ML050810207
| ML050810207 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/28/2005 |
| From: | Fawcett R, Harding M, Trosman L Global Nuclear Fuel |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NEDC-33144, Rev 01 | |
| Download: ML050810207 (25) | |
Text
ATTACHMENT 2 GNF2 Lead Use Assembly (LUA) for Peach Bottom Atomic Power Station, Unit 3, NEDC-33144, Revision 1, February 2005 Non-Proprietary Version
NEDC-33144 Revision 1 February 2005 GNF2 Lead Use Assembly (LUA) for Peach Bottom Atomic Power Station, Unit 3
NEDC-33144 -Rev 1 GNF2 L UAs For Peach Bottom 3 Document
Title:
GNF2 Lead Use Assembly for Peach Bottom 3 Abstract I5xelon Generation Company, LLC plans to load four (4), or eight (8), Lead Use Assemblies as part of the Peach Bottom 3 (PB3) Reload 15 Cycle 16 during the 2005 refueling outage.
These bundles, also referred to as GNF2 LUAs, are planned to be in operation as part of a joint program with Global Nuclear Fuel -Americas, LLC (GNF).
This report contains information that is to be provided to the Nuclear Regulatory Commission (NRC) to comply with the Kefcrence 1 letter that provides guidelines to be followed to license LUAs. Included in this report are a description of the GNF2 LIJAs, a discussion of the applicability of approved methods to the licensing analyses, a description of the objectives of the L,UA program, and an outline of the kinds of measurements planned for the LUAs.
Signatures Prepared by:
Russ Fawcett Date I
Verified by:
Lukas Trosman Date Approved by:
Margaret Harding Date February, 2005 February, 2005 February, 2005
NEUC-33 144 - Rev 1 GNF2 LUAs For Peuch Bottom 3 Important Notice Regarding Contents of this Report Please Read Carefully A. Notice This document was prepared by or for Global Nuclear Fuel. Neither Global Nuclear Fuel nor any of the contributors to this document:
A. Make any warranty or representation, expressed or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information disclosed in this document may not infringe privately owned rights; or B. Assumes any responsibility for liability or damage of any kind that may result from the use o f any information disclosed in this document.
B. Proprietary Information Notice This document contains proprietary information of Global Nuclear Fuel (GNF) and is submitted in confidence solely for the purpose or purposes stated in the transmittal letter. No other use, direct or indirect, of the document or the information it contains is authorized. It is to be handled in accordance with the contract or agreement under which it is supplied, as stated in the transmittal letter, including specifically provisions governing the confidential treatment of Proprietary Information, as well as compliancc with provisions governing export and re-export of the same. Furnishing this document does not convey any license, expressed or implied, to use any patented invention or any proprietary infomation of GNF disclosed herein, or any right to publish or make copies of the document without prior written permission of GNF, except as provided in the contract or agreement under which it is supplied. This document shall be returned upon written request of GNF.
I l l
NEDC-33 144 - RCV 1 GNF2 L UAs For Pmch Bottom 3 Revision Status Revision Number 1
Signature RMF iv
NE3DC-33 144. KCV 1 GNF2 LUAs For Peach Bottom 3 1.
2.
3.
4.
5.
2.1.
2.2.
2.3.
2.4.
2.5.
2.6.
3.1.
3.2.
3.3.
3.4.
3.5.
3.6.
3.7.
3.8.
Table of Contents Page Introduction...................................
1 2
2 Fuel Rod Design.....................................................
3 Channel Design...............................................
4 4
Debris Shield Lower Tie Plate....................................................................................
4 GNF2 Fuel Product Description....
New Design Features.....................
Part-Length Rod Configuration..................................................................................
3 High Performance Spacers.............................
Licensing Analyses...................................................................................................
12 Core Wide AOOs......................................................................................................
12 Localized AOOs.............................................
12 Control Rod Drop Accident (CRDA).......................................................................
13 Loss of Coolant Accident and ECCS 13 Refueling Accident...................................................................................................
13 Stability.............................................................
13 Shutdown Margin..................................................................................................... 13 RA-3 Shipping Container.........................................................................................
14 LUA Measurements................... -..............................................................................
16 LUA Program Objectives.........._..............................................................................
15 6.
References................................................................................................................
17 V
NEIIC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3 List of Tables Table Title Page Table 2-1......................................
GNF2 and GE14 Dimcnsions...............................................
6 vi
NEDC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3 List of Figures Figure Title Page Figure 2-1.............
Figure 2-2..........
Figure 2-3.....................................
GNF2 Lower Tie Plate..........................................................
9 Figure 2-4.....................................
GNF2 Grid Spacer..............................................................
10
........ GNF2 Bundle Assembly..........................
........... GNF2 Lattice Arrangement............................
Figure 2-5.....................................
GNF2 Axial Spacer Pitch................................................... 1 1 vii
NEDC-33 144 - Rev I CNF2 LUAs For Peach Bottom 3
- 1.
Introduction Exelon Generation Company, LLC plans to load four (4), or eight (S), Lead Use Assemblies as part of the Peach Bottom 3 (PB3) Reload 15 Cycle 16 during the 2005 refueling outage. These bundles, also referred to as GNF2 LUAs, are planned to be in operation as part of a joint program with Global Nuclear 1;uel-Americas, LLC (GNF).
This report contains information that is to be provided to the Nuclear Regulatory Commission (NRC) to comply with the Reference 1 letter that provides guidelines to bc followed to license LUAs. Included in this report are a description of the GNF2 LUAs, a discussion of the applicability of approved methods to the licensing analyses, a description of the objectives of the LUA program, and an outline of the kinds of measurements planned for the LIIAs.
The GNF2 fuel design is described in Section 2. GNF2 is designed to be compatible with other GE fuel designs. The thermal hydraulic design closely matches the overall pressure drop of previous designs. The external envelope of the fuel assembly is virtually identical to the GE14 fuel assembly currently supplied to PB3. The nuclear characteristics of these GNF2 LUAs are compatible with those of the current GE14 fuel being loaded into PB3.
Section 3 describes the licensing analyses that will be performed and the objectives of the LUA program are stated in Section 4. The kinds of measurements planned as part of L,UA surveillance are described in Section 5.
Page 1
NEDC-33 144 - Rev I GNF2 L UAs For Peach Bottom 3
- 2.
GNF2 Fuel Product Description A GNF2 bundle schematic is shown in Figure 2-1.
The GNF2 lattice arrangement is shown in Figure 2-2. The rods are spaced and supported by the upper and lower tie plates and spacers over the length of the fuel rods. The GNF2 channel has a similar planar cross section as the GE14 channel.
The fuel rods consist of high-density ceramic uranium dioxide or urania-gadolinia fuel pellets stacked within Zircaloy-2 cladding. The cladding contains an inner zirconium liner provided for PCI resistance. The fuel rod is evacuated and backfilled with helium Fuel rod dimensions are given in Table 2-1.
2.1.
New Design Features GNF2 was designed for mechanical, nuclear, and thermal-hydraulic compatibility with previous GE fuel designs. The design includes many proven features of the GElO, GE11/13, GE12 and GE14 fuel designs including PCI resistant barrier cladding, part length rods (PLR),
. New or improved features included in GNF2 are:
A discussion of each o f these new design features is provided below Page 2
NEIIC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3
~~
~
~~
2.2.
Part-Length Rod Configuration 2.3.
Fuel Rod Design The high energy GNF2 fuel rod has the following characteristics Page 3
NEDC-33 144 -- Rev 1 GNF2 L UAs For Peach Bottom 3 2.4.
Channel Design 2.5.
High Performance Spacers 2.6.
Debris Shield Lower Tie Plate Page 4
NEDC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3 Page 5
N m C - 3 3 144 - Rev 1 GNF2 LUAs For Peach Bottom 3 he1 Assembly Total number of fuel rods Table 2-1. GNF2 and GE14 Dimensions GE14 GNF2 Number of Full length Number of Partial length Lattice Array Rod to rod pitch (cm)
Number of water rods Typical Assembly Fuel weight (KgU)
Total Fuel Assembly Dry Weight Total Fuel Assembly Submerged Weight Typical Assembly active fuel length (mm)
Full length Partial Lenrrth Fuel Rod Cladding material Cladding tube diameter, outer (mm)
Cladding tube wall thickness (mm)
Pellet diameter, outer (mm)
Pellet stack density (g/cm3)
Pellet density with burnable absorber (g/cm3)
Water Rod Tube material Tube diameter, outer (mm)
Tube wall thickness (mm)
Spacer Number of spacers Axial locations Page 6
NEDC-33 I44 - Rev 1 GNF2 LUAs For Peach Bottom 3 Page 7
NlDC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3 Figure 2-2 GNF2 Lattice Arrangement Page 8
NEDC-33 144 - Rev 1 GNF2 LUAs For Peuch Bottom 3 Figure 2-3 GNF2 Lower Tie Plate Page 9
NEUC-33 144 - RCV 1 GNF2 L UAs For Peach Bottom 3 Figure 2-4 GNF2 Grid Spacer Page 10
GNF2 L, UAs For Peach Bottom 3 NEDC-33144 - Rev 1 Note that elevations correspond to the top of the lower tab attached to the spacer capture water rod.
Figure 2-5 GNF2 axial spacer pitch Page I1
NEDC-33 I44 -- Rev I GNF2 LUAs For Peuch Bottom 3
- 3.
Licensing Analyses The GNF2 LlJAs have been, or will be, analyzed using the NRC approved methods described in Reference 2. These methods are fully capable of analyzing all of the LUA features. Prior to loading of the LUAs, cycle-specific analyses will have been performed for Pl33 Reload 15 Cycle 16 to establish fuel operating limits for the LUAs and to ensure that the core loading has been designcd such that the LUAs will not be the most limiting fuel assemblies at any time during Cycle 16 with respect to compliance with LHGR, MAPLHGR and MCPR limits based on planned control rod patterns. Results of these analyses will be documented in the Supplemental Reload Licensing Report (SRLR). Furthermore, licensing analyses will be performed for the 1,UAs for each cycle of their operation, wherein the effect of the LUAs is considered for each of the appropriate licensing events and anticipated operational occurrences (AOOs) to establish appropriate reactor core thermal limits [or operation.
Exelon intends to insert the GNF2 LNAs into PB3 and to operate Cycle 16 under the provisions of 1 OCFR50.59. However, cycle specific analyses to establish fuel operating limits are not yet complete. When the cycle specific analyses are complete, GNF will document the results in the Supplemental Reload Licensing Report and Exelon will update the PB3 Core Operating Limits Report accordingly.
The application of approved methods to analyze events and accidents whose results could be affected by the LUAs design is discussed below. Since the analysis of the LUAs using the approved methods meets, or will meet, the approved criteria, it is not anticipated that NRC approval is required prior to insertion.
3.1.
Core Wide AOOs Current approved methods described in Reference 2 are considered appropriate to determine the impact of core-wide AOOs on the LUAs. The GNF2 fuel rod(s) have been analyzed with GSTRM to establish steady state, and transient overpower, LHGR limits that ensure compliance with thermal mechanical licensing requirements as specified in Reference
- 2. Appropriate MCPR limits will be established to ensure safe operation of the LUAs based on these results. Note that GEXL14 is conservatively applied in the prediction of the onset of Boiling Transition for the LUAs.
3.2.
Localized AOOs Approved methods are considered adequate to evaluate core response to a Rod Withdrawal Error (RWE), since the nuclear inputs are available to represent the LUAs discretely. MCPR results will be based on the conservative application of GEXLl4 and provided in the SRLR.
Page 12
NEDC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3 An evaluation was performed to estimate the effect on CPR of'the Fuel Loading Error (Rotated Bundle). Preliminary results demonstrate that the change in CPR for this event is bounded by that used to establish the Operating Limit MCPR (OI.MCPR) for the LUAs with significant margin, and therefore a Rotated Bundle Error will not result in violation of the OLMCPR. This will be confirmed prior to Cycle 16 startup.
3.3.
Control Rod Drop Accident (CRDA)
Compliance with licensing limits governing CRDA is assured through adherence to the Ranked Position Withdrawal Sequence (BPWS) as the associated analyses have generically demonstrated large margin to licensing limits governing acceptable enthalpy insertions. Due to the similarities in nuclear characteristics between the LUAs and approved GNF fuel designs, the Reference 2 methodology is applicable to the LUAs. Operation with the LUAs will not result in exceeding CKDA acceptance criteria 3.4.
Loss of Coolant Accident and ECCS
'The LUAs are to be loaded in non-limiting locations with respect to ECCS/LOCA MAPLHGR limits. An evaluation will be performed to assure that the LUAs will meet the PCT requirements in the event of a Design Basis Accident.
3.5.
Refueling Accident The impact of the LUAs on the assumptions and consequences of a refueling accident has been evaluated. The radiological consequences are conservatively bounded by FSAR analyses based on 7x7 or 8x8 fuel.
3.6.
Stability The GNF2 LUAs will be explicitly modeled in PR3 C16 stability analysis as part of the standard reload licensing. I Acensing requirements governing stability will be assured and the results reported in the SRLR. The PB3 C16 reload core will be designed such that the LUAs will not be the most limiting bundles from a stability standpoint.
3.7.
Shiitdown Margin The LUAs have been designed with approved methods to provide minimum cold shutdown margin greater than or equal to the design criteria identified in Reference 2, which, therefore assures that all Technical Specification shutdown margin requirements are satisfied.
Page 13
IUCUL-5I144 -- KeV 1 GNF2 LUAs For Peach Bottom 3 3.8.
RA-3 Shipping Container Criticality safety analyses have been performed that confirm the adequacy of the KA-3 Application for shipping container to support the transportation of GNF2 fuel bundles.
modification of the RA-3 certificate has been made to the regulatory authorities.
Page 14
NGDC-33144 - Rev 1 GNF2 LUAs For Peach Bottom 3
- 4.
LUA Program Objectives The purpose of the GNF2 LUA Program is to obtain surveillance data to verify that fuel bundles with the design features described in Section 2 perform satisfactorily in service, prior to use of those features on a production basis.
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NEDC-33 144 - Rev 1 GNF2 LUAs For Peach Bottom 3
- 5.
LUA Measurements As currently envisioned, measurements on the LlJAs will consist of pre-irradiation characterization of fuel pellets, clad tubing, fuel rods, components and fuel bundles.
At subsequent refueling outages, the scope of inspections consist of some, or all, of the fo 1 1 owing :
0 Fuel bundle visual 0
0 0
Corrosion thickness measurements Channel bow and bulge measurements Fuel rod and bundle length measurements Rod integrity and profiloinetry measurements The extent of such measurement will be governed by the need to minimize the impact of these activities on the refueling outage critical path, the amount of inspections being performed on similar features at other reactor sites, and by the degree of technical interest in implementing the design changes demonstrated in the LUA.
Results obtained from this LlJA Program will be summarized in a timely manner in GNF Fuel Experience Reports.
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NEDC-33 144 - RCV 1 GNF2 LUAs For Peach Bottom 3
- 6.
References 1.
Letter, T.A. lppolito (NRC) to R E Engel (GE), Lead Test Assembly Licensing, September 23, 198 1.
NEDE-24011 -P-A-l4, General Electric Standard Application for Reactor Fuel, June 2000.
- 2.
- 3.
GE14 Compliance with Amendment 22 ofNEDE-24011 -P-A (GESTAR Il),
NEDC-328681, Rev.l, September 2000.
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