85% of rated power because the APRM Fixed Neutron Flux - High scram is limiting at and above 85%
end the Reactor Vessel Steam Dome Pressure - High scram is limiting below-.
85%. 7 .L Note 7: Limit includes a single bypass valveout of service (Reference 6.11).
Noe8: Limit includes two or more by;pas valves out of service (Reference 611 ),".....
Columbia Generating Station .-9 COLR 13-22 Revision I
Table 3.2 Columbia Statlon Sqneratlng Applicl*ct Grou kdE.A t In Service Lkmilsfor Power<3#Am%--
Power (%) Limit for Flow > 50.0% Limit for Flow S 50.0%
-pI -C*. .... -M - *.
20.0- '2.2:
30- .2-
/,haffor Power_
30.b~'~2 a0,6%
Pobwer M% ii nninn * .. n. .. ... 4 ...
30.0 . 1.483 45.0 1.280 60.0 TITO 35.0 1.072 100.0 1.000 Table 3 .3.. .
CoeMb am Staon S%
Application *raw 2: 1O0 RI' Out of Seoice (RP. ) ...
TLO Power Dopendet ICPR LimftS ANFueIlTypne LlmlfwforPwer < 30.%________ _______
Power (%) Limit for Flow > 50.0% Limit for Flow _50,0%
McPRp . cPRp 25.0 . 2.30 2.27 30.0 2.25 1.2.21 Lirnhafor Powwr 30/. _______________
Power (%) Limit.
.K4 30.0 1.483 45.0 1.280 60.0 .1.50 85.0 1.072 1o0.0 1.o.00 Columla GenrIg SWn COLR 13-22 ReviWan 0
- * °rs..- ...
Application Group 3: Turbin QNiWe&VejIv* Out of Service (TBVOOS)
TLO Power Dependent MCPR Limbt
- -. . . .-. A. fetTyp .
Limisfor Power < 3&O% ,/..
.O.* _ _ ,__"_,
- ower (%).- Llim.t for Flow> 50,%W Limit for _ $0.0%
- i,.-, MCPfp . in 25.0 . 35&. . . . . . 3.25 . . .
30.0 .- 3.07 j ..... 24 .
LibWfor Powera 5OL9%____ __________
Power (%) Limit S~Kp 30.0 " -.. 1.433 .. . .. . .
J;; I nn n II II IAII 93 45.0 1.280 60.0 1.15o 85.0 1.072 .. .
100.0 1.000 ..
A o.eQmup 4. 40V* aod WTOOS TLO PMW~ DependstetM. Lhnlt Al F9e0 Typ Limbs for Powe < .00 Power (%) Umit for Flow > 3&0% Limit for flow S50.0%.
_____________MCPRp MCPRp 25.0 3.50 3.25 30.0 3.07. 2.84 Lbefts for Power> 3A0%
Power (%) Limit Kp 30.0 1.483 45.0 1.280 60.0 1.150 85.0 1.072 100.0 1.000 Columbia Generating Station -1i. COLR 13-22 Revision 0
Columbia Generating $stlon A0pplatftaoGroup !'Pmssure:t6ga tor Out 6fSeivik.(PROOS),
~~ .-TLO:Povwer pt~dsntMCPR-UmlW All Fuel Types Lbudis for Po,*r bile%
Power (PA) L for,F6ow
- 50.0% mit for FlowS 50.0%
_-iPP,_p .. .......... MCPR ...
- " 25.0 :** '" '* *':* **"2.30 "" 2.7 30.0 2.25 2.21 LimilaforPower2:30.0%______________
Power (Limit
_ _ _ __ __ _ _ _ _ _ _ _Kp 30.0 1 761 45.0 1.570 60.0 1.468 85.0 1.327 85.0 1.099 100.0 1.000 Table 3.7 Columbia Generating Station All Applicaion Groups TLO Flow Dependent MCPR Limits Al Fuel Types Flow (%) Lbmit 0.0 1.85 30.0 1.65 90.0 1.25 108.5 1.25 Columbia Generating Station .12. COLR 13-22 RevhOn 0
4.0 Linear Heat Generation Rate (LHOR) Umite for Use In Technical 8pecificaion 3.2.3 The LHGR limits for use in Technical Specification 3.2.3 are given as a function of pellet exposure for both the GE14 and ATRIM491 fuel. The LHGR limits shall not exceed the limits shown in the foillwi".. .. , , .
- a. Fuel Bundle Informat ,;Ipr and 6.10) for GE14 Reload Fuel 6c.,,
- b. Ta 4.1 for ATRIUM-10-Reload.FUeI........
- c. Table 4.2 for all fuel tOq Out of Service (PROOS) r.re.
"V . .'.
.. .. .~*... . . .4 ... ... .
.. . ~ ~ ... ... .. ..
Columbia Generating-Station- . 13i. COM13-22-Rievision.0,
%:*, . Ta.., - ,r,-".4..,
Unear Heat Generation Rid (LHGR)
...... ........ Versue.Pel tFxpowre .. ...............
- -.T*UM-10 Reload Fuel *-'.:. ...
(MWdMT% ,.A (kWl t 0 13.4.
.8900 13.4
- , ..< . . .... 7* 7.1 TOMle 4.2 Preseure Reulbhtr Out of Service (1MOOS)
Power Dependent LHOR Llmits' Al Fuel Types Power (%) Limit MFLPD 30.0 0.634 45.0 0.672 60.0 0.728 85.0 0.728 85.0 0.909 100.0 1.000 Note 1: Power dependent LHGR limits are provided for core thermal powers greater than or equal to 30% of rated power. A step change Inthe power dependent LHGR limits occurs at 85% of rated power because the APRM Fixed Neutron Flux - High scram is limiting at and above 85% and the Reactor Vessel Steam Dome Pressure
- High scram is limtng below 85%.
C91imbia Generating Station1 COLR 13-.22 Revision 0
5.0 Oscillation Power Range Monitor (OPRM) Intrumentslon Limits for Use In LCO The OPRM Inslientatlo ImIs' ss'I1 CCY3.3., :3shal n*o*ld 11* fo11Oing:
t
" "4 ,'.*2' - .'*
- r ,.* '
- *2 -Perod 8Te eclnAg rjti dio i L , 7 AnplitudeSehpont Sp -*: - 111lPuidAwrege . :.
Confirmation Count Setpolnt:N2 14 Columbfs GeneratingStation
- 15- COLR 13-22 ReMelon 0
6.0 Referenme 6.1 ANP-2602 Revision 0, "Columbia Generating Station Cycle 19 Reload Analysis,"
AREVA NP, March 2007.
6.2 EMF-3172(P) Revision 1, "Columbia Generating Station LOCA.ECCS Analysis MAPLHGR Limit for ATRIUMT-10 Fuel," Framatome ANP, June 2005.
6.3 NE-02-00-03, Revision 1, "Oscillation Power Range Monitor (OPRM) Trip Setpoints," Energy Northwest, May 13, 2009.
6.4 0000-01 57-5351-SRLR, "Supplemental Reload Licensing Report for Columbia Reload 21 Cycle 22," Revision 0, February 2013.
6.5 0000-0157,5351-FBIR, "Fuel Bundle Information Report for Columbia Reload 21 Cycle 22," Revision 0, February 2013.
6.6 GEH.0000-0076.4920-R4, "GE14 Fuel Design Cycle-Independent Analyses for Energy Northwest Columbia Generating Station," Revision 4, February 2013.
6.7 NEDO-24154 and NEDE-24154-P, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors, Volumes 1, 2 and 3, August 1988.
6.8 Letter JSC-005-8 (MFN-003-80), J. S. Chamley (GE) to H. N. Berkow (NRC),
"Revised Supplementary Information Regarding Amendment 11 to GE Licensing Topical Report NEDE-24011-P-AK, January 16, 1986.
6.9 CVI 981-01,14, Revision 1, Reference Loading Pattern Cycle 22.
6.10 0000-0098-0322-FBIR, "Fuel Bundle Information Report for Columbia Reload 19 Cycle 20," Revision 1, April 2009, Appendix C.
6.11 002N4098 RO, TColumbia Generating Station I TBVOOS for Cycle 22," February 5, 2015.
Columbia Generating Station - 16. COLR 13-22 Revision I