JAFP-04-0083, Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio
| ML041620527 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/04/2004 |
| From: | Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-04-0083 | |
| Download: ML041620527 (18) | |
Text
'
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP e Hn thory RO. Box 110
-E n
bLycoming, NY 13093 Tel 315 349 6024 Fax 315 349 8480 TA. Sullivan Site Vice President - JAF June 4, 2004 JAFP-04-0083 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
James A. Fitzpatrick Nuclear Power Plant Docket No. 50-333 Proposed License Amendment to Safet' Limit Minimum Critical Power Ratio (SLMCPR)
Gentlemen:
Pursuant to IOCFR50.90, Entergy Nuclear Operations, Inc. (ENO) is submitting a request for amendment to the Technical Specifications (TS) for the James A. Fitzpatrick Nuclear Power Plant (JAFNPP). This proposed change provides revised values for the Safety Limit Minimum Critical Power Ratio (SLMCPR) for both single and dual recirculation loop operation.
The signed original of the Application for Amendment to the Operating License is enclosed for filing.
Attachment I contains the proposed new TS page and Attachment 2 is the Safety Evaluation for the proposed changes. Attachment 3 provides the marked-up version of the current Technical Specification page. Attachment 4 is a summary of the technical basis for the SLMCPR values and is considered proprietary information by Global Nuclear Fuel - Americas, LLC (GNF).
In accordance with IOCFR2.390(bXl), an affidavit attesting to the proprietary nature of the enclosed information and requesting withholding from public disclosure is included with Attachment 4. Attachment 5 is the same GNF summary with the proprietary information removed, and is provided for public disclosure.
ENO has reviewed the proposed Technical Specification change in accordance with 10CFR50.92 and concludes that the proposed change does not involve a significant hazards consideration.
ENO has evaluated the proposed amendment against the criteria of 10CFR51.22 for environmental considerations and believes that the proposed change is eligible for categorical exclusion from the requirements for an environmental review in accordance with 10CFR5l.22(cX9). In accordance with 10CFR50.91, a copy of this application, with appropriate attachments, is being provided to the designated New York State official.
Regarding our proposed schedule for this amendment, we request your review and approval of the revised SLMCPR by September 3, 2004 with implementation prior to startup from the refueling outage.
The requested approval date and implementation period will allow sufficient time for effective planning and scheduling of affected activities associated with Refueling Outage 16, scheduled to begin on September 24, 2004.
C
If you have any questions concerning this transmittal or require additional information, please contact Mr. Andy Halliday at (315) 349-6055.
I declare under penalty of perjury that the forgoing is true and correct.
Executed on this the 4 day of 2004.
Very truly yours, w cv 5
... ~
b C
Cb AL fX T. A. Sullivan Site Vice President Attachments:
- 1. Revised Technical Specification Page (Retyped)
- 2. Safety Evaluation
- 3. Technical Specification Page (Mark-up)
Regional Administrator, Region I Mr. Paul Eddy U. S. Nuclear Regulatory Commission New York State Department 475 Allendale Road of Public Service King of Prussia, PA 19406 3 Empire State Plaza, 10e Floor Albany, NY 12223 Albany, New York 12223 Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 136 Lycoming, NY 13093 Mr. G. Vissing, Sr. Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop: 8C2 Washington, DC 20555 Mr. Peter R. Smith, President NYSERDA 17 Columbia Circle Albany, NY 12203-6399 ATTACHMENT 1 to JAFP-04-0083 REVISED TECHNICAL SPECIFICATION PAGE Safety Limit Minimum Critical Power Ratio (SLMCPR)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure c 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be i 251 RTP.
2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow k 10% rated core flow:
MCPR shall be k 1.06 for two recirculation loop operation or k 1.07 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be & 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
JAFNPP 2.0-1 Amendment XXX
ATTACHMENT 2 to JAFP-04-0083 SAFETY EVALUATION Safety Limit Minimum Critical Power Ratio (SLMCPR)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
1.0 Description of the Proposed Change Pursuant to I0CFR50.90, ENO proposes to revise Appendix A, Technical Specifications (TS) Section 2.1.1.2 of Facility Operating License DPR-59. The proposed changes to the Technical Specifications are as follows:
Page 2.0-1, Specification 2.1.1.2 - Replace the listed SLMCPR values of 1.09 (1.10 for single loop operation) with new values of 1.06 (1.07 for single loop operation).
2.0 Purpose of the Proposed Change Cycle specific calculations for JAFNPP by Global Nuclear Fuel (GNF) are summarized in Attachment 4.
The current SLMCPR values for dual and single loop operation contained in the Technical Specifications (1.09 and 1.10 respectively) are higher (more limiting) than values calculated by the fuel vendor for the next cycle (Cycle 17) using NRC-approved methods. The reduced SLMCPR values are consistent with reduced power distribution uncertainties that are supported by core monitoring methods to be used in Cycle 17 at JAFNPP. These uncertainties were reviewed and approved by the NRC as documented in. Based upon the core loading and fuel design to be used in Cycle 17, the cycle specific SLMCPR values were determined to be 1.06 for both dual loop and for single loop operation. (See additional discussion in section 3.0.)
3.0 Safety Assessment of Proposed Change The purpose of the SLMCPR is to provide high statistical probability that 99.9% of the fuel rods in the operating core would not experience transition boiling during the most limiting Abnormal Operational Transient (AOT). The criteria of transition boiling for determination of the SLMCPR is a conservative approach since this phenomena by itself does not signal the onset of fuel cladding failure. The revised SLMCPR for JAFNPP was determined using plant and cycle-specific fuel and core parameters and NRC approved methodology, as discussed in Attachment 4 (proprietary version of GNF summary of technical basis for SLMCPR values) and Attachment 5 (non-proprietary version of GNF summary). Analysis of the limiting AOT provides the allowed operating conditions, in terms of MCPR, of the core during the fuel cycle such that if the event were to occur, the transient MCPR would not be less than the SLMCPR.
No plant hardware or operational changes are required with this proposed change. supports the SLMCPR of 1.06 for single loop operation (SLO), however ENO is applying for a conservatively higher value of 1.07 for two reasons. First, the SLO SLMCPR has always been 0.01 higher than the dual loop SLMCPR for JAFNPP, and systems in place support this expected difference when operating in SLO. Second, it is expected that future cycles could show a 0.01 difference and a higher SLO SLMCPR in the Technical Specifications may avoid an amendment to support a higher value for the next or a future cycle. Actually, the single loop SLMCPR results are higher than the dual loop results by 0.008, but when rounded to two significant digits, the values are both 1.06. Both the SLO and dual loop calculation results are rounded up to the SLMCPR values submitted with this application.
4.0 No Significant Hazards Determination Pursuant to IOCFR50.92, JAFNPP has reviewed the proposed change and concludes that the change does not involve a significant hazards consideration since the proposed change satisfies the criteria in IOCFR50.92(c).
These criteria require that operation of the facility in accordance with the proposed amendment will not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident Page 1 of 3
previously evaluated, or (3) involve a significant reduction in a margin of safety. The discussion below addresses each of these criteria and demonstrates that the proposed amendment does not involve a significant hazards consideration.
The proposed change does not involve a significant hazards consideration because:
I.
The operation of JAFNPP in accordance with the proposed amendment, will not involve a significant increase in the probability or consequences of an accident previously evaluated.
The basis of the Safety Limit Minimum Critical Power Ratio (SLMCPR) is to ensure no mechanistic fuel damage is calculated to occur if the limit is not violated. The new SLMCPR values preserve the existing margin to transition boiling and probability of fuel damage is not increased.
The derivation of the revised SLMCPR for JAFNPP for incorporation into the Technical Specifications, and its use to determine plant and cycle-specific thermal limits, have been performed using NRC approved methods. These plant-specific calculations are performed each operating cycle and if necessary, will require future changes to these values based upon revised core designs. The revised SLMCPR values do not change the method of operating the plant and have no effect on the probability of an accident initiating event or transient.
Based on the above, JAFNPP has concluded that the proposed change will not result in a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
The operation of JAFNPP in accordance with the proposed amendment. will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes result only from a specific analysis for the JAFNPP core reload design.
These changes do not involve any new or different methods for operating the facility. No new initiating events or transients result from these changes.
Based on the above, JAFNPP has concluded that the proposed change will not create the possibility of a new or different kind of accident from those previously evaluated.
- 3.
The operation of JAFNPP in accordance with the proposed amendment will not involve a significant reduction in a margin of safety.
The new SLMCPR is calculated using NRC approved methods with plant and cycle specific parameters for the current core design. The SLMCPR value remains high enough to ensure that greater than 99.9% of all fuel rods in the core will avoid transition boiling if the limit is not violated, thereby preserving the fuel cladding integrity.
The operating MCPR limit is set appropriately above the safety limit value to ensure adequate margin when the cycle specific transients are evaluated. Accordingly, the margin of safety is maintained with the revised values.
As a result, JAFNPP has determined that the proposed change will not result in a significant reduction in a margin of safety.
On the basis of the above, JAFNPP has determined that operation of the facility in accordance with the proposed change does not involve a significant hazards consideration as defined in IOCFR50.92(c), in that it: (1) does not involve a significant increase in the probability or consequences of an accident Page 2 of 3
previously evaluated; (2) does not create the possibility of a new or different kind of accident from any accident previously evaluated; and (3) does not involve a significant reduction in a margin of safety.
Page 3 of 3
ATTACHMENT 3 to JAFP-04-0083 MARKED-UP TECHNICAL SPECIFICATION PAGE Safety Limit Minimum Critical Power Ratio (SLMCPR)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
SLs 2.0 2.0 SAFETY LIMITS (SMs) 2.1 SLs 2.1.1 Reactor Core SUs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25X RTP.
2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 2 10X rated core f1nd:^
CPR shall be fo recirculation loop operation or k 44G fo ngle recirculation loop operation.
2.1.1.3 Reactor veifr~ater level shall be greater than the top of active irradiated fuel.
I 2.1.2 Reactor Reactor Coolant System Pressure SL steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs: and 2.2.2 Insert all insertable control rods.
JAFNPP 2.0-1 Anendment.24-I
ATITACEIMENT 5 to JAFP-04-0083 GNF Summary of Technical Basis for SLMCPR Values (Non-Proprietary Version)
Entergy Nuclear Operations, Inc.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
Attachment AdditionaD Information Regarding the Cycle Specific SLMCPR for FitzPatrick Cycle 17 May 21, 2004 Proprietary Information Notice This document is the GNF non-pprietary version of the GNF propnetary report Fr=m the GNF proprietary version, the infomation denoted as GNF proprietary (enclosed in double brackets) was deleted to generate this version.
References I1 Lettr, Frank Akstulewicz (NRC to Glen A. Watford (GE), "Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 23 to NEDE-2401 1-P-A on Cycle Specific Safety Limit MCPR," (TAC Nos. M97490, M99069 and M97491), March 11, 1999.
[21 Letter, Thmas EL Essig (NRC) to Glen A. Watford (GE), "Acceptance for Refrencing of Licensing Topical Report NEDC-32505P, Revision 1, R-Factor Calculation Method for GEl 1. GE12 and GE13 Fuel" (TAC Nos. M99070 and M9508 1), January 11, 1999.
[31 Genera! Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, NEDO-10958-A, January 1977.
l4J Letter, Glen A. Watford (ONF-A) to U. S. Nuclear Regulatory Commission Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of lOxlO Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies", FLN-2001-016, September24, 2001.
[5]
Letter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Contol Desk with attention to J. Donoghue (NRC), "Confirmaton ofthe Applicability ofthe GEXL14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Futr, FLN-2001-017, October 1, 2001.
[61 Ltter, Glen A. Watford (GNF-A) to U. S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), 'Final Presentation Material for GEXL Presentation - Fcbnzary 11, 2002", FLN-2002-004, February 12, 2002.
page lof 7 0000-0028-9978
Attachment Additional Information Regarding the May 21,2004 Cycle Specific SLMCPR for FitzPatrick Cycle 17 Discussion Ihe Safety Limit Minimum Critcal Power Ratio (SLMCPR) evaluations for the Fitzpatrick Cycle 17 We performed using NRC approved methodology and uncertainties Ill. Table I summarizes the relevant input parameters and results of Cycle 17 and Cycle 16 cores. Additional information is provided in response to NRC questions related to smilar submittals regardmig changes in Technical Specification values of SLMCPR. NRC questions pertaining to how GE14 applications satisfyr the conditions of the NRC SERE' have been addressed in Reference [4]. Other geneically applicable questions related to application of the GEXL14 correlation, and to the applicable range for the R-factor methodology, are addressed in Reference
[5]. Items that require a plan/cycle specific response are presented below.
In general, the calculated safety limit is dominated by two key paruameters: (1) flatness of the core bundle-by-bundle MCPR distributions, and (2) flatness of the bundle pin-by-pin powerlR-factor distributions.
Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR The impact of these parameters on the FitzPatrick Cycle 17 and Cycle 16 SLMCPR values is summarized in Table 1. The Cycle 16 column and the GETAB Bases column for Cycle 17 ae both provided for comparison to the Cycle 17 Revised Bases column. The impact of these uncertainties is discussed in more detail below.
The core loading information for FitzPatrick Cycle 16 is provided in Figure 1. For comparison the core loading information for FitzPatrick Cycle 17 is provided in Figure 2. The impact of the fiel loading pattern differences on the calculated SLMCPR is correlated to the values of 1
))
11 The uncontrolled bundle pin-by-pin power distributions were compared between the FitzPatrick Cycle 17 bundles and the Cycle 16 bundles. Pin-by-pin power distributions are characterized in terms of R-fictors using the NRC approved methodology [2. For the FitzPatrick Cycle 17 limiting case analyzed at BOC, ((
D] the FitzPatriclc Cycle 17 bundles have a more peaked power distribution than the bundles used forthe Cycle 16 SLMCPR analysis.
The SLMCPR was calculated for FitzPatrick Cycle 17 using uncertainties that have been previously reviewed and approved by the NRC. These uncertainties ae shown in Table 2a and described in Reference 11]. Wcre warntd higherplant-cle-specific uncertaindes were used, as liste in Table 2b.
These calculaions use the GEXL14 correlation for GE14 fuel.
11 page 2 of 7 0000-0028-9978
Attachment Additional Information Regarding the Cycle Specific SLMCPR for FitzPatrick Cycle 17 May 21,2004 For single loop operations (SLO) the calculated safety limit MCPR for the limiting case is 1.06 as detenmined by specific calculations for FzPatrick Cycle 17 at BOC The DLO and SLO SLMCPR values calculated for FitzPatrick Cycle 17 are dswn in Table 1.
Summary lhe calculated 1.06 SLMCPR and 1.06 SLO SLMCPR for FitzPatrick Cycle 17 are consistent with expectations 1[
D These values are appropriate when the approved methodology and the reduced uncertainties given in NEDC-32601P-A and NEDC-32694P-A arm used.
Based on the information and discussion presented above, it is concluded that the calculated SLMCPR of 1.06 and 1.06 for SLO are appropriate for the FitzPatrick Cycle 17 corc.
page 3 of 7 0000-0028-9978
Attachment Additional Information Regarding the Cycle Specific SLMCPR for FitzPatrick Cycle 17 May 21, 2004 Table I Comparison of the FitzPatrick Cycle 17 and Cycle 16 SLMCPR ritz~atrick FitzPatrick FitzPatrick QUANTM, DESCRIElON Cytzle 16 Cycle 17 Cycde 17 Qcle 1 GETAB Bases' Revised Bases Number ofBundles in Core 560 560 560 Limiting Cvcle Exposure Point MOC MOC BOC Cycle Exposure at limiting Point M000 200 Reload Fuel Tpe GE14 GE14 GE14 Latest Rcload Batch Frwaction, %
35.0 36A 36A Latest Reload Average Batch Weight 4.05 4.05 4.05
% Enidhment Core Fuel Fraction for GE14 (fe) 35.0 71A 71A Core Fuel Fraction for GE12 (%)
65.0 28.6 28.6 Core Average Weiaht % Enrichment 4.06 4.05 4.05 Core MCPR (for limiting rod pattem) 1.46 1.38 1.37 ff f
ff 11 if 1
Power disribution methodology GETAB NEDO-GETAB NEDO-Rcvised NEDC-10958-A 10958-A 32601P-A Power distribution uncertainty GETAB NEDO-GETAB NEDO.
Reduced NEDC-10958-A 10958-A 32694P-A Non-powerdistribution uncertainty Revised NEDC-Rcvised NEDC-Revised NEDC-32601P-A 32601P-A 32601P-A Calculated Safety Limit MCPR 109 1.09 1.06 (DLO)
Calculated Safety Limit MCPR 110 1.09 10 (S WO
)
lTe C17 GETAB comparison SLMCPR analysis used the Stndard uncertafiy values that we used for te C16 SLMCPR analyes.
page 4 of 7 0000-0028-9978
Attachment Additional Information Regarding the Cycle Specific SLMCPR for FitzPatrick Cycle 17 May 21,2004 Table 2a Standard Uncertainties DESCRIPTION FitzPatrick Cycle 16 FitzPatick Cycie 17 Non-power Distribution Uncertainties Revised NEDC-32601P-A Revised NEDC-32601P-A Core flow rate (derived fiom presur drop) 2.5 DLO 2.5 DLO 6.0 SLO 6.0 SLO Indialchannel fow area 11 I
11 Individual channel friction factor 5.0 5.0 Friction factormultiplier rr ir 11 Reactor pressure rr n
Core inlet temperature 0.2 0.2 Feedwatertmipemture rr 11 If 11 Feedwater flow rate
[f 11 If 11 Power Distribution Uncertainties GETAB NEDC-32601P-A Reduced NEDC-32694P-A GEXL R-fictor It 11 If 11 Random effective TIP reading 1.2 DLO 1.2 DLO 2.85 SLO 2.85 SWO Systematic effective TIP reading 8.6 If n
Integrated effective TIP reading N/A If U
Bundlepowe N/A It 11 Effective total bundle power uncertainty 4.3 Table 2b Exceptions to the Standard Uncertainties Used in FitzPatrick Cycle 17 GEXL R-factor U
2 2TMs value was increased to accommodate increased cbanne bow uncertainty.
page 5 of 7 0000-0028-9978
A;.
Attachment Additional Information Regarding the Cycle Specific SLMCPR for FitzPatrick Cycle 17 MAy 21,2004 Figure 1 Reference Loading Pattern - FitzPatrick Cycle 16 52 BE3BE 50 9r EEl E
48 DEOWDE)E IEIDE BOM 48 ff-ERIMElYE-Off El 42 ME El E E3 f DE 40 S8 ID 03 ffz rE l ErM OE-I-YE-UErB 01 Mr10 f ErD OE1 Of-El s@
38 54 32 30 222 EM~EDS
~NE D 8S SD SS 28 26 E17 xru OMs OZrE OD SEl 91-M-H-ff21U-O 14 124 DMD ME) OD ff @l 9M 9M EI UIS1 MI 10 22g1 0 El 0 f -fE-I fEr I rE 1tB 921U-1f lr al UE-ff M 2
f10 01 lBlal E]B f ELJ lW El ff El 14 3EE
- 13 17 21 2325723135379443S 44 12 E
gB C
BE~~gEE x
1 3567 9011 13 1517 1921 23 2527 2931 3335 3739 4143 4547 4951 Number Cycle Code Bundle Name Loaded Load d A
GE12-P1ODSB412-17GZ-1QOT-150-T 2
13 B
GE12-PI0DS8407-14G6.0-10OT-150-T 82 14 C
GE12-P1DSB407-17GZ-1OOT-150-T 84 14 D
GE12-PIODSB405-16GZ-1OOT-I50-T-2396 56 15 E
GE12-PIODSB405-17GZ-IOOT-i50-T-2395 132 15 F
GE12-PIODSB407-14G6.0-10OT-150-T 8
15 G
GE14-PIODONAB4O5-16GZ-100T-150-T-2551 120 16 H
GE14-P1ODNAB405-16GZ-IOT-150-T-2552 76 16 page 6 of 7 0000-0028-9978
i Attachment Additional Information Regarding the Cycle Specific SLMCPR for FitzPatrick Cycle 17 May 21, 2004 Figure 2 Reference Loading Pattern - FitzPatrick Cycle 17 52
__fM S0 0
F l l U0 J-EY-JE 48 48 e
l
=55 46 In R]E3 FID UEl1f fl DE-T El DEl Egg E-1 U E1 S 42 44 EhDDDShltDDDD 40 38 302 ff El E3 FEIl MD E-11El E DIE fEll DElD E-E E-T- @E-- ff El MD W E1
's8 9
El El fE BE-10 MBE-1 E-T-E-TE3 E-1UE-ETEU E-3r3O 14 "EVE ONE] EI-f E21uE1^1 MMgE 92ll fM-E~E10MQE1 M-1 32 FI~e~Ei~lEl~DkBlbEEWlESFI911Ml~
30 WE) WE3 tBE-UE-1 t
E 951 ff SE l FM~ 91-5151 92-28 nsF E
EW hE Eh a6 BEigii~IElEh~EllktaEkEtElEh9n~EblEIEl9 14 2
ffm;}
I f}
aElio 1 3 5 7 0 11 13 15 17 19 21 23 25 27 29 31 33 353 7 39 41 43 45 47 49 61 Number Cycle Code Bundle Name Loaded Loaded A
GE14-PIODNAB405-16GZ-IOOT-150-T8-2794 180 17 B
GE14-PIODNAB405-15G8.0-10OT-150-T6-2793 24 17 C
GE12-PIODSB405-16GZ-100T-150TB-3859 40 1S D
GE12-P10DSB405-17GZ-1DOWT-150-T6-858 112 15 E
GE12-PlODSB407-14G6.O-IOOT-150-T6 8
15 F
GE14-PIODNAB405-16GZ-IOOT-150-T62562 120 ls G
GE14-PIODNAB405-16GZ-IOOT-150-T6-2563 76 16 page 7 of 7 0000-0028-9979