ML20086K519
| ML20086K519 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/31/1991 |
| From: | Melissa Crawford SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML19353B429 | List: |
| References | |
| EMF-88-182(NP), EMF-88-183(NP)-S01, EMF-88-183(NP)-S1, NUDOCS 9112130150 | |
| Download: ML20086K519 (23) | |
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l SIEMENS EMF-88-183(NP)
Supplement 1 Siemens Nuclear Power Corporation Grand Gulf Unit i Reload XN-1.3, Cycle 4 Mechanical Design Report Supplement 1 October 1991 i
Siemens Nuclear Power Corporation
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Siemens Nuclear Power Corporation i
EMF 88183(NP) l Supplement 1 i
Issue dato:
10/21/91 GRAND GULF UNIT 1
)
RELOAD XN 1.3 CYCLE 4 MECHANICAL DESIGN REPORT SUPPLEMENT 1 Prepared by:
A Ys l0'/A 91 M. L Crawford Project Engineer Mechanical Design Engineering Fuel Design
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CUSTOMER DISCLAIMER IMPORTANT NOTICE REGARDING CONTENTS AND USE OF THIS DOCWENI Pt. EASE READ CAREFULLY 4
Seemens Nudear Power Corporaton's warranoes and representanons asocoming me sub,oct maner of ttwo document are those set forth m the Agreement tstween Seemens Nudear Power Corporaton and the Customer pursuant to which this document is issued. Accorengly, except as otherwise expressly provided in suen Agrooment, rather Semens Nudear Power Corporsoon nor any person acting on its behalf makes any warranty or representaton. espressed or empbed, with respect to be accuracy, compioneness, or usefulness of the informacon contamed in this document, or that the use of any intwmason apparatus, method or process o
diodosed in mes document wel not intnnge pnvately owned nghts; of assumes any liebelrtes weh respect to the use of any informaoon, apparatus, method or process desdoned in thse document.
The informaton contained herom is for the solo use of the Customer, in order to toad imparment of nghts of Semens Nudear Power Corporabon in patents or inventons whidt may be inducted in the informaton contained an this document, me recipent. by ris acceptance of this document, agrees not to pubhsh or make putsc use (in the patent use of me term) of sudiinformaton untd so authorged in wneng by Siemens Nudoar Power Corporneon or unni aber six (6) months fotowmg norminston or expreson of the aforossad Agreement and any extension thereof, unless expressh provided in the Agreement. No nghts or licenses an or to any patents are imphed by me fumiehing of this document 6
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Supplement 1 Pagei GRAND GULF UNIT 1 PELOAD XN 13 CYCLE 4 MECHANICAL DESIGN EPCPT SUPDLEMENT1 TABLE OF CONTENTS gaetion Titte Pace
1.0 INTRODUCTION
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SUMMARY
2 2.1 Design Description Summary 2
2.2 Mechanical Design Summary 2
1 3.0 DESIGN CRITERIA..........
5 4.0-MECHANICAL DESIGN 6
4.1 Fuel Rod Analyses 7
4.1.1 Maximum Cladding Strain During Steady State Operation 7
4.1.2 Maximum Cladding Stress During Steady State Operation...
7 4.1.3 Anticipated Operational Occurrences Analysis.
S 4.1.4 Fuel Rod internal Pressure.
8 4.1.5 Fuel Pellet Centerline Temperature 9
4.1.6 Fuel Rod Cladding Fatigue 9
4.1.7 Cladding Collapse..........
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EMF-88183(NP)
Supplement 1 Page il TABLE OF CONTENTS (Continued)
Section Title Paco 4.1.8 Fuel Rod Spacing 10 4.1.9 Cladding Corrosion and Hydrogen Concentration 11 4.2 Fuel Assembly Evaluation 11 4.2.1 Structural Strength........................
11 4.2.2 Spacer Spring 11
- -4.2.3 Assembly Growth 12
5.0 REFERENCES
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EMF-88183(NP)
Supplement 1 Pago ill TABLE OF FiGUAES Section Titre Pace 4.1 LHGR Umit For 8x8 Fuel 33
' 4.2 Protection Against Fuel Fadures Umut During ACO's Fct 8xe Fuet 34 l
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EMF-88183(NP)
Supplement 1 Page1 GRAND GULF UNIT 1 13EkQAD XN.1.3. CYCt.E 4 MECHANICAL DESIGN REPORT SUPPLEMENT 1
1.0 INTRODUCTION
This report provides a summary of an evaluation, applicable to the Siemens Power Ccrperation (SNP) 8x8 fuel for the Grand Gulf Unit 1 Nuclear Power Re XN 1.3. The analyses support an extension of the assembly exposure and a modification of the mechanical LHGR limits The meenanical design of Grand Gulf 1 XN 1.3is essentially the same as th Type 4/5/6 design; tnus, several of the mechanical design related sections of covered by specific references to generic mechanical design reports Where applicab analyses have been extended, consistent with SNP's generically approved metho the increased ournup and the revised mechanical LHGA limit.
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EMF-88183(NP)
Supplement 1 Page 2 2.0
SUMMARY
The SNP 8x8 fuel design for Grar d Gulf 1 XN-13 has been evaluated to allow operation up to a peak assembly exposure with a mechanical LHGR limit The results of the evaluaticn..*ic?te that all design enteria are met.
The fuel mechanical desjn description is summar' zed below.
2.1 Cesion Cescriotion Summary The SNP ex8 assemoly design for Grano Gulf 1 XN 1.3 reload censists of 62 fuei r:ds and two centrally located water rods. one of wnich functions as a spacer capture rod. Seven scacers maintain fuel rod spacing. The design also uses a quick-removable upper tie plate design to facilitate fuelinspection and bundte reconstitution cf irradiated assemblies.
The fuel rods are Zircaloy 2.claccing, 35 mits inick. The rods are pressurizeo, ar.c contain either UO 'Gd 0 or UO fuel pellets witn a nominal density of 94.5% of the theeret:ca!
2 23 2
density. The fuel rods contain two possible diametrical pellet to clad gap sizes 9.5 mils or S.5 mi!s. Natural uranium axial fuel blankets, at the tcp and the bottem of ine fuel column, are provided for greater neutron economy.
The SNP 8x8 fuel design for Grand Gulf 1 XN 1.3 reload includes two minor cesign modifications which allow higner fuel exposures. The snanks on the upper end caps and tne spacer capture rod lower end cap have Deen lengthened to increase their engagement in the tie plates. The lower tie plate seal has also been redesigned to increase the length of engagement of the seal with the fuel channel. These modifications were incorporatee to accommodate increased differential growth, between the fuel assembly and channel, and the fuel assembly and the fuel rods, which results from the higher assembly exposure.
2.2 Mechanical C"icn Summary The mechanical design analyses were performed to evaluate etadding steady state strain and stress, transient strain and stress, fatigue damage, creep co!! apse, corrosion, hydrogen l
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EMA88183(NP)
Supplement 1 Page 3 absorption, fuel rod internal pressure, fuel temperature, cifferential fuel red growth, creep tow, and spacer grid design. The analysas justify irradiation to Major analysis results are:
The maximum end of life (EOL) steady state efaccing strain is calculated to t:e colow tne 1.0% des gn limit.
Cladding steady state stresses are calculated to be below the material strength limits.
The cladding strain during anticipated operational occurrences (ACOs) does not exceed 1.0%.
The maximum fuel rod internal rod pressure remains below SNP's criteria limit.
The fuel centerline temperature remains below the m?lting point during ACOs.
, The cladding fatigue usage factor is within the 0.67 design limit.
Structural members have adequate strength to support handling and hycraulic leacs.
Compliance with inis criterien prevents the forniation of fuel ~ column gaps, and the possibility of creep collapse.
Evaluations of assembly growth and differential fuel rod growth show that the desigr' provides adequate c!earances for compatibility with me fuel assembly enannel. Also, there is adequate engagement of the end caps in the upper tie plate and lower tie plate throughout the design life.
The ir.itial fuei red design spacing is expected to be adequate tr., accommocate expected rod to rod gap closure for the fuel design life.
1 EMF-88183(NP)
Supplement 1 Page 4 The maximum EOL reducson in cladding thickness due to corrosion and the maxiinum concentration of hydrogen in the claddirig ar6 calculated to be we!! within the design limits.
The fuel rod plenum spring and other miscellanecus components are shown to meet the respective design bases.
The spacer springs meet all the design requirements, ano can accommedate the expected relaxation at ECL L
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Supplement 1 Page 5
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3.0 DESIGN CRITERIA The detailed Siemens Nuclear Power Corporation design ente 1.3 reload fuelis given in Reference 1.
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EMF 88183(NP)
Supplement 1 Page 6 4.0 MECHANICAL DESIGN Three reports have previously been issued to document the mechanical cesign analyses for the Grand Gulf 1 SNP 8x0 fuel. These reports are:
XN NF 83 25, Revisien 1.
Grand Gulf 1 XN 1 Design Repcrt Me" *snical Thermal Hydraulic, and Neutronic Design for Exxon Nuclear JP BWR/6 Fuel As.
,. r g issued in August 1983:
XN NF 85 67 (P)(g" evision 1," Generic Mechanical Design For Exxon.. #ar Jet Pump BWR Reload Fuel
, issued in Septemcer 1986; and ANF 88-183 (P)," Grand Gulf Unit 1 Reload XN 1.3, Cycle 4 Meenanical Cesign ReportM issued November 1988'.
The analyses in the first repen were performed with the RCDEX2 computer cede and justified irraciation Fuel rod analyses repcrted in tne generic mechanical desian recort were oerformed usino the computer code RCCEX2A and justified irradiation t Both RCCEX2 and RCCEX2A codes have been approved for generic application by the NRC.I2'0) The generic meenanical
-design report was submitted and approved for generic use by the NRC in 1986.
The Grand Gulf Unit 1 Reload XN 1.3, Cycle 4 mechanical design report extenced the fuel assembly burnup
. This document reports the results of design calculations performed to support higher fuel assembly exposure and a slightly modified LHGR mechanical limit than has been reported previously. The fuel red calculations in this report used the RCOEX2A computer code.
The fuel assembly has been analyzed to a peck assembly exposure and peak rod and peak pellst exposures respectively. These values are conservative estimates of the maximum exposures to ce reached with the Grand Gulf 1 XN 1.3 8x8 reload fuel. The analyses have been performed assuming a design power history identical to that used in Reference 1, at low to medium exposures and a
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EMF-88183(NP)
Supplement 1 Page 7 slightly modified power history at higher exposures. This slightly modified power history was generated from the modified LHGR mechanicallimit curve shown in Figures 4.1 and 4.2.
4.1 Fuel Aod Analvsos Fuel rod analyses, where required. have teen performed to verify adequate performance of the fuel The fuel rod and peak pellet exposures useo in tne analyses were respectively. The design power history used in Reference 1 was modified at higher exposure values for Grand Gulf 1. The LHGR mechanicallimits in Reference 1 have also been mcdified for Grand Gulf 1. The analyses results reported here demonstrate compliance witn the design criteria.
4.1.1 Maximum Claddino Strain Durino Steady State Ccerat!cn The maximum cladding strain during steady state operation is limited to <1% The analyses have been performed with RCDEX2A. Ths results indicate that the strain is below 1*'a.
in Figure 3.8 of Reference 1, the cladding strain is depicted up to a rod nodal exposure strain is below the design limit.
4.1.2 Maximum Claddino Stress Durino Steadv State Oceration Fuel rod cladding stresses during steady state operation are calculated elasticity theory. The design stress limits ato in accordant:o witn the ASME pressure vessel code.
i EMF 88183(NP)
Supplement 1 Page 8 The assumptions made in the stress analysis reported in Reference 1 have been reviewed.
16e review indicates that the original assumptions made in perforr"v g the analysis (e.g., internal red pressure, clad thinning, etc.) still bouno the conditions at the higher excesure and mocif ed operating powers. Consequently, the analysis res'ults rer.,orted in Table 3.3 of Reference 1 are applicable.
4.1.3 Anticiented Ocerational Occurrences Analysis Two design criteria are impcsed en the fuel redu to avoid fuel failure during power changes caused by anticipated operational occurrences (ACOs). The enteria are to limit the cladding strain to less than 1% and to insure that the maximum pellet centerline temperature remains below the pellJt melting point. The AOCs are assumed to produce a maximum red riod:' pnwer equal to those defined in Figure 4.2.
Using the methodology described,in Reference 1, an analysis was performed with the mechanical LHGR limits in Figure 4.2 The results of the analysis verity that the cladding strain and fuel temperatures meet the design enteria for ACOs within the defined power limits.
4.1.4 Fuel Aod internal Pressure.
The fuel rod internal pressure is limited
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EMF-88183(NP)
Supplement 1 Page 9 Using the methodology described in Reference 1, an analysis was per10rmed using the modified LHGR limits The results of the analysis indicate that the maximum internal pressure remainc below the design criteria 4.1.5 Fuel Pellet Centerline Temocrature The design criteria requires that fuel centerline temperature remain colow the fuel melting
' point during operation. A fuel pellet centerline temperature analysis was performed using the methodology described in Reference 1 while applying the modified LHGR limit curve ano higher exposure level. The results of the analysis indicated that the fuel pellet centerline temperature will remain below the fuel melting point. Therefore, the design enteria is met.
-4.1.6 Fuel Red Claddino Faticue Fuel assembly shuffling, reactor power maneuvering, and ACOs will impose a cyclic loading on the cladding. The design criteria requires that the calculated cyc!ic fatigue usage factor remain within 0.67 times the cladding fatigue life.
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EMF-88183(NP)
Supplement 1 Page 10 To assure that the fuel rcd does net fail due to stress cyclic fatigue, a fatigue an performed. The results of the analysis show that the cumulative fatigue damage remain the 0.67 limit.
4.1.7 Claddina Celtaose Fuel failures due to cladding collapse have been observed in some PWR's in fuel recs designed and fabricated by other fuel vendors. No SNP fuel rod has over failed due to this mechanism. The likelihood of a fuel rod failing due to cladding collapse in a BWR reac smalldue to the lower operating coolant pressure of the Grand Gulf 1 reactor compared to th in a PWR. Nevertheless, the fuel rods are analyzed to assure that fuei red collapse will n The pellet con sietes densification during early operation. >
The analysis results reported in Table 3.1 of Reference 1 are still appucacle for the extended exposure.
- 4. t. 8 Fuel Aod Soaqing The design cri aria states that changes in rod.to rod and rod to-channel gaps must be -
taken into account in establishing the thermal limits. Thermal limits are not affected if the minimum rod to-rod gap is greater The analysis performed in Reference 1 to calculate the maximum fuel rod bow has been evaluated for applicability at higher exposures
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l EMF 88183(NP)
Supplement 1 Page 11 design criteria will remain.
Therefore, a significant margin to the 4.1.9 Claddino Cerrosien and Hydrocen Concentratien The design criteria for cladding corrosion limits metal;oss due to cerrosion H drogen absorption is limited y
Reference 1, an analysis was performed.
tJsing the methodology in The results of the analyses indicated that the cladding corrosion and hydrogen absorption will remain well below the design criteria.
4.2 Fuel Assembly Evaluatter The performance of the fuel assembly has been evaluated. The structural strength, spacer design, and assembly growth have been investigated as follows.
4.2.1 Structural Strencth The structural strength of tio plates, locking meenanism, and tie rods is not de with exposure or with minor modifications in the LGHR mechanical limits. The an results previously reported in Reference 1 are applicable.
4.2.2 Soncer Sarino SNP data indicates that spacer springs relax with irradiation. The observations i that the relaxation rate decreases with increased exposures and that it tends to satu exposures.
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l EMF 88183(NP)
Supplement 1 Page 12 It is therefere cenciuced that the scacer spring design is acceptable 4.2.3 Assembiv Growth The design er,teria requires that the red end caps remain engaged in the tie plates and that the lower tie pl.*'
W spring remain engaged in the fuel channes throughout the life of the fuel assembly. E.. growth is exposure dependent, the minimum engagement will occur at the EOL Assembly growth was determined by evaluating differential growin between stancard fuel rods and non fuel rods and the tie rods. Additionally, an evaluation of channel engagement with the lower tio plate seal as a function of irradiation exposure was reviewed. The calculatiens indicate that sufficient channel and end cap engagement are present to ECL 4
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Supplement 1 Page 13 e
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EMF 88-183(NP)
Supplement 1 Page 15
5.0 REFERENCES
1.-
" Generic Mechanical Design for Exxcn Nuclear Jet Pump BWR Reload Fuel", XN NF 85 67(P)(A), Revision 1, September 1986, 2.
"RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Cece. XN NF 81-58(NP)(A), Supplement 1 & 2 Revision 2, Maren 1984 3.
- RODEX2A Fuel Red Thermal Mechanical Evaluation Model". XN NF 85 74(F)(A).
August 1986.
" Grand Gulf 1 XN 1 Design Report, Mechanical, Thermal Hydraulic and Neutronic Cesign 4
for Exxon Nuclear JP BWR/6 Fuel Assemblies *, XN NF 83 25. Revision 1. August 1983.
5.
" Qualification of Exxon Nuclear Fuel for Extended Burnup (SWR)', XN NF 82 06(P)(A).
Supplement 1,4 and 5, November 1985.
6.
XN NF 82-06(P)(A), Supplement 1, Revisien 2. "Cualification of Exxon Nuclear Fuel fer Extended Burnup', May 1988.
7,
" Grand Gull Unit 1 Reload XN 1.3 Cycle # Mechanical Design Reporta, ANF 88-183(F).
November 1988.
EMF 88183(NP)
Supplement 1 Issue date:10/21/91 GRAND GULF UNIT 1 RELOAD XN 1.3, CYCLE 4 MECHANICAL DESIGN REPORT SUPPLEMENT 1 Distribution S. L Leonard (8)
Document Control l
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> 0 to GNRO-91/00186
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