BVY 10-029, Core Operating Limits Report for Cycle 28, Vermont Yankee
| ML101450412 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 05/21/2010 |
| From: | Devincentis J Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 10-029 | |
| Download: ML101450412 (24) | |
Text
Operations, Inc.
Nuclear Operations, Entergy Nuclear Vermont Yankee Yankee 320 Governor Governor Hunt Road Enteigy Vernon, VT 05354 Tel 802 257 7711 James M.
James M. DeVincentis DeVincentis Licensing Manager Licensing Manage~ .
21, 2010 May 21,2010 10-029 BVY 10-029 ATTN: Document Control Desk U.S. Nuclear Nuclear Regulatory Commission Commission Washington, DC 20555-0001 Washington,
SUBJECT:
Core Operating Limits Report for Cycle 2828 Vermont Yankee Nuclear Nuclear Power Station Docket No. 50-271 License No. DPR-28 License DPR-28
Dear Sir or Madam:
Madam:
accordance with Section 6.6.C of the Vermont Yankee In accordance Yankee Technical Specifications, Specifications, enclosed is the Core Operating Operating Limits Report Report for Cycle 28. This report presents the the cycle-specific operating cycle-specific operating limits for Cycle 28 of the Vermont Yankee Nuclear Power Station.
There are no regulatory commitments being made in this submittal.
regulatory commitments Should you have any questions concerning concerning this transmittal, please please contact me at (802) 451-3150.
Sincerely,
[JMD/JTM]
[JMD/JTM] - Vermont Yankee Nuclear Power Station - Cycle 28 - Vermont Yankee - Vermont Yankee Nuclear Power Station - Cycle 28 - Vermont Yankee Core Core Operating Operating Limits Report cc listing (next page)
AbDI
(10-029 BVY 10-029 Docket No. 50-271 Page 2 of2 of 2 cc: Mr. Samuel J. Collins Mr: Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Commission 475 Allendale Road King of Prussia, PA 19406-1415 19406-1415 Mr. James James S. Kim, Project Project Manager Manager Office of Nuclear Reactor Regulation Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8C2A O-8C2A Washington, Washington, DC 20555 20555 Inspector USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC LLC 320 Governor Governor Hunt Road Vernon, Vermont 05354 05354 Mr. David O'Brien, O'Brien,Commissioner Commissioner VT Department Department of Public Service Service 112 State Street - Drawer 2020 Montpelier, Vermont 05620-2601
BVY 10-029 10-029 Docket No. 50-271 Attachment Attachment 11 Vermont Vermont Yankee Yankee Nuclear Nuclear Power Power Station Station Cycle Cycle 2828 Core Core Operating Operating. Limits Limits Report Report
Vermont Yankee Nuclear Power Station Station Cycle 28 Operating Limits Report Core Operating Revision 0
May 2010 2010 Prepared Prepared 1TResposible L. Engnr.- / (pi J/Sign 5!J7/~IO 5/-L7*iec Responsible Engineer (Print/Sign) Date Reviewed 5/17/~(o 6/17/1Io/o Fuels and Analysis (Print/Sign), Date-".,
... .. / *,*"* , /)*,i.
Approved Approved Approved Approved 2.0 J ()
Onsite Safety RevieWCodnmmittee fP rmt/Sign) Date "
Approved 5-4gro*L j, " . ML" .5111I c General Manager, Plant Operitions (Prt/ ign) Date
MEV ISION RECORD REVISION RECORD Revision Revision Date Description Description 28 28 0o 05/2010 0512010 Cycle 28 revision reVision Cycle 28 COLR Vermont Yankee Nuclear Nuclear Power Station Revision 0 Revision Record Pahge ii of i P:lge
- \BSTRACT
,'-\BSTRACT This report presents Cycle 28 specific operating operating limits at current license license thermal power power
((1912 1912 thermal megawatts) megawatts) for the operation operation of the Vermont Yankee Nuclear Nuclear Power Station Station as specified in Technical specified Specification 6.6.C. The limits included in the repC)rt Technical Specification report are average planar linear linear heat generation rate, linear linear heat generation generation rate, minimum critical critical power power ratio, andand thermal-hydraulic thermal-hydraulic stability stability exclusion region.
Specifications Table 3.2.5 pertaining The requirement of Technical Specifications pertaining to the rod block monitor (RBM) setpoint equation maximum value of N for single loop and dual loop operation operation are included in this report.
included '
Cycle 28 COLR Vermont Yankee Nuclear Nuclear Power Station Revision Revision 0 Abstract AbstrClct P;lge i of i
TA13LE TABLE OF CONTENTS Page LIST OF TABLES TA BLES ............................................................................................................................
................................................................................................... I...................... ii LIST OF FIGURES FIG URES .,..................................................................................................
...................................... '" ............................................................................. ii
1.0 INTRODUCTION
INTRODUCTION ............................................................................................................... 1 2,0 2.0 OPERATING LIMITS CORE OPERATING LIM ITS .... ~ ........................................................................................ 2 2,1 2.1 Average A verage Planar Linear Heat Generation Rate Limits (APLHGR) ...................... 2 (APLHGR) ...........................
2.2 M inim um Critical Minimum Critical Power Ratio (M CPR) Lim (MCPR) Limits its .....................................................
................................................ 2 2.3 Linear Heat Generation Generation Rate (LHGR) (LHG R) Limits Lim its ........................................................
................................................... 4
.4 2.4 Therm al-Hydraulic Stability Exclusion Region .......................................................
Thermal-Hydraulic ................................................. 5 2.5 Power/Flow Map PowerlFlow M ap .......................................................................................................
................................................................................................ 7 2.6 Operation .......................................................................................
Single Loop Operation .......................................................................................... :.. 7 2.7 Rod Block M onitoring .............................................................................................
Monitoring ...................................................................................... 8 3.0.
3.0* REFERENCES ..................................................................................................................
REFERENCES .................................................................................................................. 16 16 Cycle 28 COLR Vermont Yankee Yankee Nuclear Power Station Revision 0 Table of Contents Contents Pace i of iiii Page
\13 LIZ uiF {jj(Y4 [EN'TS (uni iniicd LIST OF TABLES Number N umber Title ?age Table 2.1-1
'Table 2.1-1 MAPLHGRLimits MAPLHGR Limits for Bundle Types:
GNF2-PlODG2B403-14G6.0-100T2-1S0-T6-3259 GNF2-P 10DG2B403-14G6.0- 100T2-150-T6-3259 GNF2-Pl GNF2-P1 ODG2B404-14GZ-100T2-150-T6-3260 0DG2B404-14GZ- 100T2-150-T6-3260 GNF2-Pl GNF2-PI ODG2B403-11 0DG2B403- 11G6.0-1 G6.0-100T2-1S0c 00T2-150-T6-3261 T6-3261 GNF2-PlODG2B404-18GZ-lOOT2-1S0-T6-3262 GNF2-P I 0DG2B404-18GZ- 100T2-150-T6-3262 ................................. ....................................... 9 Table 2.1-~
2.1-2 . MAPLHGR Limits for Bundle Types:
MAPLHGR GNF2-PI GNF2-PIODG2B387-15GZ-IOOT2-150-T6-2977-LUA 0DG2B387-15GZ- 100T2-150-T6-2977-LUA GE14-PlODNAB383-17G6.0-100T-150-T6-2865 GE14-PIODNAB383-17G6.0-1OOT- 150-T6-2865 GE14-PlODNAB422-I4GZ-100T-150:'T6-2965 GE14-P1ODNAB422-14GZ- 100T-150-T6-2965 GE14-P1ODNAB388-15GZ-GEI4-PlODNAB388-I5GZ-IOOT-150-T6-2968 1OOT- 150-T6-2968 GEI4-Pl ODNAB388-15GZ~ 100T-150-T6-2969 GE14-PIODNAB388-15GZ- 1OOT-150-T6-2969 GE14-PlODNAB421-16GZ-100T-150-T6-3084 GE14-P1ODNAB421-16GZ-lOOT- 150-T6-3084 GEI4-PI0DNAB420-16GZ-IOOT-I50-T6-3085 GE14-P1ODNAB420-16GZ- lOOT- 150-T6-3085 GE14-PIODNAB388-15G6.0-1OOT-GEI4-PlODNAB388-I5G6.0-100T-150-T6-3086 150-T6-3086 GEI4-PlODNAB388-16GZ-100T-150-T6-3087 GE14-P 1ODNAB388-16GZ- OOT- 150-T6-3087 ........................................
................................... 9 Table 2.2-1 Table Rated Rated MCPR Operating Operating Limits (OLMCPR) (OLMCPR) ..............................................
............ ............................ 10 10 2.2-2 Table 2.2-2 R B M Setpoint ............................................................................................
RBM ....................................................................................... 10 LIST OF FIGURES FIGURES Number Title Page 2.2-1 Power Dependent K (P) I/ MCPR MCPR (P) Lim Limits its ..........................................................
.......................................................... 11 11 2.2-2 2.2-2 Flow Dependent MCPR Operating ........................................
Operating Limit MCPR (F) ............................................ 12 12 2.3-1 2.3-1 Power Dependent LHGRFAC LHGRFAC (P) Multiplier Multiplier ........................................................
.................................................. 13 13 2.3-2 2.3-2 LHGR LHGR Flow Factor LHGRFAC (F) .......................................................................
............................... 14 2.4-1 Lim its of Power/Flow Limits .....................................................................
PowerlFlow Operation ....................................................... ,................... 15
(~ycle 28 Cycle 28 COLR COLR Vermont Vennon[ Yankee Yankee Nuclear Power Station Revision 0 Contents Table of Contents Page iiii of i':lge of iiii
1.0 1.) INTlRODU.CTIOiN INTRODUCTION cycle-specific limits for operation of the Vermont Yankee Nuclear This report provides the cycle-specific Nuclear Cycle 28. It includes the limits for the average planar linear heat generation Power Station in Cycle Power rate, linear heat generation generation rate, minimum critical power power ratio, and thermal-hydraulic thermal-hydraulic stability exclusion region. If any of these limits are exceeded, exceeded, action will be taken-as taken-as defined in the Technical Technical Specifications.
specified in Technical As specified Specifications Table Technical Specifications Table 3.2.5, the rod block monitor (RBM) setpoint equation maximum equation maximum value of N for single and dual loop operation included in this report.
operation are included This Core Operating Limits Report for Cycle 28 has been prepared prepared in accordance accordance with the requirements requirements of Technical Technical Specifications Specifications 6.6.C. The core operating limitshave operating limits have been developed developed using the NRC-approved NRC-approved methodologies methodologies listed in References References 3.1 through 3.4. The methodologies methodologies are also listed in Technical Specification 6.6.C. The bases for these limits are in Technical Specification References References 3.5 through 3.8. The GNF2 MCPR MCPR operating operating limits include include Compensatory Measures to bound the effects of potentially bent GNF2 spacer flow wings as described in Reference Reference 3.6.
As documented in the Vermont Yankee Extended Extended Power Uprate (EPU) Safety Safety Evaluation Evaluation andand resulting License Condition (Reference (Reference 3.10), when operating at thermal thermal power greater than 1593 megawatts thermal, thermal, the safety limit minimum critical critical power ratio (SLMCPR) shall be established by adding 0.02 to the cycle-specific cycle-specific SLMCPR value calculated calculated by the NRC approved approved methodologies documented methodologies documented in General Electric Licensing Licensing Topical Report NEDE-24011-P-A, NEDE-2401 1-P-A, .
"General Electric Standard "General Standard Application for Reactor Fuel," as amendedamended and documented in the Core Operating Limits Report. The 0.02 penalty is not applied applied to the single loop SLMCPR, because because the plant is limited limited to the conditions specified in Section 2.6 while in single loop loop operation. The reload reload licensing analysis is consistent with with the SLMCPR in Technical SLMCPR Technical Specification 1.1 .A (1.09 Specification 1.1.A (1.09 dual loop and 1.10 1.10 single license single loop) and includes the imposed license condition on the dual loop value (Reference 3.6).: 3.6).
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2.0 (-"ORE OPERATJNG CORE OPERATING LIMITS UMITS The Cycle 28 operating limits have been defined using NRC-approved NRC-approved methodologies. Cycle 28 must be operated operated within the bounds of these limits and all others specified in the Technical
'Technical Specifications.
Specifications.
2.1.
2.1. Average Planar Linear Heat Generation Rate Limits (APLHGR) (T.S. 3.11.A) 3.11.A)
APLHGR is applicable to a specific planar height and is equal to the sum of the linear linear heat generation rate (LHGR)
(LHGR) for all of the fuel rods in the specific bundle at the specific height divided by the number of fuel rods in the fuel bundle at the height.
The maximum APLHGR APLHGR (MAPLHGR)
(MAPLHGR) limit is a function of reactorreactor power, core flow, fuel type, and average planar average planar exposure. The cycle dependent limits are developed developed using NRC approved methodology methodology described described in References References 3.1, 3.3 and 3.11.
3.1,3.3 MAPLHGR 3.11. The MAPLHGR limit ensures that the peak clad temperature temperature during a LOCA will not exceed the limits as specified specified in 10CFR50.46 10CFR50.46 (b) (1) and that the fuel design analysis criteria defined in References Referenges 3.1, 3.3 and 3.11 will be met. .
Tables 2.1-1 and 2.1-2 provide a limiting composite composite of MAPLHGR MAPLHGR values for each fuel type, which envelope envelope the lattice MAPLHGR MAPLHGR values employed by the process computer computer (Reference 3.6). When hand calculations (Reference calculations are required, required, these MAPLHGR MAPLHGR values are used for all lattices in the bundle.
For single recirculation loop operation, the limiting values shall be the values from these Tables listed under under the heading "Single Loop Operation."
Operation." These values are*obtained are-obtained by multiplying multiplying the values for two loop operation by 0.82 (References (References 3.6 and 3.9).
The*P,9weraIld;flow,~.Iep~nd,e~tJ:..HGRlimits The power and floW dependent, LHGR limits (LHGRFAC'multipliers)
(LHGRFAC multipliers) 'in in Figure 2.3-1 2.3-1 ahd2~3j..2'are*suffiCient' and 2.312' are, sufficient to provide~adequate off~rated conditions provide"adequate protection for offi-rated conditions for a LOCA. Therefore, Therefore, the power and flow dependent MAPF MAPFAC AC multipliers multipliers are set to 1.
1.
2.2. Minimum Critical Power Ratio (MCPR) Limits (T.S. a.s. 3.11.C) 3.1 LC)
MCPR is the smallest Critical Power Ratio (CPR) that exists in the core for each each type ofof fuel and shall be equal to, or greater than the Operating Limit MCPR (OLMCPR), which which is aa function of Core Thermal Thermal Power, Core Flow, Fuel Type, and Scram Time (Tau).
The rated Operating Operating Limit MCPR at steady-state steady-state rated power and increased increased core flow operating operating conditions is derived derived from the cycle specific specific fuel cladding cladding integrity Safety Safety Limit MCPR MCPR and the delta CPR, as determined determined from the most limiting transient event.
The rated OLMCPR will ensure that the Safety Limit MCPR is not exceeded exceeded during any abnormal operational occurrence (Reference 3.6).
occurrence (AOO) (Reference The rated OLMCPR OLMCPR for two loop and single loop operation documented in Table 2.2-1 operation is documented and is dependent on scram time (Tau) surveillance surveillance data at position 36 (Reference (Reference 3.5).
3.5).
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Determination Oetermination of of Tau:
Tau:
I. First. ,,., shall be determined:
TOIl' l-N
" ri INiii '
r - _i=-,-'_ _
tll'<, - "
ZN, INi i='
where:
=
n = number of scram time tests thus far this cycle, N==number of active rods measured in surveillance i,i, and Ni t;r := average scram time to position 36 dropout of all rods measured in surveillance i.i.
ii. Second, 'iB r'B shall be determined:
6 L 13 8 =d+,lL + 1. 1.65 5 N where:
,lL = 0.830 =
,u = mean of the distribution for average average scram insertion time to position 36 dropout used in the ODYN Option B analysis.
oa= 0.019 ==standard (j= 0.019 standard deviation of the distribution for average scram insertion insertion time to position 36 dropout position 36 dropout used in the ODYN Option B analysis.
NI =
N, = number number of active rods measured during the first surveillance surveillance test at BOC.
iii.
iii. Third, determine the OLMCPR, Third, determine OLMCPR, as follows: '
If :s Lm'er,.e
< LB,m, then OLMCPROption OLMCPRop,io, B B from Table Table 2.2.1 may be used.
If T,,eLave>> LB, 'B,then a new OLMCPR OLMCPR shall be calculated:
OLMCPRNew = OLMCPRopfio,, B + - rs (OLMCPROption A -OLMCPROP,,W 8)
TA -- B where:
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~JLMCPR()prinn1 ,,A kjLMCPRop~i, = Option i\:::: Uption A OLIVICPR OLMCPR from 'fable Table 2.2.1 based b<lsed on Option A analysis
-natysis using full core scram times listed in Technical Technical Specificatiolls.
Specifications.
OLMCPRopio OLMCPROption 1 B3 =
= Option B OLMCPR from Table 2.2.1 based based on Option B analysis described described in Reference Reference 3. 1.
3.1.
= 1.096 seconds 0\ = seconds = = Technical Technical Specification Specification core average scram time to drop-out of of position position 36.
The OLMCPR is the greater of the flow and power dependent dependent MCPR operating limits, MCPRoperating MCPR (F) and MCPR (P).
OLMCPR =
The flow dependent MCPR operating limit, MCPR (F), is provided in Figure 2.2-2.
For core thermal powers less than 25%, the power dependent MCPR operating operating limit, MCPR (P), is is provided in Figure 2.2- 2.2-1.
L For core thermal powers equal to or greater greater than 25%, MCPR (P) is the product product of the rated OLMCPR OLMCPR presented presented in Table 2.2-1 and the K (P) factor presented presented in Figure Figure 2.2-1.
2.2-1.
Cycle exposure dependent dependent limits are provided through the end of rated exposure exposure point, which is expected expected to be the maximum exposure attainable at full power during ICF ICF Coastdown operation is allowable down to 40% rated CTP per Reference operation. Coastdown Reference 3.1.
For single recirculation recirculation loop operation, the MCPR limits at rated flow shall be the values from Table 2.2-1 listed under the heading, "Single Loop Operation." Operation." The single loop are obtained values are obtained by addingadding 0.01 to the two 100ILoperation loop. operation values (TS. 1.1.A.1)...
values (TS.1.1.A.l) 2.3.
2.3'. Linear Heat Heat Generation Gerieration Rate (LHGR) Limits (T.S:;"3.H.B)'
(LHGR1L'imits (T.S-. 3.11.B)",
LHGR is the.
the heat generation generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated associated with tfiethe unit length. By maintaining maintaining the operating LHGR below.the below..the applicable LHGR limit, it is assured that all thermal-mechanical design basis and licensing thermal-mechanieal licensing limits for the fuel will be satisfied.
The maximum maximum LHGR limit is a function of reactor power, core flow,Juel flow, fuel and rod type, and fuel rod nodal exposure. The limit is developed using NRC approved methodology methodology described in Reference Reference 3.1 to ensure the cladding will not exceed exceed its yield stress and that the fuel thermal-mechanical thermal-mechanical design criteria will not be violated during any postulated postulated transient events.
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During reactor reactor power operation. the LHGR of any rod ill power operation, in any fuel bundle alat any axial location shall not exceed h,cation exceed the rated power and rated core flow limits (LHGR e~lch (LHGR*,)s1d ) for each fuel and rod type as a function of fuel rod nodal fLuel anid nod~1 exposure exposure listed in Reference 3:7.
3.7.
The LHGR LHGR limits for the fuel pin axial locations with no gadolinium and maximum maximum gadolinium concentration gadolinium concentration listed in Reference expected to operate near the LHGR Reference 3.7 are expected limits.
There are also fuel pins with axial locations that have gadolinium concentrations that are gadolinium concentrations less than the maximum concentration concentration anywhere anywhere in the bundle. The LHGR LHGR limits for these axial locations locations range uniformly uniformly between the case of no gadolinium gadolinium and the most limiting gadolinium gadolinium concentration.
concentration. .
For other than rated power and flow conditions (below 23% 23% core thermal power thermal calculation is not required),
limit calculation required), the applicable applicable limiting LHGR LHGR values for each fuel type is the smaller of the power and flow dependent dependent LHGR limits multiplied multiplied by the applicable applicable power and flow adjustment factor or the LHGR LHGR limit multiplied multiplied by 0.82 when in single single loop operation.
LHGR limit = = MIN (LHGR (P), LHGR LHGR (F)).
(F>>.
Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent LHGR limit adjustment adjustment factor, LHGRFAC LHGRFAC (P), shown in Figure 2.3-1 and the LHGR LHGR~td.std .
LHGR (P) = = LHGRFAC LHGRFAC (P) x LHGR LHGR,ld std The flow-dependent LHGR limit, LHGR LHGR (F), is the product of the LHGR flow dependent dependent LHGR limit adjustment adjustment factor, LHGRFAC LHGRFAC (F), (F), shown in Figure 2.3-2 and the LHGRs'td.
LHGR std .
LHGR (F) (F) == LHGRFAC LHGRFAC (F) x LHGRstd 2.4. Thermal-Hydraulic Thermal-Hydraulic Stability Exclusion Exclusion Region (T.S. 3.6.1)
Region (T.S. 3.6.J) predominant oscillation mode is core-wide based on decay ratios at the most limiting The predominant point on the powerlflow power/flow map. Normal plant operationoperation is not allowed inside the bounds of of the exclusion region defined in Figure 2.4-1. Operation inside of the exclusion region region may result in a thermal-hydraulic thermal-hydraulic oscillation. Intentional Intentional operation operation within the buffer allowed unless the Sta~ility region is not allowed Stability Monitor Monitor is operable. Otherwise, the buffer region is considered considered part of the exclusion exclusion region (Reference (Reference 3.6).
The coordinates of the Exclusion Exclusion Region Region are as follows:
Point [ Power (%)
(%) Flow Flow(%)(%)
A A 57.9 57.9 41.7 41.7 B
B 37.5 31.3 31.3 Cycle 28 Cycle 28 COLR COLR VJermont Yankee Nuclear Vermont Yankee Nuclear Power Power Station Station R-evision R.evision 00 Page 55 of Page 16 of !6
fhe Nlodified ShaDe file Modified Shaoe Fui.nction FunctIon equalion equal ion used to generate Ihe Exclusion generate the Exclusion Region boundary boundary is as follows:
is where, P = a core thermal power value on the Exclusion Region boundary boundary (% (% of rated),
W W = the core flow rate corresponding corresponding to power, P, on the Exclusion Region boundary boundary (% (% of rated),
PA, P A = core thermal power at State Point A (% (% of rated),
PB P B = core thermal power at State Point B (% of rated),
WA W A = core flow rate at State Point A (% (% of rated),
W WB B = core flow rate at State Point B B (% of rated),
The, The. range of validity of the fit is: 31.3% $..%Flow
< %Flow <41.7%
$..41.7%
The coordinates coordinates of the Buffer Region are as follows:
Point [ Power (%)(%) Flow (%)
C 63.8 49.1 D 32.5 31.3 31.3 The Modified Shape Function equation used to generate the Buffer Region Region boundary boundary is as follows:
foHows:
where, P = a core thermal power power value on the Buffer Buffer Zone boundary (% (% of rated),
W W = the core flow rate corresponding corresponding to power, P, on the Buffer Zone boundary (%
on of rated),
Pc = core thermal power at State Point C (% of rated),
C (%
PD =
PD core thermal power at State Point 0 D (% of rated),
WC We = core flow rate at State State Point C (% of rated),
WD W D = core flow rate at State Point D 0 (% of rated),
The range of validity validity of the fit is: 31.3% <%Flow 31.3% $.. <49.1%.
%Flow $..49.1 %.
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1.5.
2.3. Power/Flow Map Power operation, with respect to Core Thermal Power/Total Power/Total Core Flow combinations, combinations, is is allowed allowed within the
[he outlined area of Figure 2.4-1.
2.4-1. This area is bounded by the following lines:
- Minimum Pump Speed Line, Line: This line approximates approximates operation at minimum pump' pump speed. Plant start-up is performed with the recirculation recirculation pumps operating operating at Reactor power level will approximately approximately 20% speed. Reactor approximately follow follow this line during the normal control*
control-rod withdrawal sequence.
- Natural Circulation Circulation Line; The operating state the reactor follows along this line for the normal control rod withdrawal sequence in the absence of recirculation recirculation pump operation.
- Exclusion Region; The exclusion exclusion region is a power/flow powerlflow region where an instability can occur. The boundary boundary for the exclusion exclusion region is established through use of an analysis procedure procedure which is demonstrated demonstrated to be conservative relative to expected operating conditions.
expected operating
- Buffer Buffer Region Boundary; The Buffer Region is determined by adjusting the endpoints of the Exclusion Exclusion Region to meet a 0.65 decay ratio O.R OR increasing increasing the flow on the highest rod line by 5% and decreasing decreasing power on the natural circulation line by 5% if more limiting than the 0.65 by 5% O~65 decay ratio intercepts.
- Rated Rated Power Line and MELLLA Boundary; These lines provide the upper power power limit and operating domain assumed assumed in plant safety analyses.
- ICF Boundary; This line represents represents the highest allowable'analyzed allowable'analyzed core flow. The analysis in Reference 3.4 supports the maximum attainable core flow being 107%
being 107%
of rated core flow.
2.6. Single Loop Operation Operation SLO was not analyzed analyzed for operation operation in the MELLLA MELLLA region. The powerlflow power/flow operating operating condition condition for Single Loop Operation Operation (SLO) is core power less than 1239 MWTh (64.80%CTP),
(64.80%CTP), core flow less than 26.35 M#/hr (54.9%) and maximum rod line less than M#lhr (54.9%)
90% (References 3.3)
(References 3.2 and 3.3)
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2.7.
L7. Rod R.od Block B lock Monitoring Monitoring The The Rod Block Block Monitor Monitor (RBM)
(RBM) control control rod block block functions functions are no longer longer credited credited in in the the Rod Rod Withdrawal Withdrawal Error Error (RWE)
(RWE) Analysis Analysis and and as such, do do not affect affect the the MCPR MCPR Operating Operating Limit. 'The The RBM RBM setpoints setpoints are are based based on on providing providing operational operational flexibility t1exibility in in the MELLLA MELLLA region region (TS Bases Bases 3.2).
3.2). The The rod block block monitor monitor (RBM)
(RBM) setpoint setpoint equation equation maximum maximum value value of N of N for single loop and dual loop operation are listed in Table 2.2-2.
single loop and dual loop operation are listed in Table 2.2-2.
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Table 2.1-1
- 2. 1-l MAPLHGR Limits for Bundle Types:
MAPLHGR GNF2-PIODG2B403-14G6.0-100T2-1S0-T6-3259 GNF2-P I0DG2B403-14G6.0- 100T2-150-T6-3259 GNF2-PII0DG2B404-14GZ-GNF2-P ODG2B404-14GZ-lIOOT2-1S0-T6-3260 00T2-150-T6-3260 GNF2-PlIODG2B403-1 GNF2-P ODG2B403-111G6.0-100T2-150-T6-3261 G6.0-100T2-1S0-T6-3261 GNF2-PIODG2B404-18GZ-100T2-1S0-T6-3262 GNF2-P 10DG2B404-1 8GZ- 100T2-150-T6-3262 MAPLHGR MAPLHGR (kW/ft)
Average A verage Planar Planar Exposure Exposure (GWd/ST) Two Loop Operation Operation Single Single Loop Operation' Operation I o0 13.78 13.78 11.30 11.30 17.52 17.52 13.78 13.78 11.30 11.30 60.78 60.78 7.50 6.15 6.15 63.50 63.50 6.69 5.49 Table Table 2.1-2 2.1-2 MAPLHGR Limits for Bundle Types:
GNF2-P10DG2B387-15GZ- 100T2-150-T6-2977-LUA GNF2-PlODG2B387-15GZ-100T2-150-T6-2977-LUA GE 14-P 1ODNAB383-17G6.0- 100T- 150-T6-2865 GEI4-PlODNAB383-17G6.0-100T-150-T6-2865 GE14-P1ODNAB422-14GZ- 100T- 150-T6-2965 GEI4-PlODNAB422-14GZ-IOOT-150-T6-2965 GE14-P1ODNAB388-15GZ- 100T--150-T6-2968 GEI4-PlODNAB388-15GZ-100T 150-T6-2968 GE14-P 1ODNAB388- 15GZ- 1OOT- 150-T6-2969I GE14-PlODNAB388.;15GZ'-100T-150-T6-2969; GEi4:;.PlODNAB42r~
GEl i6GZ~ 100T-150:.T6.-3084:
4-P 1ODNAB42 1-16GZ- 100T-150:-T6-3084',.'"
GE14~PI0DNAB420"16GZ~100T-150:T6-3085' GE l4-P 1ODNAB420-16GZ- 1OOT- 150-T6-3085 GE14-P1ODNAB388-15G6.0-1OOT-150-T6-3086 GEI4-PlODNAB388-15G6.0-100T-150-T6-3086 GE14-P1ODNAB388- 16GZ- 10OT- 150-T6-3087 GE14-PlODNAB388'-16GZ-100T-150;.T6-3087 MAPLHGR MAPLHGR (kW/ft)
Average Average Planar Exposure (GWd/ST)
(GWdlST) Two Loop Operation Operation Single Loop' Operation' Operation I o
0 12.82 12.82 10.51 19.12 19.12 12.82 12.82 10.51 57.61 8.00 6.56 63.50 63.50 5.00 4.10 4.10 Technical Technical Specification
References:
3.6.G. l a and 3.1l.A.
3.6.G.la 3.11.A.
tMAPLHGR I MAPLHGR for single loop operation operation is obtained obtained by multiplying MAPLHGR MAPLHGR for two loop operation operation by by 0,82.
0.82.
Cycle Cycle 28 COLR 28 COLR Vermont Yankee Nuclear Power Station Revision Revision 0 Page 99 of Page of [6 16
Table
'fable 2.2-1 Onerating Limits Rated MCPR Operating (01 IVICPR)
I imits (OLMCPR)
Rated MCPR Operating Limits(OLMCPR)
Cycle Exposure Two Loop2 Sihgle Single Loop OQtioniFuel TY12e Option/Fuel Type Range Range Operation- . Operation O12eration2 O12eration Option NGE14 A/GE14 o0 to 8,900 MWd/St MWd/St 1.45 1.45 1.46 Beyond Beyond 8,900 MWd/St MWd/St 1.59 1.59 1.60 1.60 A/GNF2 3 Option NGNF2 o0 to 8,900 MWdlSt MWd/St 1.47 1.48 1.48 Beyond 8,900 MWd/St 1.59 1.60 1.60 Option B/GE14 0o to 8,900 MWdlSt MWd/St 1.40 1.41 Beyond 8,900 MWd/St 1.42 1.43 Option B/GNF2 3 0o to 8,900 MWdlSt MWd/St 1.40 1.41 Beyond Beyond 8,900 MWd/St 8,900 MW dlSt 1.49 1.50 1.50 References 3.6.
Source: References 1 The MCPR operating operating limit is increased by 0.01 for single loop operation.
2 The two loop MCPR operating limits bound ICF operation operation throughout the cycle.
3 The GNF2 MCPR operating limits include Compensatory include Compensatory Measures to bound the effects of potentially bent GNF2 spacer flow wings (Reference (Reference 3.6).
Table 2.2-2 2*.2-2 REM Setpoint 44 .
RBM Setpoint Dual Loop Operation Operation Maximum Maximum Value of "N"in "N" in RBM Setpoint Equation Equation - 62.
Single Loop Operation Maximum Value of "N" "N" in RBM Setpoint Equation - 68.
Reference 3.8 Source: Reference Technical Technical Specification
References:
References:
Table 3.2.5.
4 The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in Table Table 3.2.5 of the Technical Technical Specifications.
Specifications.
Cycle 28 COLR Vermont Yankee Nuclear Power Station Vermont Yallkee Revision 0 PagŽe 100of r}C1gc 16 of 16
Figure 2.2-1 Figure Dependent K (P) / MCPR (P) Limits Power Dependent (Technical Specification Reference Reference 3.11.C) 3.11 .C) 1-*----*----------*----*--------*-**----***------*-*----****-*------*-------*-**----*----------1 I 3.00 3.00 [ ___ ,0 _ -._, ----r----,--*-,----,---,-----,.----r--.---,--- rT- - -r--- .-,-- - ' - - -..- ' - - - ' - - -
I I : : : : : : : : : ~CPA(P) J-o.- MCPR(P) for <25%P, ~~-;60%FI >60%F 2.75 2.....;-
i.--,.- ;I .;. :-- *-~----:*---r- ;-.l~
]- --A-MCPA(P)MCPR(P)for for <25%,
<25%, :s:60%F t <60%F l ( I I t ( I 2.50
\ ::'
I'
- ~K(P)for~25%P 2--o--K(P) for->25%P I'* '1--
I 2.25 . ,. - -I, .,
Q.
'l I a:CLt 2.00 .. - -f *1* .,.
a.
0 *1
- 2 , I Q. 1.75 I.
,I. J .
~
1.500 . l ...... I . i ... r Ii . . . i.. . .. i .
1.50 . '.
- 0. 1.25
.75-It
- . 1.-
. ' .' I..I. -
1.00. , j 1.00 "
I I I. Ir I I I I 0.75+--~-~--r--~-~--~-~-~-~--~-_r-~--~-~-~-~
20 25 30 35 40 45 50 55 60 65 70 75 80 80 85 85 90 90 95 95 100 100 Power (% Rated)
(% Rated)
Operating Operating Limit MCPR(PI MCPR(P) ;= K(P) K(P) ** Operating Operating Limit MCPR(100)
Limit MCPR(lOO)
For PP << 23%, 23%, No No Thermal Limits Required Required P-Bypass ;= 25% 25% Rated Power Power MCPR(P) limits are based on a 1.09 SLMCPR MCPR(P) SLMCPR MCPR(P)
MCPR(P) <25%P, >60%F for <25%P, >60%F POWER LIMIT EQUATIONS EOUATIONS PWER LIM70 2.T70 I
23.0 2.70 I 25.0 2.58 23% ~* P < 25%:
For 23% 11CPR (P)
MCPR(P) 6.00E-02(25.0 -- P)
= 2.58+ 6.O0E-02(25.0 PI MCPR(P)
MCPR(P) <25%P. S60%F for <25%P, 560%F POWER J LIMIT LIMIT EOUATIONS EQUATIONS I 23.0
_25.0 25.0 I
, 2.24 2.15 2.15 For 23% SS P For 23% P < 25%:
< 25%: MCPR(P)
2.15+ 4.50E-02(25.0 4.50E-02(25.0 -- P)P)
(P)
K(P)
K for for Ž25%P 2:25%P POWER LIMIT EQUATIONS EQUATIONS 25.0 1.55 45.0 1.28 1.28 25% 5S P For 25%
For P << 45%:
45%: MCPR(P)
MCPR (P) = 1.281,28 + 1.35E-02(45.0 .- PI
+ 1.35E-02(45.0 P) 100.0 1.00 For 45%
45% S s P << 100%:
100%: MCPR{P) = 1.00
!1CPRIPI 1,00 + 5.09E-O)(100.0 -- P)
+ 5.09E-03(100.0 P)
Cycle 28 COLR Vermont VermOlll Yankee Nuclear Power Starion Station Revision 0 Revision 0 iaae of I16 Page II II 01' 6
Figure Figure 2.2-2 Flow Dependent MCPR Operating Operating Limit MCPR M/CPR (F)
(Technical (Technical Specification Reference 3.
Specification Reference 3.11 .C)
I I.C) 1.80 1.80 1-
-- a- Max Runout Flow = 109.5%
1.70 1.70 1.60 efl.x:
a.
0 1.50 -
1.50
- e 1.40 1.30 1.20 1.20 1.10 1.10 20 30 40 50 50 60 70 80 80 90 .100..
.100 110 120 120 Flow (%
Flow (%Rated)
Rated)
MCPR(F) limits are based MCPR(F) based on aa 1.09 1,09 SLMCPR Max Runout Flow - 109 5%
109.5%
FLOW FLOW LIMIT LIMIT EQUATIONS 30.0 1. 60 1.60 30% S< F ~!9 109.5%:
For 30% HCPR(F)
MCPR(F) = MAXIl.25.
MAX(I.25, -0.622'FIl00 1.7865
-0.622-F/100 + 1.7865 86.3 1.25
- 1. 25 109.5 1.25
- 1. 25 Cycle 28 :28 COLR Vermont Yankee Yallket:: Nuclear Power Station Sration Revision 0 paigýe 12 FJ-:u?;t' I oof1"16 16
Fiigure 2.3-1 Figure 2.3-i Power Dependent LHGRFAC power LHGRFAC (P) Multiplier Multiplier (Technical (Technical Specification Specification Reference Reference 3.11.B) 3.11.B) 11.20
.20 ,..-----,--*--r---,---,----T----,.----,--*-*---,------r--,-
I I .,
I 1.00 1.00 ~
, I IIn
-I 0.80 I-I n I I 0
0 LHGF-(P for. ?25%P cc0.60 LL ,
a: 0.60 I 0-0 J:
-J
..J I
20 50 0.55 0 5 6 7 7 8 85, Io 9 0 0.40 0040 Poe (%Rtd -I.
-<:I- LHGRFAC(P) for <25%P, >60%F 0.20 0.20 - - - .., - - - - - - r - - - ..., - - - -< - - 1" - - - - - - r -
I I I --lr- LHGRFAC(P) for <25%, ::;60%F
->- Powe)
LHGRFAC(P) (o for R25%2:25%P P 0.00 +----.;..----i---'--i-----i---.;...--r-.--..---.;...----;.--...;---i------;.--..;--.....;--.......;.------J 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)
LHGR-(P) = LHGRFAC(P)
LHGR(P) LHGRFAC(P)
- LHGRStd . LHGRstd For P < 23%,23%, No No Thermal Thermal Limits Limits Required P-Bypass P-Bypass = = 25%
25% Rated Power Power LHGRFAC(P)
LHGRFAC(P) for <25%P,
<25%P, >60%F POWER POWER ýLIMITEQAIN LIMIT I;;Ql.1M:IQNa 23.0 0.560 0.560 25.0 0.568 0.568 For 23% 23% ~* P < 25%: LHGRFAC(P)
LHGRFAC(P) = 0.568 + 4.00E-03(P 4.00B-03(P - 25.0) 25.0)
LHGRFAC(P) for LHGRFAC(P) for <25%P, S60%F -60%F POWER POWER -LIMIT LIMIT !:;QL1AI1 QI'lS 23.0 0.598 0.598 23.0 20.0 0.598 For 23% ! P < 25%: LHGRFAC(P) = 0.608 25.0 0.608 For 23% ,; P < 25%: LHGRFAC(P) 0.608 +
- 5.00E-03)P 5.00B-03(P - 25.0)
LHGRFAC(P)
LHGRFAC(P) for 2:25%P 225%P POWER LIMIT !:;QUlIrIQNS ZEUATIONS 25.0 0.608 100.0 100.0 1.000 1.000 For 25% 25% ,;* P < 100%: LHGRFAC(P) = 1.000 LHGRFACIP) 1.000 *+ 5.23E-03(P 5.23E-03(p - 100.0)
Cycle 28 COLR Vermont Vermont Yankee Nuclear Nuclear Power Station Revision 0 Revision Page 13 of 16 f>a!:?e I ()
`igure 2.3-2 Figure 2.3-2
_LHGR LI-IGR Flow Factor LHGRFAC LHGRFAC (F) (F)
(Technical Specification Reference 3.1l.B) 3.1 I.B)
I-----.-.------.-.. -.~-------------*-*------- . ------------------------------.--------.. ----.---.-.-----~
1.20 -,------,-----...--------r-----r-.-----,--_--..........,...-----.,.-----;-----,----
1_20 -~-
~1 1.00 1.00- - - - - - - - L - - *.
L ______ J _ _ _ _ _ _ J2. _ _ _ _ _ _ .J - __ - __ -' -c..C~-'---'-----...L...----O-I F 0.80 - ------,-------r-I-
~
cc
- u. _ 1 _ _ _ _ _ _ .1----~
.1 _ _ _ _ _ _ ...1 _ _ _ _ _ _ ..J _ _ _ _ _ _ ..J _ _ _ _ _ _ _ 1__ _
___ 1__ ** ____
L ______ _
a: 0.60-U-" 0.60 - - .1.
CJ C,.
- I:
...J F F 0.40 4 r - - - - - - T - - - - - - j - - - - - - ,~1- - - - - - "I - - - - - - ..,
2 - - - - - - "-)- - - - - - * - - - - - - r - - - - - -
F F
- F
______ L ______ 1 ______ .1 _ _ _ _ _ _ J _______I _______ 1 _ _ _ _ _ _ _ 1 _ _ _ _ _ _ _ 1 _ _ _ _ _ _ _ 1_ _ _ _ _ _ _
0.20 + - I. - -
I I
\ \
A I I I I~
--o--Max Runout Flow Max Runout 109.5% I Flow== 109.5%
0.00 0.00+--~_.----~---_4~---~----~---~-----,----~------~--~
20 20 30 40 50 50 60 70 80 90 100 110 120 FRow FlOw (% (% Rated)
Rated)
LHGR(F) =
LHGRIF) = LHGRFAC(F)
LHGRFACIF) ** LHGRstdLHGRstd Max Runout Max Runout Flow - 109:5%
Flow -= 109 '5%
FLOW FLOW LIMIT EQUATIONS EAO 30.0 0.54 0.54 For 30% 30% *~ F S ~ 109.5%:
109.5%: LHGRFAC(F MIN(I.00, LHGRFACIF) = MINI1.OO. [A(F)*F/100+8(F)])
[AIF)*F/l00+BIF)])
92.6 82.6 1.00
- 1. 00 AIF) = 0.974 A) 0.874 109.5 109.5 1.00
- 1. 00 B(F) =
ElF) = 0.278 0.278 Cycle 28 28 COLR COLR Vermont Vermont Yankee Yankee Nuclear Nuclear Power Power Stationi Station Revision 0 Revision Page Page 14 of 16
Figure Figure 2.4-1 Limits of Power/FlowOperation Power/Flow Operation (Technical Specification Reference 3.6.1) 3.6.J)
CYC~E CYCLE POWER/FLOW MAP 28 POWERIFLOW 110 110 -----~ ---;-----------:----
f I , ' Rated ~owe, Line
, , I I I ,
100 I , I I I ,
~ I I :
90
~
'0 80 80 Q)
-o (U
cr: 7070
~ I
'- I Q) 60 " ICE Boundary.
~
o0 11.
Cii E
IL 50 \
Q)
~ 40
~
o0 o0- 30 30 I I Minimum Pump
, SpeedUne I
20 I" I
I I 10 - 1 " "" -" ","""
Mifllmum PO'MI' Une 0o I o0 10 20 30 40 50 60 60 70 70 80 90 100 100 110 110 Core Flow (% Rated)
Cycle 28 COLR VXermnont Vc:rmont Yankee Yankee Nuclear Nuclear Power Power Station Station Revision 0 iPzt P:lgee t515 of of 16 16
3.U k.0 REFERENCES
- 3. I.1.
- 3. Report, General Electric, General Electric Standard Application for Reactor Fuel (GESTAR iI),II), NEDE-24011-P-A-16, NEDE-240 I-P-A- 16, October October-2007' 2007 (Proprietary).
3.2. Report, GE, Vermont Yankee Nuclear Power Station Station APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),
. Specifications/Maximum (ARTS/MELLLA),
NEDC-33089P, March 2003 (Proprietary).
3.3. Incorporated Vermont Yankee Nuclear Power Report, GE, Entergy Nuclear Operation IncorporatedVermont Station Extended Power Uprate - Task T0407 ~- ECCS-LOCA SAFER/GESTR, SAFER/GESTR, GE-NE-0000-0015-5477-01, September 2004 (Proprietary)
GE-NE-0000-0015-5477-01, 3.4. Report, GE, Vermont Yankee Yankee Nuclear Power Station Increased Core Flow Analysis, NEDC-32791P, February 1999 (Proprietary).
3.5.
3.5. Letter, Global Nuclear Fuels, William H. Hetzel (GNF)to (GNF) to Dave Mannai (VYNPC),
(VYNPC),
Vermont Vermont Yankee Option B Licensing Basis, WHV: 2001-023,, November 2001-023,.November 9, 2001.
9,2001.
3.6. Report, Global Nuclear Fuels, Supplemental Supplemental Reload Licensing Report for Vermont 0000-0100-8140-SRLR, Rev. 2, May Yankee Nuclear Power Station Reload 27 Cycle 28, 0000-0100-8140-SRLR.
(ECH-NE- 10-00006).
2010 (ECH-NE-1O-00006).
3.7. Report, Global Nuclear Fuels, FuelFuel Bundle Information Report for Vermont Vermont Yankee Nuclear Power Station Reload 27 Cycle 28, 0000-0100-8140-FBIR, 0000-0100-8140-FBIR, Rev. 0, February 2010 (Proprietary)
(Proprietary) (ECH-NE- 10-00008).
(ECH-NE-1O-00008).
3.8. VYDC 2003-015, ARTS/MELLLA Implementation.
2003-015, ARTS/MELLLA Implementation; 3.9. Report; GE, Vermont Report;GE, Vermont Yankee Station Single-Loop Yankee Nuclear Power Station Single Loop Operation, NEDO-30060, February 1983. 1983.
3.10. Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations,Operations, Inc. Docket No. 50-271 Vermont Yankee 50-271 Vermont Yankee Nuclear Power Station Amendment Amendment to Facility Operating Operating License License Amendment Amendment No. 229 License License No. DPR-28, Extended Extended Power Up Uprate rate Amendment, Amendment, March 2006.
3.11.
3.11. Report, GEH, Vermont YankeeYankee Nuclear Nuclear Power Station Station GNF2 ECCS-LOCA Evaluation, ECCS-LOCA Evaluation, 0000-0100-8613-RO, December 0000-0100-8613-RO, December 2009 (ECH-NE- 10-00001)
(ECH-NE-lO-OOOOl)
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