ML16356A017

Information Report for Lead Use Assemblies

ML16356A017
Person / Time
Site:	Hatch
Issue date:	12/16/2016
From:	Global Nuclear Fuel - Americas
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16356A011	List: ML16356A017 NL-16-2383, Information Report for Lead Use Assemblies
References
NED0-33874, Rev 0
Download: ML16356A017 (26)

Text

Edwin I. Hatch Nuclear Plant Unit 2 Information Report for Lead Use Assemblies Enclosure 2 Non-Proprietary Report NED0-33874 GNF3 Lead Use Assembly

GNi=

Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GE,Toshiba, & Hitachi NED0-33874 Revision 0 September 2016 Non-Proprietary Information - Class I (Public)

GNF3 LEAD USE ASSEMBLY FOR EDWIN I. HATCH NUCLEAR PLANT, UNIT 2 Copyright 2016 Global Nuclear Fuel -Americas, LLC All Rights Reserved

NED0-33874 Revision 0 Non 7Proprietary Information - Class I (Public)

INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33874P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).

IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The design, engineering, and other information contained in this document is furnished for the purpose contained in the contract between Southern Nuclear Operating Company, Inc. and GNF, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone for any purpose other than that for which it is intended is not authorized; and with respect to any unauthorized use, GNF makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.

11

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

REVISION HISTORY Revision , Date.* Description of Change A 08/2016 Issued for Customer Review 0 09/2016 Initial Release iii

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Publi.c)

TABLE OF CONTENTS

1.0 INTRODUCTION

.................................................................................................................... 1 2.0 GNF3 FUEL PRODUCT DESCRIPTION .............................................................................. 2 2.1 New Design Features ....................................................................................... :............. 2 2.2 Water Rod ...................................................................................................................... 3 2.3 Channel .......................................................................................................................... 3 2.4 Fuel Assembly Spacer ................................................................................................... 4 2.5 Fuel Rods ....................................................................................................................... 4 2.6 Upper Tie Plate .............................................................................................................. 4 3.0 LICENSING ANALYSES ..................................................................................................... 13 3.1 Core Wide AOOs ......................................................................................................... 13 3.2 Localized AOOs .......................................................................................................... 13 3 .3 Control Rod Drop Accident.. ....................................................................................... 14 3.4 Loss-of-Coolant Accident and Emergency Core Cooling System .............................. 14 3.5 Refueling Accident ...................................................................................................... 14 3 .6 Stability ........................................................................................................................ 14 3.7 Shutdown Margin ........................................................................................................ 14 3.8 RAJ-II Shipping Container .......................................................................................... 14 3.9 Fuel Storage ................................................................................................................. 14 4.0 LUA PROGRAM OBJECTIVES ........................................................................................... 15 5.0 LUA INSPECTIONS ............................................................................................................. 16

6.0 REFERENCES

....................................................................................................................... 17 iv

NED0-33874 Revision 0 Non-Proprietary Information - Clas.s I (Public)

LIST OF TABLES Table 2-1 GNF3 and GNF2 Nominal Dimensions ........................................................................ 5 v

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

LIST OF FIGURES Figure 2-1 GNF3 Fuel Bundle Assembly ....................................................................................... 6 Figure 2-2 GNF3 Lattice Arrangements ......................................................................................... 7 Figure 2-3 GNF3 Water Rod End Plug Connection ....................................................................... 8 Figure 2-4 GNF3 Channel .............................................................................................................. 9 Figure 2-5 GNF3 Spacers ............................................................................................................. 10 Figure 2-6 GNF3 and GNF2 Upper Tie Plates ............................................................................. 11 Figure 2-7 GNF3 and GNF2 Axial Spacer Pitch .......................................................................... 12 VI

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

ACRONYMS Term Definition '

AOO Anticipated Operational Occurrence

(( )) (( ))

(( )) (( ))

BPWS Banked Position Withdrawal Sequence COLR Core Operating Limits Report CPR Critical Power Ratio CRDA Control Rod Drop Accident ECCS Emergency Core Cooling System FLR Full-Length Rod GE General Electric GNF Global Nuclear Fuel - Americas, LLC HNP-2 Edwin I. Hatch Nuclear Plant, Unit 2 LHGR Linear Heat Generation Rate LOCA Loss-of-Coolant Accident LPLR Long Part-Length Rod LTP Lower Tie Plate LUA Lead Use Assembly MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio NRC Nuclear Regulatory Commission NSF Zirconium-Tin-Niobium-Iron Alloy OLMCPR Operating Limit MCPR PCI Pellet/Cladding Interaction PCT Peak Cladding Temperature PLR Part-Length Rod RWE Rod Withdrawal Error SPLR Short Part-Length Rod SRLR Supplemental Reload Licensing Report UTP Upper Tie Plate VII

NED0-33874 Revision 0 Non-Proprietary Information- Class I (Public)

ABSTRACT Southern Nuclear Operating Company, Inc. plans to load four (4) Lead Use Assemblies (LUAs) as part of the Edwin I. Hatch Nuclear Plant, Unit 2 (HNP-2) Reload 24 Cycle 25 during the 2017 refueling outage. These bundles, also referred to as GNF3 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). Included in this report are a description of the GNF3 LUAs, a discussion of the licensing analyses, a description of the LUA program objectives, and any applicable measurements planned for the GNF3 LUAs.

Vlll

NED0-33874 Revision 0 Non-Proprietary Information- Class I (Public)

1.0 INTRODUCTION

Southern Nuclear Operating Company, Inc. plans to load four (4) Lead Use Assemblies (LUAs) as part of the Edwin I. Hatch Nuclear Plant, Unit 2 (HNP-2) Reload 24 Cycle 25 during the 2017 refueling outage. These bundles, also referred to as GNF3 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 Reference 1 that provides guidelines to be followed to license LUAs.

Included in this report are a description of the GNF3 LUAs, a discussion of the licensing analyses, a description of the LUA program objectives, and any applicable measurements planned for the GNF3 LUAs.

The GNF3 fuel design is described in Section 2. GNF3 is designed to be compatible with other General Electric (GE)/GNF fuel designs. The thermal hydraulic design closely matches the overall pressure drop of previous designs. The external envelope of the fuel assembly is compatible to the GNF2 1 fuel assembly currently supplied to HNP-2. The nuclear characteristics of these GNF3 LU As are compatible with those of the current GNF2 fuel being loaded into HNP-2.

Section 3 describes the licensing analyses that will be performed. Section 4 states the objectives of the LUA program. Section 5 describes any applicable measurements planned as part of this LUA program.

1 Description and licensing compliance for GNF2 is provided by Reference 2.

1

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public) 2.0 GNF3 FUEL PRODUCT DESCRIPTION A GNF3 fuel bundle schematic is shown in Figure 2-1. The GNF3 design consists of (( )) fuel rods and ((

)) fuel rods terminate just past the (( )) and are designated as Short Part-Length Rods (SPLRs).

Additionally, (( )) fuel rods terminate just past the ((

)) and are designated as Long Part-Length Rods (LPLRs). Eight peripheral fuel rods are used as tie rods. The GNF3 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 GNF3 channel has a ((

)) The GNF3 channel interacts with the Lower Tie Plate (L TP) (( )) to control leakage flow.

The fuel rods consist of high-density ceramic uranium dioxide or urania-gadolinia fuel pellets stacked within (( )) cladding. The cladding (( ))

providing Pellet/Cladding Interaction (PCI) resistance. The fuel rod is evacuated and backfilled with helium to (( )) atm. Fuel rod dimensions are given in Table 2-1.

2.1 New Design Features GNF3 was designed for mechanical, nuclear, and thermal-hydraulic compatibility with previous GE/GNF fuel designs. The design includes many proven features of the GElO, GEl 1113, GE12/14, and GNF2 fuel designs including PCI resistant barrier cladding, Part-Length Rods (PLRs), and a thick-comer/thin-wall channel. New or improved features included in GNF3 are

((

2

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

))

These new features have been tested for flow induced vibration performance. A discussion of each of these new design features is provided in the following sections.

2.2 Water Rod The (( )) provides neutron moderation in the top region of the bundle where in-channel void fractions are higher while ((

)) as shown in Figure 2-1 and Figure 2-2. ((

)) has also been improved in the bundle ((

)) provides for a ((

))

The GNF3 (( )) to the Upper Tie Plate (UTP). ((

)) The (( )) is connected to the L TP ((

)) as shown in Figure 2-3. ((

))

2.3 Channel

((

)) The GNF3 (( )) has a ((

)) as shown in Figure 2-4.

((

)) thus providing similar structural and in-reactor behavioral characteristics as prior channel designs. Thus, the GNF3

(( )) can be considered a ((

)). The

(( )) provides for a more effective and efficient ((

)). The interface between the (( )) and the L TP will (( )) channel-L TP interface. Thus, (( )), the leakage flow holes in the LTP are designed to provide similar overall bypass flow as GE14 and GNF2.

3

NED0-33874 Revision 0 Non-Proprietary Information- Class I (Public)

The material of the GNF3 (( )) is a zirconium alloy containing niobium (1 %), tin (1 %), and iron (0.35%) (NSF). The NSF alloy provides for enhanced resistance to channel-control blade interference. NSF is effectively resistant to fluence gradient and shadow corrosion-induced channel bow while maintaining equivalent creep bulge characteristics as Zircaloy.

2.4 Fuel Assembly Spacer The GNF3 spacer is a similar design as the GNF2 spacer. The GNF3 spacer is a ((

)), and the spacer structural material is Alloy X-750. The spacer structure is improved for ((

)) The spacer grid has ((

)) The spacer design also includes ((

))

The GNF3 fuel design includes ((

)) The GNF3 spacer is shown in Figure 2-5.

2.5 Fuel Rods The GNF3 FLRs and LPLRs are ((

))

2.6 Upper Tie Plate The GNF3 UTP has been ((

)) This was accomplished by (( )) as shown in Figure 2-6.

4

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

Table 2-1 GNF3 and GNF2 Nominal Dimensions Fuel Assembly GNF2 GNF3 Lattice array I Ox IO No change Total number of fuel rods 92 rr Number ofFLRs 78 Number of SPLRs I LPLRs 6/8 Number of water rods 2 Rod-to-rod pitch (cm) rr Typical assembly fuel mass (kgU)

Active fuel length (cm)

FLR SPLRs I LPLRs Rod length (cm)

FLR SPLRs I LPLRs Fuel Rod Cladding material Cladding tube diameter, outer (cm)

Cladding tube wall thickness (cm)

Pellet diameter, outer (cm)

Pellet stack density (g/cm3 )

Pellet density with burnable absorber (g/cm 3 )

Helium backfill pressure (atm)

Water Rod Tube material Tube diameter, outer (cm), ff 11 Tube wall thickness (cm), ff 11 11 11 Soacer Material Alloy X-750 No change Number of spacers, ff 11 8 rr 11 Axial locations Figure 2-7 Figure 2-7 Channel Material Zr-2 I Zr-4 I NSF NSF Inside width (cm) rr rr Inside comer radius (cm)

Thickness (cm)

))

((

)) ))

5

NED0-33874 Revision 0 Non-Proprietary Information- Class I (Public)

((

))

Figure 2-1 GNF3 Fuel Bundle Assembly 6

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

((

))

Figure 2-2 GNF3 Lattice Arrangements 7

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

((

))

Figure 2-3 GNF3 Water Rod End Plug Connection 8

NED0-33874 Revision 0 Non-Proprietary Information- Class I (Public)

((

))

Figure 2-4 GNF3 Channel 9

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

((

))

Figure 2-5 GNF3 Spacers 10

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

((

))

Figure 2-6 GNF3 and GNF2 Upper Tie Plates 11

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

((

))

Figure 2-7 GNF3 and GNF2 Axial Spacer Pitch 2 2

Elevations correspond to the top of the lower tab attached to the water rod.

12

NED0-33874 Revision 0 Non-Proprietary Information- Class I (Public) 3.0 LICENSING ANALYSES The GNF3 LUAs have been, or will be, analyzed using the NRC approved methods described in Reference 3. These methods are adequately capable of analyzing all of the GNF3 LUA features.

Prior to loading of the GNF3 LU As, cycle-specific analyses will have been performed for HNP-2 Reload 24 Cycle 25 to establish fuel operating limits, documented in the Supplemental Reload Licensing Report (SRLR), for the GNF3 LUAs and to ensure that the core loading has been designed such that the GNF3 LUAs will not be the most limiting fuel assemblies at any time during Cycle 25 with respect to compliance with Linear Heat Generation Rate (LHGR), Maximum Average Planar Linear Heat Generation Rate (MAPLHGR), and Minimum Critical Power Ratio (MCPR) limits based on planned control rod patterns. Furthermore, licensing analyses will be performed for the GNF3 LUAs for each cycle of their operation, wherein the effect of the GNF3 LUAs is considered for each of the appropriate licensing events and Anticipated Operational Occurrences (AOOs) to establish appropriate reactor core thermal limits for operation.

Southern Nuclear Operating Company, Inc. intends to insert the GNF3 LUAs into HNP-2 and to operate Cycle 25 under the provisions of 10 CFR 50.59; however, cycle-specific analyses to establish fuel operating limits are not yet complete. When cycle specific analyses are complete, GNF and Southern Nuclear Operating Company, Inc. will document the results in each respective SRLR. Southern Nuclear Operating Company, Inc. will update the HNP-2 Core Operating Limits Report (COLR) accordingly.

The application of approved methods to analyze events and accidents whose results could be affected by the GNF3 LUA's design is discussed below. Because the analysis of the GNF3 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 3 are considered appropriate to determine the effect of core wide AOOs on the GNF3 LUAs. The GNF3 fuel rod(s) will be analyzed with PRIME to establish steady-state, and transient overpower, LHGR limits that ensure compliance with thermal mechanical licensing requirements as specified in Reference 3. Appropriate MCPR limits for the GNF3 LUAs will be established to ensure compliance with regulatory requirements governing boiling transition. As noted in Section 2.4, ((

)) As such, (( ))

MCPR operating limits as well as core monitoring. Once a critical power correlation for GNF3 is available, the correlation will be implemented in subsequent cycles if deemed necessary.

3.2 Localized AOOs Approved methods are considered adequate to evaluate core response to a Rod Withdrawal Error (RWE) because the nuclear inputs are available to represent the GNF3 LUAs. MCPR results will be (( )) provided in Southern Nuclear 13

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

Operating Company's SRLR for Cycle 25. Once a critical power correlation for GNF3 is available, the correlation will be implemented in subsequent cycles if deemed necessary.

An evaluation was performed to estimate the effect on the Critical Power Ratio (CPR) of the Fuel Loading Error (Misoriented Fuel Bundle). Preliminary results demonstrate that the change in CPR for this event is bounded by that used to establish the Operating Limit MCPR (OLMCPR) for the GNF3 LUAs with significant margin, and therefore a Misoriented Fuel Bundle Error will not result in violation of the OLMCPR. This will be confirmed prior to Cycle 25 startup.

3.3 Control Rod Drop Accident Compliance with licensing limits governing a Control Rod Drop Accident (CRDA) is assured through adherence to the Banked 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 GNF3 LUAs and approved GE/GNF fuel designs, the Reference 3 methodology is applicable to the GNF3 LUAs. Operation with the GNF3 LUAs will not result in exceeding CRDA acceptance criteria.

3.4 Loss-of-Coolant Accident and Emergency Core Cooling System The GNF3 LUAs are to be loaded in non-limiting locations with respect to Emergency Core Cooling System (ECCS)/Loss-of-Coolant Accident (LOCA) MAPLHGR limits. An evaluation will be performed to ensure that the GNF3 LUAs will meet the Peak Cladding Temperature (PCT) requirements in the event of a design basis accident.

3.5 Refueling Accident The effect of the GNF3 LUAs on the assumptions and consequences of a refueling accident will be evaluated.

3.6 Stability The GNF3 LUAs will be evaluated in the HNP-2 Cycle 25 stability analysis as part of the standard reload licensing. Licensing requirements governing stability will be assured and the results reported in the SRLR. The HNP-2 Cycle 25 reload core will be designed such that the GNF3 LUAs will not be the most limiting bundles from a stability standpoint.

3.7 Shutdown Margin The GNF3 LUAs have been designed with approved methods to provide minimum cold shutdown margin greater than or equal to the design criteria identified in Reference 3.

3.8 RAJ-II Shipping Container Criticality safety analyses have been performed that confirm the adequacy of the RAJ-II shipping container to support the transpmiation of the GNF3 LUA fuel bundles. The NRC has granted an authorization to ship the GNF3 LUAs using the RAJ-II shipping container (Reference 4).

3.9 Fuel Storage The GNF3 LUAs have been designed with approved methods to provide ample margin to the design criteria identified in Reference 3 for GE designed fuel storage racks.

14

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public) 4.0 LUA PROGRAM OBJECTIVES The purpose of this GNF3 LUA program is to demonstrate 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.

15

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public) 5.0 LUA INSPECTIONS As currently envisioned, no measurements or inspections are planned for the GNF3 LUAs due to inspections being performed on similar features at other reactor sites.

16

NED0-33874 Revision 0 Non-Proprietary Information - Class I (Public)

6.0 REFERENCES

1. Letter, T. A. Ippolito (NRC) to R. E. Engel (GE), "Lead Test Assembly Licensing,"

MFN-182-81, September 23, 1981.

2. Global Nuclear Fuel, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," NEDC-33270P, Revision 6, March 2016.

3. Global Nuclear Fuel, "General Electric Standard Application for Reactor Fuel (GESTAR II),"

NEDE-24011-P-A-22, November 2015.

4. Letter, Michele Sampson (NRC) to Scott P. Murray (GNF), "Authorization for Shipment of the Model No. RAJ-II Package with GNF3 Lead Use Assemblies," October 31, 2014. (ADAMS Accession Number ML 14305AO 17).

17