ML20065R612
| ML20065R612 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/30/1990 |
| From: | Charnley J, Hansen E GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19310D014 | List: |
| References | |
| 23A6492, 23A6492-R, 23A6492-R00, NUDOCS 9012190105 | |
| Download: ML20065R612 (19) | |
Text
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o ENCLOSURE 1 SUPPLEMENTAL RELOAD LICENSING SUBMITTAL FOR PNPP RELOAD 2, CTCLE 3 l
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GENuclearEnemy 115 Curtner Annue 23gS492 SonJose, CA 95125 '
Revision 0 Class I
) September - 1990 -
23A6492, Rev. O Supplemental Reload Licensing Submittal p for Perry Nuclear Power Plant Unit 1
- Reload 2 Cycle 3
-3 y
)
a
' A'pproveh) '^ Approved: /h AE& '
J. . Charnley, Manage E. C. Ilansen, Manager
) Reload Nuclear Engineering lpel Licensing x
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y
) Perry 1 nam 2 Reload 2 new o Important Notice Regarding Contents of This Report Please Read Carefully t
The only undertakings of the General Electric Company (GE) respecting information in this document are contained in the contract between Cleveland Electric Illuminating Company (CEI)
> and OE, and nothing contained in this document shall be construed as changing the contract. The
. use of this information by anyone other than CEI for any purpose other than that for which it is intended,is not authorized; and with respect to any unauthorized use, GE makes no representation or warranty, and assumes no liability as to the completeness, accuracy or usefulness of the p information contained in this document.
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l Page 2 D
O Perry 1 2w.m Reload 2 ner o Acknowledgment O
The engineering and reload licensing analyses which form the technical basis of this Supple-mental Reload Licensing Submittal, were performed by P. A. Hahn and J. L. Casillas of the Fuel O Engineering Section. The Supplemental Reload Licensing Submittal was prepared by P. A.
Lambert and verified by J. L. Embley of Regulatory and Analysis Services.
O O
O O
O A.
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'O Page 3 O
- o. . Perry 1 moo 2 Reload 2 Rev,0 1 Plant unique Items'(1.0)*
O: A Ppendix A:- Analysis Conditions Appendix B: Basis For Analysis of Loss of feedwater Heating Event Appendix C: Analyzed Operating Domain a 2. Reload Fuel Hundles (1.0 and 2.0)
Fuel Tvne Cycle Loaded Number O Irradiated:
BP8 SRB 219 1 64 "
BP8 SRB 176 1 140 **
BS301E 2 136 O BS301F 2 136 New:
GE8B P8 SOB 320 90Z-120M 150 T 3 104
.O GE8B P8SQB322 70Z 120M 150 T 3 .MS Total 748
_ .3. l Reference Core Imding Pattern (3.2.1)
' Nominal previous cycle core average exposure at end of cycle: 16,436 mwd /MT Minimum previous cycle core avera
. from cold shutdown considerations:ge exposure at end of cycle M,105 mwd /MT g; ' Assumed reload cycle core average exposure at end of cycle: 18,357 mwd /MT Core loading pattern: Figure 1
~
- O
. ( ) refers to area of discussion in GeneralElectric Standard ApplicationforReactorFuel, NEDE 24011-P A 9, September,1988; a letter "S" preceding the number refers to the U.S.
- Supplement, NEDE 24011 P A 9 US, September 1988.
' 'y-s "4 BP8 SRB 219 fuel bundles and 140 BP8 SRB 176 fuel bundles were removed for the second cycle; these fuel bundles are to be reinstalled for the third cycle.
Page 4 0
O Perry 1 2mm Reload 2 Rev.o i
- 4. Calculated Core Effective Multiplication and Control System Worth No Volds,20 C (3.2.4.1 and 3.2.4.2)
O Beginning of Cycle, K,y,,
Uncontrolled 1.127 Fully controlled 0.953 O
Strongest control rod out 0.985 R, Maximum increase in cold core reactivity with exposure into cycle, AK 0.003
- 5. Standby Liquid Control System Shutdown Capability (3.2.43)
Boron Shutdown Margin (AK)
(prJD) (20'C. Xenon Free)
O M0 0.029
- 6. Reload Unique GETAB AOO Analysis initial Condition Parameters (S.23)
Exposure: BOC3 to EOC3 O Fuel Peakine Factors Bundle Power Bundle Flow Initial Design IEal Radial Adal B Factor _.1MWt) (1.000 lb/hr) MCPR GE8x8EB 1.20 1.55 1.40 1.051 7.239 117.5 1.17 BP8x8R 1.20 1.54 1.40 1.051 7.166 117.1 1.18 O
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Page 5 0
): Perry 1 ause Reload 2 ney. o
- 7. Selected Margin Improvement Options (S.S.I)
); Recirculation pump trip: Yes Rod withdrawallimiter: Yes Thermal power monitor: Yes Measured scram time: No Exposure dependent limits: No
)l Exposure points analy ed: 1 (EOC)
- 8. Operating Flexibility Options (S.5.2) j-Single loop operation: Yes Load line limit: No Extended load line limit: No Increased core flow: Yes j Flow point analyzed, %: 105 i Feedwater temperature reduction: Yes
- ARTS Program: No Maximum extended operating domain: ~ Yes 9.' Core-wide AOO Analysis Results (S.2.2)*
. Methods used: GEMINI and GEXL PLUS
, . ACPR
. Flux O/A Event (% NBR)(% NBR) GE8x8EB BP8x8R Figure Exposure range: - BOC 3 to EOC 3 Load rejection without 280 108 0.06- 0.06 2 bypass f; Feedwater controller 203 112- 0.10 0.10 3-failure (143%)
Pressure regulator 150 105 0.05 0.05 4 failure downscale Loss of 100'F " " 0.11 "
0.11
- feedwater heating
' Limiting values listed; see Appendix C.
" See Appendix B.
Page 6 y
O Perry 1 - umn Reload 2 Rev. 0
- 10. Local Rod Withdrawal Errcr (With Limiting Instrument Failure) AOO Summary
- (S.2.2.1.5) '
O-The generic bounding BWR/6 rod withdrawal error is analyzed in NEDE 24011.P A 9.US and GESSAR II Appendix 15B is applied; the resulting ACPR is 0.11. The original generic analysis in GESSAR II was not applicable for control cell core operation; however, it was g; subsequently shown to be applicable for control cell core operation and GESSAR II was revised to reflect this application in Revision 21.
- 11. Cycle MCPR Values * (4.3.1 and S.2.2)
O Safety limit: 1.07 Exposure range: BOC 3 to EOC 3 O Non-oressurization events:
GE8x8ED BP8x8R
- Rod withdrawal error 1.18 1.18
- g Loss of 100*F feedwater heating 1.18 1.18 Pressurization events:-
Ontion A O GE8x8EB BP8x8R Load rejection without bypass 1.13 1.13 Feedwater controller failure 1.18 1.18 l0 l
Pressure regulator failure downscale 1.13 1.13 o
O l
- GEMINI ODYN adjustment factors are provided in the letter from J. S. Charnley (GB) to M.
W. Hodges (NRC), GEAflNI ODYN Adjustment Factorsfor BWR/6, dated July 6,1987. The
~O.
MCPR limit does not change because of channel bow. Channel bow is reflected in the manitoring of the core.
l-Page?
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p Perry 1 aswn Reload 2 Rev. 0
- 12. Overpressurization Analysis Summary (SS)
> Pd Pv Event (plig) (psic) Plant Response MSIV closure (flux scram)* 1226 1258 Figure 5 p 13. Ioading Error Results (S.2.2.3,7)
Loading error results are not applicable for BWR/6 plants. NRC approval of the non applicability of Loading Errors to BWR/6 plants is documented in Section S.2.2.3.7 of p hTDE 24011 P A 9 US.
- 14. Control Rod Drop Analysis Results (S.2.23.1) p Banked Position Withdrawal Sequence is utilized at the Perry Nuclear Power Plant Unit 1; therefore, the bounding control rod drop analysis (CRDA) described in NEDE 24011 P A 9 US is applied. NRC approval of the bounding analysis is given in the letter to J. S. Charnley (GE), Acceptance for Referencing of Licensing Topical Report p NEDE 240ll, Revision 6, Amendment 9 'GESTAR-il General Electric Standard Application for Reactor Fuel," January 25,1985.
- 15. Stability Analysis Results (SA)
D GE SIL 380 recommendations have been included in the Perry Nuclear Power Plant Unit 1 operating proceduies and/or Technical Specifications and, therefore, the shbility analysis is not required. NRC approval for deletion of a cycle specific stability analysis is documented y in Amendment 8 to NEDE 24011 P A 9 US. In addition, the I my Nuclear Power Plant Unit I recognizes the issuance of NRC Bulletin No. 88-07, Wpplement 1, Power Oscillations in Boiling Water Reactors (BWRs), and will continue to comply with the recommendations contained herein.
D
'The MSIV closurkflux scram) analysis is performed using GEMINI methods at the 102% power level to account for the power level uncertamties specified m Regulatory Guide 1.49. The analysis
, was performed with 13 highest setpoint safety valves operational.
Page8 D
)? Perry 1=. a.u u n :
Reload 2 - nev o 16.' Loss of. coolant Accident Results (S.2.2.3.2)
)j LOCA method used: SAFE /REFLOOD (see the Perry Nuclear Power Plant Unit 1 Updated Safety Analysis Report, as amended)
Bundle'I)pe: GE8B P8 SOB 320 90Z 120M.150-T(GE8X8EB)* ,
),
Average Planar Ernosure_ MAPLHOR (kw/ft)
(GWd/ST) - (GWd /MT) Most Limiting Least Lirnhing 0.0 0.0 11.75 11.76
)
0.2 0.2 11.78 11.79 1.0 1.1 11.83 11.90 2.0 2.2 -11.91 12.00 -
3.0 33 12.02 12.13
)
4.0 4.4 . 12.17 12.27 5.0 5.5 12.32 12.40 6.0 6.6 - 12.44 12.53 7.0 7.7 12.56 12.67 1 8.0 8.8 12.70 12.82 9.0 9.9 12.84 12.96 10.0 11.0 12.97 13.07 12.5 13.8 13.00 13.03
).--
15.0 16.5 12.73 12.74 20.0 22.0 12.10 12.12.
'J.0 27.6 11.48 11.49 35.0 38.6 10.23 10.24
)-
45.0- 49.6 - 8.66 - 8.68 50.0 55.1 6.16 '6.18 The Peak Clad Temperature (PCF) is $2105'F at all exposures; the Local Oxidation (Fraction) is
)' '.
50.049 at all exposures.
T
'MAPLHGR multiplier for single-loop operation (SLO) is 0.80.
E Page 9 f
).c .. Perry 1 uwe .
Reload 2 Rev.0
- 16. ' 14ss of coolant Accident Results (S.2.2.3.2) (continued)
I Bundle Type: GE8B P8 SOB 322 70Z 120M 150 T(GE8x8EB)*
Average Planar Exnosure MAPLHOR (kw/fti
"); (GWd/SD (GWd/MT) Most Limiting Least Limiting 0.0 0.0 12.11 12.13 0.2 0.2 12.10 12.13 1.0 1.1 12.09 12.14
)* 2.0. 2.2 12.16 12.22 3.0 3.3 12.28 12.35 4.0 4.4 12.42 12.51-5.0 - 5.5 12.58 12.67
) 6.0 . . 6.6 12.67 12.77
. 7.0 7.7 12.75 12.86
- v. 8.0 8.8 12.83 12.95 9.0 9.9 12.92 13.04 10.0 11.0 13.02 '13.11 12.5 13.8 - 13.07 13.09
'15.0 16.5 12.79 12.79
- 20.0 - 22.0 12.19 - 12,19 25.0' - 27.6 11.56 11.56 35.0' 38.6 10.29 10.30 45.0 49.6- - 8.77 8.80 50.0 55.1 6.27. 6.30 l~ Th'e Peak Clad Temperature (PCT) is $2100'F at all exposures; the Local Oxidation (Fraction) is
= $0.048 ata' ll exposures..
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- MAPLHGR multiplier for single loop operation (SLO) is 0.80.
Page 10
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': mesMs+sM M Msme eMBEMMMMMMMe 3: mHMMMMMMMMMMe
- " eH M M M M M M M +8 HE+sM Me
- -m8MBEMBEMs+sMMMMMME+sse 3
irMMMMMMs+sMMMs+sHMMM i:MBEMH8+sMs+sHMMs+8MMMM
, irMMMMMBE9EMMMMMB8MM
:M M BsBEM M BsM M M M M8+88+ss+8
';:BEMMs+88+sMBEMMMM8sMEs+a
'r*8M MBsM ME+8M M MBEM M8+sE" "M M Ms+EB8M M M M M M M M"
- M M M M s+2 8 8 H M M M M S "MMMMMMMMM*
- *"sMMMMHs IIIIIIIIIIII
) 1 3 5 7 911131517192123252729313335373941434547495153555759 l FUEL TYPE
) A = BP8 SRB 176 E = BS301E
.B = BP8 SRB 219 F = GE88-P8SQB322-7GZ-120M-150-T C'= BP8 SRB 219 0 = GE88 P8SQB320-9GZ-120M-150-T D = BS30lf
) Figure 1 Reference Core IAading Pattern Page 11
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); Perry 1 mu,3 Reload 2 g,7 o
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=4.. . ... ... %. ... . ...
i m (wcoes) tie (ucoes) 3 Figure 2. Plant Response to load Rejection without Bypass
)
Page 12 D-
Perry 1 m e.m Reload 2 ney o l
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t= (n:oos) a < t= (x: cs>
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Figure 3. Plant Response to Feedwater Controller Failure Page 13
_ - . - -~- _. . -
3 Perry 1 , m92 Reload 2 Rev 0
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I Na - ,,, ! MiEkir' a ,.
K 2
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.... ... .. .. ::: ...= =: L_ 1.: \
titt (KC046) 13E (ECDOS) l i sce.sm) i voi
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... . .. n. ... n, titt (Ecmes) flic (Ecoes) y Figure 4. Plant Response to Pressure Regulator Failure Downscale l
Page 14
Perry I nwv2 Reload 2 ney o kekNT* ,,
l(M 4 e45 3!I!fv""
ved ru I
E a ='.
- m. %
- N we n.
..s.. ... .g. :: . ::= ; ::,..; ; :: :
TIE (Ecots) flE (EC006)
}(s0I NEP"U "'
$ e,wtj*!!li?
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ty E
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fin (E 3(5) tis (scocs)
I Figure 5. Plant Response to MSIV Closure, Flux Scram p
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Page 15 I
)_ . Perry 1- zuun Reload 2 Rev.0' Appendix A D:
- Analysis Conditions 3_ To reflect actual plant parameters accurately, the values shown in Table A 1 were used this cycle to reflect the bounding conditions.
Table A 1 .,
D-Analysis Value Pararneter 250'F FW Temp. 420'F FW Temo.
3: Thermal power, MWt 3579 3579 Dome pressure, psig 1008 1026 Rated steam flow, Mlb/hr 12.58 15.40 Turbine pressure, psig 974 976 Core flow, Mlb/hr 109.2 109.2 Reactor pressure, psia 1056 1056 Inlet enthalpy, Btu /lb -512.4 528.8 Non fuel power fraction - 0.038 0.038 D
No, of dual mode Safety / Relief Valves 17* 17*
Relief mode lowest setpoint, psig 1143* 1143*
- - Safety mode lowest setpoint, psig 1177- 1177
'3)
- )
E *There are a total of 19 valves; the 2 lowest setpoint safety / relief valves are assumed to be out of service in the transient analyses.
Page 16 j)
) Perry I nAun Reload 2 Rev j}
Appendix B 4 b
Basis for Analysis of Loss of feedwater Heating Event b The loss of feedwater heating event was analyzed using the BWR Simulator Code (Reference B 1). The use of this code is permitted in GESTAR 11 (Reference B 2). The transient plots, neutron flux and heat flux values normally reported in Section 10 are not an output of the BWR Simulator code; therefore, these items are not included in this document.
D The transient analysis inputs normally reported in Section 6 of the licensing submittal are internally calculated in the BWR Simulator Code and in ODYN.
I References B1 Stea@ State Nuclear Afethodr, NEDE-30130 P A and NEDO 30130 A, April 1985.
B2 General Electric Standard Application for Reactor Fuel, NEDE 24011 P A 9, September 1988.
D D
D D
D Page 17 B
D- Perry 1 mm2 Reload 2 new o
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Appendix C D
Analyzed Operating Domain e The core wide abnormal operational occurrence (AOO) analysis results reported in Section 9 are the most limiting values over the entire allowable operating range. This range covers the following operating options:
g 1. Standard 100% power / flow map;
- 2. End of cycle power coastdown; g 3. MEOD with 100% power flow range from 75% to 105% of rated; and
- 4. Partial feedwater heating to 320*F during the cycle with final feedwater temperature reduction to 250*F after AllRods out at end of cycle.
9 Limiting events and conditions analyzed are based on Reference C 1 and the USAR analytical results. The Reload 2/ Cycle 3 analyses were performed assuming all four turbine control valves in a full are mode of operation. This is conservative for partial are configuration.
9 The single loop operation (SLO) analysis was reverified for the standard power / flow map with normal feedwater temperature.
- References C-1 General Electric Standard Application for Reactor Fuel, NEDE 24011 P A 9.US, September 1988.
O O
Page 18 (Final) 9
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