|
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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20217H3631999-10-14014 October 1999
Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su
ML20210Q9931999-07-31031 July 1999
Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud
ML20154L0691998-10-14014 October 1998
COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy
ML20216A8971998-05-0606 May 1998
Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2
ML20148J8351997-05-31031 May 1997
COLR North Anna Unit 1 Cycle 13 Pattern Og
ML20129F8591996-10-21021 October 1996
COLR North Anna 2 Cycle 12 Pattern Cv, Rev 0
ML20112E2341996-04-30030 April 1996
Rev 0 to NE-1068, North Anna Unit 1,Cycle 11 Core Performance Rept, for Apr 1996
ML20107D2231996-02-29029 February 1996
COLR North Anna 1 Cycle 12 Pattern Bl, Rev 0
ML20107K1141995-05-31031 May 1995
Rev 0 of COLR North Anna 2 Cycle 11 Pattern Um
ML20084G9211995-05-12012 May 1995
Rev 0 to NE-1024, North Anna Unit 2,Cycle 10 Core Performance Rept, Dtd May 1995
ML20078P9611994-11-30030 November 1994
Cycle 10 Core Performance Rept
ML20076J1461994-09-30030 September 1994
Rev 0 to COLR North Anna Cycle 11 Pattern Bw
ML18153B3851993-11-30030 November 1993
Reload Nuclear Design Methodology.
ML20058F1311993-11-0505 November 1993
Rev 0 to North Anna Unit 2,Cycle 9 Core Performance Rept
ML20059G8951993-10-31031 October 1993
COLR for North Anna 2 Cycle 10 Pattern Re, Rev 1
ML20101U1881992-06-24024 June 1992
Rev 0 to NE-895, North Anna Unit 2,Cycle 9 Startup Physics Tests Rept
ML20101J5871992-05-31031 May 1992
Rev 0 to Technical Rept NE-876, North Anna Unit 2,Cycle 8 Core Performance Rept
ML20096C6161992-04-30030 April 1992
Rev 0 to North Anna 2,Cycle 9 Loading Pattern ET Core Operating Limits Rept
ML20094K3351992-02-29029 February 1992
Core Operating Limits Rept
ML20077E4111991-05-31031 May 1991
Rev 0 to Technical Rept NE-838, North Anna Unit1,Cycle 8 Core Performance Rept
ML20066F9541991-01-18018 January 1991
1,Cycle 9,Pattern R8 Core Surveillance Rept
ML20028H8601991-01-16016 January 1991
Rev 0 to NE-817, North Anna Unit 2,Cycle 8 Startup Physics Test Rept. W/910128 Ltr
ML20028H8621991-01-0909 January 1991
Rev 0 to NE-799, North Anna Unit 2,Cycle 7 Core Performance Rept. W/910128 Ltr
ML20058F3841990-10-30030 October 1990
Revised Proposed Changes to Core Operating Limits Repts
ML20058C1661990-10-25025 October 1990
Core Surveillance Rept for North Anna 2 Cycle 8 Pattern Qf
ML20064A8731990-09-11011 September 1990
Cycle 8 Core Surveillance Rept
ML20043G1921990-06-0808 June 1990
Core Surveillance Rept for North Anna 2,Cycle 7 W/Extended License Burnup Limit.
ML20012E8311990-03-26026 March 1990
Cycle 8 Core Operating Limits Rept.
ML20012E8321990-03-26026 March 1990
Cycle 7 Core Operating Limits Rept.
ML20247H0291989-08-31031 August 1989
Cycle 7 Core Performance Rept
ML20245C4931989-06-0505 June 1989
Cycle 8 Relaxed Power Distribution Control Pattern - Core Surveillance Rept
ML20245L0931989-04-30030 April 1989
Rev 0 to North Anna Unit 2 Cycle 6 Core Performance Rept
ML18149A4301986-09-30030 September 1986
Rev 1-A to Reload Nuclear Design Methodology.
ML20155K6461986-05-22022 May 1986
Rev 1 to North Anna Unit 2,Cycle 5,Relaxed Power Distribution Control Core Surveillance Rept for FQ=2.20
ML20155F5721986-03-31031 March 1986
Cycle 4 Core Performance Rept
ML20151N5671985-11-30030 November 1985
Cycle 5 Core Performance Rept
ML20135H9491985-08-31031 August 1985
Rev 1 to Reload Nuclear Design Methodology
ML20069K3671983-04-30030 April 1983
Cycle 2 Core Performance Rept
1999-07-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999
Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised
ML20217H3631999-10-14014 October 1999
Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su
ML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML20212J9251999-10-0101 October 1999
Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant
ML20217D6851999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With
ML20211N2611999-09-0808 September 1999
Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable
ML20211J2561999-08-31031 August 1999
Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2
ML20216E5011999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with
ML20211J2421999-08-31031 August 1999
Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2
ML20210T0791999-08-13013 August 1999
Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable
ML20210S1411999-07-31031 July 1999
Monthly Operating Repts for July 1999 for North Anna Power Station.With
ML20210Q9931999-07-31031 July 1999
Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud
ML20209E5641999-06-30030 June 1999
Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With
ML20195G1901999-05-31031 May 1999
Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with
ML20206L4831999-05-10010 May 1999
SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping
ML20206Q6671999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With
ML20205S0391999-04-21021 April 1999
SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii)
ML20205K3041999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With
ML20207K5921999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With
ML20207E1731999-02-18018 February 1999
Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year
ML20205A0241998-12-31031 December 1998
Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With
ML20199C8781998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With
ML20198H9541998-12-0303 December 1998
Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant
ML20198J5561998-12-0303 December 1998
ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps
ML20197G8551998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With
ML20196G1381998-11-0303 November 1998
Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit
ML20195D0571998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With
ML20154L0691998-10-14014 October 1998
COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy
ML20155J6911998-10-0909 October 1998
Staff Response to Tasking Memorandum & Stakeholder Concerns
ML20154H4001998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With
ML20151X8011998-09-10010 September 1998
Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section
ML20151W4711998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With
ML20237A4341998-07-31031 July 1998
Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2
ML20236V1251998-07-14014 July 1998
ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis
ML20236K5531998-07-0707 July 1998
SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment
ML20236M3381998-06-30030 June 1998
Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2
ML20248M1011998-05-31031 May 1998
Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2
ML20248C8831998-05-29029 May 1998
SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program
ML20247K9281998-05-15015 May 1998
Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary
ML20216A8971998-05-0606 May 1998
Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2
ML20247F4441998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2
ML20217B5321998-04-20020 April 1998
Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs
ML20217H9611998-04-0707 April 1998
Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed
ML20216B1891998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2
ML20216E8801998-03-0606 March 1998
Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii)
ML20216E2561998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2
ML20199J6431998-02-0202 February 1998
Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218
ML20202D5811998-01-31031 January 1998
Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2
ML20198S7571998-01-15015 January 1998
Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping
ML20198P1351997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2
1999-09-08
[Table view] |
Text
. .
t I
I CORE OPERATING LIMITS REPORT (COLR)
I NORTH ANNA POWER STATION UNIT 2 CYCLE 13 PATTERN UD REVISION 1 l
JULY 1999 l
~ ~
9908170007 990812 PDR ADOCK 05000339 P PDR ;
Virginia Electric and Power Company i i
N2C13/UD COLR Rev 1 Page 1
V: s N2C13 CORE OPERATING LIMITS REPORT 1.O INTRODUCTION This revision of the Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 13 is being prepared in accordance with Technical Specification (TS) 6.9.1.7. The Technical Specifications affected by this report are listed below:
3/4.1.1.4 Moderator Temperature Coefficient I 3/4.1.3.5 Shutdown Bank Insertion Limit 3/4.1.3.6 Control Bank Insertion Limits ,
-3/4.2.1 Axial Flux Difference 1 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor and Power Factor Multiplier The cycle-specific parameter limits for North Anna 2 Cycle 13 for the specifications listed above are provided on the following pages, and were developed using the NRC-approved methodologies specified in TS 6.9.1.7.
The heat flux hot channel factor surveillance specification 4~.-2.2.2 requires the application of a cycle dependent function, N(z) to the measured FQ(z) before comparing _it to the limit. N(z)
- accounts for power distribution transients encountered during normal operation. As function N(z) is dependent on the predicted i equilibrium FQ(z) and is sensitive to the axial power i distribution, it is necessary to generate this function using the actual EOC burnup distribution from the previous cycle. The N(z) function, generated after the shutdown of Cycle 12 is provided as Table 1. This revision of the COLR specifies a revised limit for FQ(z) that is applicable to EOC coastdown operation. All other-i COLR parameters remain unchanged.
l N2C13/UD COLR Rev 1 Page 2 Y
2.O OPERATING LIMITS-2.1 Moderator Temperature coefficient (TS 3/4.1.1.4) 2.1.1 The moderator temperature coefficient (MTC) limits are:
The BOC/ARO-MTC shall be less positive than or equal to
+0.6E-4 Ak/k/ U F below 70 percent of RATED THERMAL POWER.
The BOC/ARO-MTC shall be less positive than or equal to 0 0
(zero) ~ Ak/k/ F at or above 70 percent of RATED THERMAL POWER.
The EOC/ARO/RTP-MTC shall be less negative than -5.0E-4 0
Ak/k/ F.
I 2.1.2 The MTC surveillance limits are- I The 300 ppm /ARO/RTP-MTC should be less negative than or equal to -4. 0E-4 Ak/k/ F.
The 60 ppm /ARO/RTP-MTC should be less negative than or equal to -4.7E-04 Ak/k/ F.
where: BOC - Beginning of Cycle ARO - All Rods Out '
EOC End of Cycle RTP - RATED THERMAL POWER 2.2 Shutdown Bank Invertion Limit (TS 3/4.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to 227 steps. l I
2.3 control Bank Insertion Limits (TS 3/4.1.3.6) 2.3.1 The control rod banks shall be limited in physical insertion as shown in Figure A-1.
N2C13/UD COLR Rev 1 Page 3
~
[--
\
2.4 Axial Flux Difference (TS 3/4.2.1) 2.4.1 The axial flux difference limits are provided in Figure A-2.
2.5 Heat Flux Hot Channel Factor-FQ(z) (TS 3/4.2.2)
The change in the FQ limit for temperature coastdown is accommodated by defining a variable quantity, FQum as indicated below. Then, the following expressions can be used for both normal operation and Tavg coastdown regimes.
FQum = 2.19, for normal operation at full power; FQu = 2.15, for EOC temperature coastdown.
2.5.1 The Fg(x) limits are:
FQum Fg(z) $ ---
Fg(z) $ 2*FQum
1 THERMAL POWER where: P = ------------------- , and RATED THERMAL POWER K(z) is provided in Figure A-3 2.5.2 The Fg(z) surveillance limits ares i FQum K(z)
F g(z)M $ --- * ---- for P > 0.5 l
l P N(z) 1
- N2C13/UD COLR Rev 1 Page 4 l
l l
l
F.
K(z)
Fg(z)M $ 2*FQum * ---- for P $ 0.5 N(z)
THERMAL POWER where: P = ------------------- ,
RATED THERMAL POWER K(z) is provided in Figure A-3, and N(z) is a non-equilibrium multiplier on Fg(z)M to account for power distribution transients during normal operation, provided in Table A-1. The top and bottom 15% of the core is excluded per TS 4.2.2.2.G.
2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(N) and Power Factor Multiplier (TS 3/4.2.3)
FAH(N) $ 1.49*{1 + 0.3*(1 - P))
THERMAL POWER where: P = ------------------- -
RATED THERMAL POWER i
i N2C13/UD COLR Rev 1 Page 5
Table A-1 N2C13 NORMAL OPERATION N(zTs Height 0 to 1000 1000 to 3000 3000 to 5000 5000 to 7000 7000 to 9000 9000 to 17700 17/00 to EOC Node (feet) MWD /MTU MWD /MTU MWD /MTU MWD /MTU MWD /MTU MWD /MTU MWD /MTU 10 10.2 1.159 1.159 1.159 1.153 1.153 1.153 1.118 11 10.0 1.158 1.158 1.158 1.152 1.152 1.152 1.119 12 9.8 1.155 1.155 1.155 1.150 1.150 1.150 1.125 13 9.6 __ 1.155 1.155 _ 1.155 _ _1.149 1.149 1.149 1.134 14 9.4 1.156 1.156 1.156 1.149 1.149 1.149 1.141 15 9.2 1.162 1.162 1.162 1.153 1.153 1.153 1.149 16 9.0 1.171 . 1.171 1.171 1.162 1.162 1.162 1.157 17 8.8 1.181 1.181 _ 1.181 _ 1.173 _1.173 1.173 1.166 18 8.6 1.188 1.188 1.188 1.181 1.181 1.180 1.177 19 8.4 1.193 l 1.193' 1.193 ~
1.187 1.187 1.187 1.187 20 8.2 1.197 1.197 1.197 1.193 1.193 1.196 1.196 21 8.0 1.200 1.200 _ _1.200 1.196 1.196 1.203 1.203 l 22 7.8 1.203 1.203 1.203 1.198 1.198 1.209 1.209 23 7.6 1.205 1.205 1.205 1.198 1.198 1.213 1.213 4 24 7.4 1.205 1.205 1.205 1.197 1.197 1.217 1.217 25 7.2 1.204 1.204 1.204 1.194 1.194 1.219 1.219 26 7.0 1.200 1.200 1.200 1.190 1.190 1.218 1.218 27 6.8 1.196 1.196 1.196 1.184 1.184 1.217 1.217 28 6.6 1.190 1.190 1.190 1.177 1.177 1.214 1.214 29 6.4 1.183 1.183 1.183 1.170 1.170 1.210 1.210 30 6.2 1.172 1.172 1.172 1.162 1.162 1.202 1.202 31 6.0 1.162 1.162 1.162 1.154 1.154 1.195 1.195 32 5.8 1.149 1.149 1.149 1.144 1.144 1.184 1.184 33 5.6 1.135 1.135 1.135 1.132 1.132 1.173 1.173 34 5.4 1.122 1.122 1.122 1.119 1.119 1.156 1.156 ;
35 5.2 1.111 1.111 1.111 1.106 1.106 1.135 1.135 36 5.0 1.105 1.105 1.105 1.098 1.098 1.119 1.119 37 4.8 1.104 1.104 1.104 1.096 1.096 1.113 1.113 38 4.6 1.107 1.107 1.107 1.098 1.098 1.115 1.115 39 4.4 1.113 1.113 1.113 1.100 1.100 1.118 1.118 40 4.2 1.118 1.118 1.118 1.104 1.104 1.121 1.121 41 4.0 1.122 _ 1.122 1.122 . 1.109 _ 1.109 1.123 _
1.123 42 3.8 1.126 1.126 1.126 1.114 1.114 1.124 1.124 43 3.6 1.131 1.131 1.131 1.121 1.121 1.127 1.127 44 3.4 , 1.136 1.136 1.136 1.130 1.130 1.131 1.130 45 3.2 1.143 1.143 1.143 ._ 1.140 1.140 1.140 1.138 46 3.0 1.149 1.149 1.150 1.150 1.150 1.151 1.150 47 2.8 1.157 1.157 1.159 1.159 1.159 1.166 1.166 48 2.6 1.166 1.166 1.167 1.168 1.168 1.178 1.178 49 2.4 1.175 1.175 1.176 1.176 1.176 1.191 1.191 50 2.2 1.183 1.183 1.184 1.184 1.184 1.203 1.203 51 2.0 1.190 1.190 1.191 1.191 1.191 1.213 1.213 52 1.8 1.197 1.197 1.198 1.198 1.198 1.223 1.223 N2C13/UD COLR Rev 1 Page 6
4
/ (0.534, 227) 220 -
Fully Wd position = 227 s".eps 210 -- -
200 / (1.0,5)
C-BAbK 190 -
180 170 / - - - -
160 - - - -
y 150
/
}. 140 - ---
lii 130 -- - - - - - - - -
j120 "(0,118
- '~~~
E !D-BANK g 110 -- --- - - - - -
o.
g100 - - - - -
j go .__ _ _ _ ._ .._ _ _.
80 -- - - - - - -
70 - - - - -
60 -- -- -- - - - - - -
50 -
40 -- ----
30 --'--
20 --
10 -- - ---
0 l 0) 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power i
N2C13/UD COLR Rev 1 Page 7
Figure A-2 N2C13 Axial Flux Difference Limits 120 110 - - ----
(-12, 100) (+Q,100)
' Unacceptable Cheratidi Unacceptable bperalion 90 ___
80 ----- - - - - - - - - - - - - - -
g i Acceptabe Operation a 70 --- - - ---
1 60
] - -- - - - - - -- - - - - - - --- - --
is e
I o
50 -- - - - - - - - - - - - - - -- - - - - - -- ---
!8 ( 27. 50l (+20, 50) i a
( 40 - -- - - - ----- - --
30 ---- ---- --- - --- - - - - - - - - - - - - -
l 20 -- -- - --
10 - -- - - -
0
-30 -20 -10 0 10 20 30 Percent Flux Difference (Delta-l)
N2C13/UD COLR Rev 1 Page 8
1 i
9 Figure A-3 K(Z)- Normalked FQ as a Function of Core Height 1.2 1.1 - - - - - -
L6,1.0) 1.0 , - - - -
0.9 --
12l .925)~
0.8 - - - -
^
N k 0.7 -- - - - - --
O N
a j 0.6 - - - - - - ---
oc O
Z .
N n.s --- --- _-- - - - - - . . - - . . - -- - - - -.
x:
0.4 - -- ----- - - ------ - - -
0.3 -- --- --- - - - -- --- ---- - - -
0.2 - - -- -- -
l 0.1 -
0.0 l 0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (PT) l N2C13/UD COLR Rev 1 Page 9 l-
