RNP-RA/04-0006, Transmittal of Core Operating Limits Report for Cycle 22
| ML040160599 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/07/2004 |
| From: | Baucom C Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/04-0006 | |
| Download: ML040160599 (14) | |
Text
I a40 Progress Energy Serial: RNP-RA/04-0006 JAN 0 7 2004 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 TRANSMfTAL OF CORE OPERATING LIMITS REPORT Ladies and Gentlemen:
In accordance with Technical Specifications 5.6.5.d, Progress Energy Carolinas, Inc. (PEC), is transmitting the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Core Operating Limits Report (COLR) for Cycle 22.
PEC recently discovered that, due to an administrative oversight, the attached COLR was not transmitted to the NRC upon issuance on November 4, 2002. There have been no mid-cycle revisions to the COLR during Cycle 22. The Cycle 23 COLR is expected to be transmitted to the NRC in approximately three months.
If you have any questions concerning this matter, please contact me.
Sincerely, 621') x3a4--V C. T. Baucom Supervisor - Licensing/Regulatory Programs RAC/rac Attachment c: L. A. Reyes, NRC, Region II NRC Resident Inspector, HBRSEP C. P. Patel, NRC, NRR Progress Energy Carolinas. Inc.
AC)o I Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC29550
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0006 13 pages including cover page H. B. ROBINSON STEAM ELECTRIC PLANT (IIBRSEP), UNIT NO. 2 CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Note: This report is Attachment 7.1 to HBRSEP, Unit No. 2, Fuel Management Procedure (FMP)-001
4 ATTACHMENT 7.1 Page 1 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 1.0 OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for HBRSEP Unit No. 2, Cycle 22 has been prepared per EC 47804 in accordance with the requirements of ITS 5.6.5.
The Improved Technical Specifications affected by this report and the methodologies used for the various parameters are listed below.
ITS Applicable Methodology Parameter Reference (Section 3.0 Number)
MTC 3.1.3 1, 2,4,15,18,19,22 Shutdown Bank RILs 3.1.5 1, 2,4, 8, 15, 18, 19, 22 Control Bank RILs 3.1.6 1, 2, 4, 8,15, 18,19, 22 F0 Y(Z) 3.2.1,3.2.3 1,2,5,6,7,8,11, 12,13, 14, 15,17, 18,19, 21, 22 FAH 3.2.2, 3.2.3 1,2,3,4,5,6,7,9,10, 11, 12, 13, 14, 15, 17, 18, 19, 20, 21, 22 AFD 3.2.1, 3.2.3 1, 2, 6, 7, 12, 13,14, 15, 16, 18,19,21,22 Shutdown Margin Requirements 3.1.1, 3.4.5, 3.4.6 1, 2, 4, 8,15, 18, 19, 22 Refueling Boron Requirements 3.9.1 1, 2, 4, 8, 18, 19, 22 COLR 5.6.5 None FMP-001 I Rev. 16 l Page 10 of 22
ATTACHMENT 7.1 Page 2 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in ITS 5.6.5 and the COLR Section 3.0.
2.1 Moderator Temperature Coefficient (ITS 3.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
a) The Positive MTC (ARO) shall be less than or equal to +5.0 pcm/OF for power levels up to 50% RTP, and b) The Positive MTC (ARO) shall be less than or equal to 0.0 pcm/OF at 50%
RTP and above.
c) The Negative MTC (ARO/RTP) shall be less negative than -40.0 pcm/OF.
2.1.2 The 300 ppm Surveillance limit is:
At an equilibrium RTP-ARQ boron concentration of 300 ppm the MTC shall be less negative than or equal to -32.9 pcm/OF.
2.1.3 The 60 ppm Surveillance limit is:
At an equilibrium RTP-ARO boron concentration of 60 ppm the MTC shall be less negative than or equal to -36.9 pcmPF.
2.2 Shutdown Banks Insertion Limits (ITS 3.1.5) 2.2.1 The shutdown banks shall be withdrawn to at least 225 steps.
2.3 Control Bank Insertion Limits (ITS 3.1.6) 2.3.1 The control banks shall be limited in physical insertion as shown in Figure 1.0 FMP-001 Rev. 16 l Page 11 of 22
ATTACHMENT 7.1 Page 3 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 2.4 Heat Flux Hot Channel Factor- FQv (Z) (ITS 3.2.1, 3.2.3)
Fcv(Z) < (CFQ/P) x K(Z) for P > 0.5 FaV(Z) < (CFQ/O.5) x K(Z) for P
- 0.5 Where: P = (Thermal Power I Rated Thermal Power) 2.4.1 CFQ = 2.46 for ROB-14, ROB-16, ROB-17, ROB-18 and ROB-19 reload batches 2.4.2 K(Z) is specified in Figure 2.0 2.5 Nuclear Enthalpy Rise Hot Channel Factor - FAH (ITS 3.2.2, 3.2.3)
FAH < FAHRTP (1 + PFAH (1-P))
Where: P = (Thermal Power / Rated Thermal Power) 2.5.1 FAH is the measured FAHN multiplied by the measurement uncertainty (1.04) 2.5.2 FHRTP = 1.80 for ROB-14, ROB-16, ROB-17, ROB-18 and ROB-19 reload batches 2.5.3 PF&H = 0.2 2.6 Axial Flux Difference (ITS 3.2.1, 3.2.3) 2.6.1 The axial flux difference target bands are +/-3% and +/-5% about the target AFD.
2.6.2 V(Z) values for the +/-3% and +/-5% target bands are specified in Figures 3.1 and 3.2 2.6.3 The AFD Acceptable Operation Limits are specified in Figure 4.0 FMP-001 Rev. 16 Page 12 of 22
ATTACHMENT 7.1 Page 4 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 2.7 Shutdown Margin Requirements (SDM) (ITS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.4.5, 3.4.6, 3.9.1) 2.7.1 The Mode I and Mode 2 required SDM versus RCS boron concentration is presented in Figure 5.0.
2.7.2 The Mode 3 SDM requirements are as follows:
a) With at least 2 reactor coolant pumps in operation, the SDM shall be greater than or equal to that specified in Figure 5.0.
b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 4% Ak/k.
c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to that specified in Figure 5.0.
2.7.3 The Mode 4 SDM requirements are as follows:
a) With at least 2 reactor coolant pumps in operation, the SDM shall be greater than or equal to that specified in Figure 5.0.
b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 4% Ak/k.
c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to that specified in Figure 5.0.
2.7.4 The minimum required SDM for Mode 5 is 1%Ak/k.
2.7.5 The minimum required SDM for Mode 6 is 6% Ak/k.
2.8 Refueling Boron Concentration (ITS 3.9.1) 2.8.1 In Mode 6 the minimum boron concentration shall be 1950 ppm.
FMP-001 Rev. 16 l Page 13 of 22
ATTACHMENT 7.1 Page 5 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 3.0 METHODOLOGY REFERENCES
- 1) Not Used For Cycle 22
- 2) XN-NF-84-73(A), Revision 5, "Exxon Nuclear Methodology For PWRs:
Analysis of Chapter 15 Events," Siemens Power Corporation, October 1990.
- 3) XN-NF-82-21(A), Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.
- 4) EMF-84-093(A), Revision 1, "Steamline Break Methodology for PWRs,"
Siemens Power Corporation, February 1999.
- 5) XN-75-32(A) Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Fuel Rod Bow," Exxon Nuclear Company, October 1983.
- 6) XN-NF-82-49(A), Revision 1 (April 1989) and Supplement 1 (December 1994), "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power Corporation.
- 7) EMF-2087(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.
- 8) XN-NF-78-44(A)," A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983
- 9) Not Used For Cycle 22
- 10) Not Used For Cycle 22
- 11) XN-NF-82-06(A), Revision I and Supplements 2, 4, and 5, 'Qualification of Exxon Nuclear Fuel for Extended Burnup (PWR)," Exxon Nuclear Company, October 1986.
- 12) Not Used For Cycle 22 FMP-001 Rev. 16 l Page 14 of 22
ATTACHMENT 7.1 Page 6 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0
- 13) Not Used For Cycle 22
- 14) Not Used For Cycle 22
- 15) Not Used For Cycle 22
- 16) ANF-88-054(A), -PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H.B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, October 1990.
- 17) ANF-88-133(A), and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.
- 18) ANF-89-151 (A), and correspondence UANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"
Advanced Nuclear Fuels Corporation, May 1992.
- 19) EMF-92-081(A), Revision 1, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," Siemens Power Corporation, February 2000.
- 20) EMF-92-153(A), Revision 0 and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, March 1994.
- 21) XN-NF-85-92(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.
- 22) EMF-96-029(A), Volume 1, Volume 2 and Attachment, "Reactor Analysis System for PWRs," Siemens Power Corporation, January 1997.
- 23) EMF-92-116(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.
I FMP-001 I Rev. 16 l Page 15of 22
ATTACHMENT 7.1 Page 7 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 1 .0, Control Group Insertion Limits for Three Loop Operation 225
-- (4.07,225); (67..03,2251 (h0.155.125)
(0.215~ Bank B 200 175 Bs 0 C '~~~~~~~~(10165) 150 E
I 125 R 100 U,
0 (0.87) 0 75 50 25
- (20.~
0 10 20 30 40 50 s0 70 so 90 100 CORE POWER (%)
NOTE: The breakpoint between BOL and EOL RIL occurs at 50% of the cycle as defined by burnup. For Cycle 22, this bumup occurs at 254 EFPDs.
Control rod banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is Shutdown "A", Shutdown NB", Control
'A", Control 'B", Control 'C", and Control "D". The insertion sequence is the reverse of the withdrawal sequence.
Overlap of consecutive control banks shall not exceed the prescribed setpoint for automatic overlap. The setpoint is 97 steps.
Control bank A must be withdrawn from the core prior to power operation.
At BOL and 0% core power, Control bank B will be at or above step 224.
I FMP-001 I Rev. 16 l Page 16 of 22 l
ATTACHMENT 7.1 Page 8 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 2.0, Normalized Axial Dependence Factor Kqz) for Fq Versus Elevation 1.20 (6.0, 1.0) 1.00 P
- 1 0.80 0
I I I I I I ~~~~~~~(12.0, Q.64 S.0.60
- - -- - - - I - - - - L - - - - - ~
X 0.40 0.20 0.00 0 1 2 3 4 5 6 7 8 9 10 11 12 Axial Height (ft)
IFMP-001 IRev. 16 1Page 17 f2
ATTACHMENT 7.1 Page 9 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.1 V(z) as a Function of Core Height Height *5% +/-3%
(Feet) V(Z) V(Z)
'0.0 1.0000 1.0000
- 0.2 1.0000 1.0000
'OA 1.0000 1.0000
- 0.6 1.0000 1.0000
- 0.8 1.0000 1.0000
'1.0 1.0000 1.0000 1.11.
II I I I I I I I T r I I I T I T I I I I *1.2 1.0000 1.0000 I I_ I I I I I I I I I I I I I I I Ih I I 1A 1.0999 1.0679
--F-4 -I - -I- - - - - - - - - - -I - -I- - F-F +-4-- -- I-
- I I I I I I I I I I I I I I I I I I I I I1 I 1.6 1.0979 1.0666 1.it 1.8 1.0948 1.0644 I. 1I I I I r 1 I I I I I I I I I 2.0 1.0916 1.0624
, I, i A~~~~~R3A I I I I _ , ,A 2.2 1.0883 1.0603 1.9W 2.4 1.0846 1.0575 2.6 1.0810 1.0545 Ir I -r II - - I -I I I 1I - I- I r rI - TIT I I I I I II I I I I I I I I A ' 1 I 1 I 2.8 1.0765 1.0511 t.C; 3.0 1.0737 1.0494 3.2 1.0718 1.0483 1.07
'- -4 '~~ I 1 h i' ' I I I I I A g^ I Is I I 3.4 3.6 1.0693 1.0666 1.0463 1.0441
L I-J-. I
,-IL L I _ IL _ I _ I E 3.8 1.0634 1.0418
, , , I I
- A I , III ,, I I I I 4.0 1.0609 1.0399 1.C6 I ,I
-l I I I .LIA I, I I I4A AAIk I I l I .1 I II I ^ I I I I 4.2 1.0589 1.0380 4.4 1.0571 1.0356 A4--1----I--FF- 4.6 1.0562 1.0345 tC5
- 4--l---,
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- F-P -- S I 1 I -~+-i i -- -
s
-4 i -- I 1
-F 2 F- -.4 4- I--I--I Jls- I--l I I
- F-F - +-4-I-I
+ 4 I I 4.8 1.0558 1.0348 5.0 1.0558 1.0352 I I I I I III I ITI IIIII I I I I I 5.2 1.0558 1.0351 Ir 5A 1.0556 1.0349
- s +-1 + - -I-- - I-- F- -4+- 4--I--I- -FE - 43+ 4 [- --I- -I- -F- F-4+- 4- 5.6 1.0548 1.0349 I I I I I I I-^
1 I I I I I I I I 5.8 1.0538 1.0347 im 6.0 1.0527 1.0341 6.2 1.0513 1.0335 I I I I I I I I I Ig I I I I I I I 6A 1.0491 1.0330 s ro - -
6.6 1.0462 1.0313 1
6.8 1.0428 1.0297 0 1 2 3 4 5 6 7 6 9 10 11 12 7.0 1.0389 1.0277 c-nwPwq 7.2 1.0373 10268 7A 1.0402 1.0273 7.6 1.0456 1.0300 7.8 1.0503 1.0335 8.0 1.0555 1.0374 6.2 1.0610 1.0414 B.4 1.0666 1.0453 8.6 1.0722 1.0499 8.8 1.0769 1.0531 9.0 1.0811 1.0567 92 1.0851 1.0608 9.4 1.0888 1.0651 9.6 1.0925 1.0688 9.8 1.0955 1.0719 10.0 1.0985 1D0750 102 1.1014 1.0778 10.4 1.1038 1.0796 10.6 1.1048 1.0808
- 10.8 1.0000 1.0000 Note: V(z) data applicable for 0 < bumup < 11,000 MWD/MTU. *11.0 1.0000 1.0000
- 11.2 1.000 1.0000 11.A 1.0000 1.OO0
- 11.6 10000 10000 11.8 1.0000 1.0000
- 12.0 1.O0O 1.0000 FMP-001 Rev. 16 l Page 18 of 22
ATTACHMENT 7.1 Page 10 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.2 V(z) as a Function of Core Height Height i5% +/-3%
(Feet) V(Z) V(Z)
.0.0 1.0000 100
'02 1.0000 1.0000
'OA 1.0000 1.0000
'0.6 1.0000 1.0000
'G.8 1.0000 1.0000 I T 4
I I 1
I I I
4 - I - -I I I I I I I I
I T
I rI I
I I
I I
r I
1 I
T I I I
I I
I *1.0 1.0000 1.0000 L _ _ _'I _' _ L 1I' _ J_ _ '
I ' '
I I _ J _ L_ Iv Ij I__ '12 1.0000 1.0000 I *I I I I I I I I I I , , I , I ,I I, l I I 1A 1.1017 1.0696 1.. I I I* I I I I , I I I I I I 1I 1 I I I 1.6 1.0990 1.0682 I 1 I 1 I I I t I I It 1 1 I 1.8 1.0957 1.0660 I I I 4 I l 1 1 1 I I I 1 I i I I 2.0 1.0920 1.0635
~~~~ ~
_E _IJ__l__LL~lJ__l r. -l- - - ~
-*t3%AWD~.
- 4. dI .. , -r -r- 4- -4 4- 1--r-L -. L.
.. . -- 22 1.0883 1.0611 i J T~~~ -
I, IL I I I I 1-I I I I I 41 k I --I I I T I I I T I I I I I I l , I I 2A 1.0846 1.0587 I.Wa 2.6 1.0810 1.0552 I I I I I I I I I I I I I I I I I I I I I . . 2.8 1.0764 1.0515 I I I I I I I I I I I I I I I I 4 I g Is I
-T~n UX----n--rr T~~l~1 Tn 1 3.0 1.0719 1.0486
_I I _ Il Il _ 1IL_I W ' I _ _ _L_ Il _ 1_ _ _I I l_L_ 3.2 1.0678 1.0462
- 1 J J J I I I I I
z l I+
1 .
l I
I I
I iCl t I I I I
3A 1.0644 1.0439 1.0C I 1 l 1 111+ 1 +l I I I I 1 I+
3.6 1.0626 1.0419 3.8 1.0637 1.0404 I I I Tl I I 4.0 1.0654 1.0410 4.2 1.0672 1.0427 F , I U: I I I I I 14 1 1 1 I I I I I I 4.4 1.0690 1.0443
, I I I I I I I I I
, iC
,U i
. , * , I 4.6 1.0703 1.0456 I I I I I I I I I I I I I+ 1 1 1 Ii 1 I I I 4.8 1.0716 1.0468 p i I I i I I I I I I I 11 v I I I I I I I 5.0 1.0726 1.0479 IJOB 1.06 T I -I I T I I i* -I Pt.~
I 1i -I Ir W ) I I - rI I 5.2 1.0729 1.0487 1 I__,_l L_ EI _ J _ L1JI____L._.L.A
[TE _J _'TL _L._1J_ 5A 1.0725 10488 I I I I I I U I
- Ill I " I I I I I I I I I I 5.6 1.0716 1.483 lim -
I
- 1 I
- t I I
I I E F- 14-a*- -A
^ l
-F l l
-U -
l w H-4 -.
l
-F- - 4- 2--U - F-41 - 5.8 1.0703 1.0479 I I I I I I I I I I
- I *1 I 1 1 1 1 1 6.0 1.0681 1.0468 l l l I , } I 6.2 1.0654 1.0452 I -- ,--,--rr-I--,I- -rIr- -I--,_,I-rI I I,--r-rI I 6.4 1.0622 1.0436 (R.
1.W_ . . . .
6.6 1.0586 1.0415 Q0 1.0 20 30 40 so e.0 7.0 &0 to 1Q0 11.0 120 6.8 1.0540 1.0385 c d O 7.0 1.0503 1.0370 72 1.0493 1.0364 7A 1.0521 1.0359 7.6 1.0570 1.0359 7.8 1.0611 1.0385 Note: V(z) data applicable for 11,000 < burnup < 18,359 MWD/MTU. 8.0 1.0652 1.0417 82 1.0689 1.0448 8A 1.0716 1.0476 8.6 1.0741 1.0503 8.8 1.0773 1.0534 9.0 1.0811 1.0569 92 1.0851 1.0608 9A 1.0888 1.0651 9.6 1.0925 1.0688 9.8 1.0955 1.0719 10.0 1.0985 1.0750 102 1.1014 1.0778 10A 1.1038 1.0796 10.6 1.1048 1.0808
'10.8 1.0000 1.0000
'11.0 1.0000 1.0000
'11.2 1.0000 1.0000
'11A 1.0000 1.0000
'11.6 1.0000 1.0000
'11.8 1.0000 1.0000
'12.0 1.0000 1.0000 l FMP-001 I Rev. 16 l Page 19 of 22 l
ATTACHMENT 7.1 Page 11 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 4.0, Allowable Deviation from Target Flux Difference 100 1*
(t10,90) 90 :UNCCETA (4.,9b UNACCERUTBLE 80 OPERATION UNACCPTABE/.'PTA9 70 a-LEOPEM~TION x 60
-I
- 0. - - --- -- - -- -a - - - -- - - ---
50
... . . / Tagtad 0:
40 -- ,--
-- -------- U 30 20.
10 0 , ; ,
-40 -30 -20 -10 0 10 20 30 40
[EJIATION FROM TARGEr FLUXK DIFFMECE('h)
NOTE: For power levels above 90%, power operation is allowed within the target bands (+/-3% and +5%).
I FMP-001 I Rev. 16 l Page 20 of 22
4pl ATTACHMENT 7.1 Page 12 of 12 HBRSEP UNIT NO. 2, CYCLE 22 CORE OPERATING LIMITS REPORT REVISION 0 Figure 5.0, Shutdown Margin Versus Boron Concentration 2.0 1.8 I I I I I I I ~~~I- I I II I -I- I 4 - -I II I- II I 4 - 4 - I- I- I I I I 1-I II I I I I ~I -I- I I I- I T I I T I I I I -I- I I
-: -~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
1.6 I I I I I I II IL
' I I I I I I1 I I IL I I IL 1.4 4-F-F- 1 4- I- -I 4-- 4-F--I- 4 '-- 1- - F- F-I
---V 4-f- -I 4-I- -I-A-- r-I I I I I I I I I I IL I I L 1 -1 11I1 1 I 1 I I I 1 I I IL 2
a 1.2 I- I r I rI T I I I I IT I I I I I Ir I I -
C) 1.0 11 IL L 11 I I IL I IL I ~ ~ I II I I 1 -1 I I - I 4I 4 I 4 I I I4 4 I I 4 I I I I I I I I~~-I I I I I I I I I I I I I I I I r I I I I 0.8 I I L I I - I,- I 1 I I I I -I I, 1 I I I1 I I I I ILI I IL1 I 1I I -I- I1 IL 0.6 0.4 0.2 0.0 0 200 400 600 800 1000 1200 1400 1600 1800 2000 BORON CONCENTRATION, ARO, HFP (ppm)
IFMP-001 IRev. 16 1Page 21of2