ML17053A758
| ML17053A758 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/28/1979 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML17053A757 | List: |
| References | |
| 79NED266, NEDO-24185, NUDOCS 7906290600 | |
| Download: ML17053A758 (30) | |
Text
NEDO-24 185 79NED266 Class I April 1979 NINE MILE POINT NUCLEAR POWER STATION UNIT 1 EXTENDED LOAD LINE LIMIT ANALYSIS LICENSE AMENDMENT SUBMITTAL (CYCLE 6)
..V. Woodford, dr. Ergioeer Operating Licenses II Approved: R.I O. J~
Brugge, Manager Operating Licenses II NUCLEAR ENERGY PROJECTS OIVISION ~ GENERAL ELECTRIC COMPANY SAN JOSE, CALIFORNIA95125 V9063O0 goo
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NEDO-24185 0 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY This report was prepared by'General Electric solely for Niagara Mohawk Power Corporation.(NMPC) for i&PC's use with the U.S. Nuclear Regulatory Commission (USNRC) for amending NMPC's operating license of the Nine Mile Point Nuclear Power Station Unit 1. The information contained in this report is believed by General Electric to be an accurate and true representation of the facts known, obtained, or provided to General Electric at the time this report was-prepared.
The only undertakings of the General Electric Company respecting information in this document are contained in Niagara Mohawk Power Corporation Purchase Order No. 69545 dated 1/29/79 as amended by exceptions noted in General Electric memorandum'dated 2/20/79 for analysis for the nuclear system for Nine Mile Point Nuclear Power Station, Unit 1, and nothing contained in this document shall be construed as changing said agreement. The use of this information except as defined by said agreement, or for any purpose other than that for which it is intended, is'not authorized; and with respect to any such unauthorized use, neither- General Electr'c Company nor any of the contributors to this document makes any representation or warranty (express or implied) as to the completeness, accuracy, or usefulness of the informa-tion contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such infor-mation.
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- 1. INTRODUCTION Previous analyses (References 1 and 2) provided the analytical bases for operation under a modified power/flow line designed toenable the direct ascension to full power within the design bases previously applied.
This submittal provides results of analyses which justify operation up to 100%
of- rated power at 91% of rated coze flow. The analysis results aze provided in the same sequence as the standard reload format to assure that all aspects of reactor operation which are affected are covered. Future reload submittals will incorporate the use of the extended load line in the analysis.
- 2. ANALYSIS RESULTS 2.1 Plant-Unique Items Not Affected 2.2 Reload Fuel Bundles Not Affected 2.3 Reference Core .Loading, Pattern Not Affected 2.4 Calculated Core Effective i~fultiplication and Control System Worth-No Voids, 20'C Not Affected 2.5 Standby Liquid Control System Shutdown Capability Not Affected 2.6 Reload-Unique Transient Analysis Inputs - Affected by Additional Data as Shown
I NEDO-24185 Transient Analysis Inputs EOC EOC-1000 HWd/t EOC-2000 ~md/t Void Coefficient N/A,"'6.85/-8.56 -7.58/-9.48 -8.67/-10.84 (c/% Rg)
Void Fraction (%) 37-. 42 37.42 37.42 Doppler Coefficient N/A -0.233/-0.222 -0 '28/-0 '16 -0,222/-0.210 (c/% 'F)
Avg Fuel Temperature ('F) 1204 1204 1204 Scram Vorth N/A ($ ) -36.83/-29.47 -35.61/-28.49 -33.73/-26.99 Scram Reactivity Figure la Figure lb Figure lc
- N = Nuclear Input Data A = Used in Transient Analysis 2.7 Reload-Unique GETAB Transient Analysis Initial Condition Parameters Affected by Additions as Shown Unique GETAB Transient Analysis Initial Condition Parameters 100K Power/91X Flow gx8 8xgR Peaking Factors Local l. 22 1.22 1 ~ 22 1.20 1.20 1.20 Radial 1.676 1.704 1.704 1 ~ 822 1.850 1.850 Axial 1.4 1.4 1.4 1.4 1.4 1.4 R-Factor 1. 102 1.102 1.102 1.051 1.051 1.051 Bundle Power (Mwt) 5.707 5.802 5.802 6.201 6.294 6. 294 Bundle Flow (10 lb/hr) 93.34 92.67 92.67 89.53 88.96 88.96 Initial MCPR 1.22 1 ~ 20 1.20 1.22 1 ~ 20 1 ~ 20 2.8 Selected Margin Improvement Options' Not Affected
P 4'vv.i 5e) % <<' <<lA,+Q "p4r 't .< i ides~=., 'i)i s>> & ) 4 s .. i lJ
NEDO-24185 2.9 Core-Hide Transient Analysis Results Affected by Additions as Shown Core-Wide Transient Analysis Results sP 4CPR Plant PoxXer Core PloM Q/A -
Dome V Transient ~EE os xs ~X ~X ~XR 8) ~(X R 8 ~s) ) ~S 8 8/ExER ~Rss o s Turbine Trip xt/o EOC 94.3 91 20885 99 ' 1193 1227 0.15 Pigure 2a Bypass Turbine Trip xt/o EOC-1000 98 ~ 0 91 168.4 98.7 1190 1224 0.06 Pigure 2b Bypass MWd/t Turbine Trip v/o EOC-2000 100 91 139. 5 100.0 1179 1213 <0.01 Figure 2c Bypass MWd/t 2.10 Local Rod Withdrawal Error (With Limiting Instrument Failure) Transient Summary Affected by Additions as Shown Local Rod Withdrawal Error (With Limiting Instrument Failure)
Transient Summar Rod 'ACPR LHGR Rod Block Position Limiting
~RRRRXR Feet Withdrawn 8x8 8x8R 8x8 8x8R Rod Pattern 104 -8.0 0.30 '.25 13.77 15.69 Figure 3 105* 8.5 0.32 0.27 13.90 15.90 Figure 3 106 9.0 0.33 0.30 14.00 16.06 Figure 3 107 9.0 0.33 0.30 14.00 16.06 Figure 3 108 9.5 0.34 0.32 13.93 16.03 Figure 3 109 9.5 0.34 0.32 13.80 16.03 Figure 3
- Rod Block Setpoint 2.11 Operating HCPR Limit Not Affected 2.12 Overpressurization Analysis Summary Conservative analysis (EOC case) shows that operation of the plant, in accordance with the extended load line, limit does not violate the vessel overpressure pro-tection criteria. Calculated peak pressures are at least: 25 psi below the cri-teria of 1375 psig.
2.13 Stability Analysis Results Not Affected
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NEDO-24185 2.14 Loss-of-Coolant Accident Results Potential Effects Explained A discussion of low flow effects on LOCA analyses for all operating plants (Ref-erence 3) has been presented to and was approved by the NRC (Reference 4). With the flow-dependent restrictions imposed by Reference 4, the LOCA analysis refer-enced in the plant/cycle specific reload submittal is applicable in the power flow domain discussed in this submittal.
2.15 Loading Error Results Not Affected 2.16 Control Rod Drop Analysis Results - Not Affected
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NEDO-24185 REFERENCES
- 1. "Nine Mile Point Nuclear Power Station Unit 1 Load Line Limit Analysis License Amendment Submittal", NED0-24012, May 1977.
- 2. "Supplemental Reload Licensing Submittal for Nine Mile Point Nuclear Power Station Unit 1 Reload No, 7 Reanalysis Supplement", NED0-24155-1, Supple-ment 1, December 1978.
- 3. Letter, R.L. Gridley, to D.G. Eisenhut (NRC), "Review of Low Core Flow Effects on LOCA Analysis for Operating BWR's", Nay 8, 1978.
- 4. Letter, D.G. Eisenhut (NRC) to R.L. Gridley, enclosing "Safety Evaluation Report Revision of Previously Imposed MPLHGR (ECCS-LOCA) Restrictions for BWR's at Less Than Rated Flow", May 19, 1978.
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NEDO-24185 45 CONTROL ROO DRIVE VERSUS TIME SCRAM REACTIVITYVERSUS TIME 40 60 35 70 30 67A CRO IN PERCENT 25 Po I I I
Z 50 O I O
CO os O 20 cc CL 40 30 NOMINALSCRAM CURVE IN {-S) 10 20 SCRAM CURVE USEO IN ANALYSIS 10 3
TIME (seconds)
Figure la. EOC Scram Reactivity
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NEDO-24185 45 CONTROL ROD DRIVE VERSUS TIME SCRAM REACTIVITYVERSUS TIME 90 40 80 35 70 30 60 I
K 67A CRD IN PERCENT 25 j
0.
I 2 50 0
I- b CO 04 20 40 15 NOMINALSCRAM CURVE IN (-S) 30 10 20 SCRAM CURVE USED IN ANALYSIS 10 0
0
.- TIME (seconds) .
Figure 1b. EOC-1000 HWd/t Scram Reactivity
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NEDO-24185 100 45 CONTROLROD DRIVE VERSUSTIME SCRAM REACTIVITYVERSUS TIME 90 40 35 70 30 67A CRD IN PERCENT 25 Q I I I
50 I b CO O 20 0
40 NOMINALSCRAM CURVE IN (-S) 15 30 10 20 I
SCRAM CURVE USED IN ANALYSIS 10 0 0 0
TIME beconds)
Figure 1c. EOC-2000 MWd/t Scram Reactivity
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2 AVE 3 COAF.
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)EAT FLM FLUX I VESSEL PfIES RISE tPSI) 2 SfFHY VALVE FLOH 3 M.IEF VALVE FLOH 0 BYPASS V VE FLGH 100.
- 0. 0.
0 4. 8.- 12. 16. 0 8. 12. 16.
TINE tSK) TINE tSK) oI 1 LEVEL 2 VESSEL t INN~-SEP-SKIRT
~~11~ STEi8FLOH 10 RE TI VITY 2 OOPPLS)t ACTIVITY gj 'TL AasCI PM J 3 Sf~ RF ACT)V)TY 00 PFEEt)HATE FL15I '0TA~L YIV17V It)0. 0.
0.
-100. 2e
- 0. 4. 8. 12. 18. 0 8. 12. 16.
TINE tSK) TINF tSEC)
Figure 2a. Nine Nile Point-1 Turbine Trip Without Bypass, Trip Scram, EOC
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I )%MBA LUX I VESSEL PCS RISE (PSI) 2 AVE SURF BEAT FLUX 2 SUETY VA.VE FLQ(
150. 3 C0(K IHLI T FLOH 3 BELIEF V Q hYF~
100.
p K
100.
- 0. 0.
0 8. 12. 16. 0 8. 12. 16.
TIHE (SEC) TIRE (SEC) l4 ot7I I LEVEL(1 H)EF-SEP-SKIRT TIVITY 2 VE%R. S EAHFLQH ACTIVITY 3 TUHDIHE 7EAYFLGH TIV17Y 00 UVEEQTB 3-LN (l TDTAL TIVIIV co 100. 0 0.
-100.
- 0. 8. 12. 16. 0. 8. 12, 16.
TIVE (SEC) TIRE (SEC)
Figure 2b. Nine Mile Point-1 Turbine Trip Without Bypass, Trip Scram, EOC-1000 MWd/t
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1 NEUTAt)H LUX I VESSEL S BISE (PSI) o 2 AVE SUAF - SKAT FLUX 2 SAFETY V VE FLOH t 3 CSK I 150. T FLOM MA~ KVCN 3 ACLIEF V VE FLOH
- 0. 0.
0 4. 8. 12. 16. 0 5. 12. 16.
TIHE ISEC) TIRE (SEC)
CI 1 LEVEL(I -BEF-SEP-SKIRT VOTO TIYITT oI 2 VESSEL S EAHFLOH 2 OOPPLEA ACTI YlTY 3 TUBB I HE TEAHFLOM 3 SCBAH BEACTI YITT MEEOHATEI FLIR 4 TOTR. AE CTI Vl lT 00 100. 0.
W 5
PJ 0.
I 5
-100.
0 8. '2.
TIHE (SEC)
- 16. 0 8.
TI)IE ISEC)
- 12. 16.
Pigure 2c. Nine Nile Point-l Turbine Trip Without Bypass, Trip Scram, EOC-2000 >IWd/t
p NEDO-24185 02 06 10 14 18 22 26 00 47 28 43 16 16 39 00 00 35 16 36 38 31 00 00 08 27 16 38 36 NOTES: 1. ROO PATTERN IS I/4 CORE MIRROR SYMMETRIC.
UPPER LEFT QUADRANT IS SHOWN ON MAP
- 2. NUMBERS INDICATE NOTCHES WITHDRAWN OUT OF 48. BLANK IS A WITHDRAWN ROD
- 3. ERROR ROO IS 18,31 Figure 3. Limf.ting Rod Pattern 12
ATTACHMENT C Niagara Mohawk Power Corporation License No. DPR-63 Docket No. 50-220 Amendment Classification
'The proposed amendment to the operating license has been evaluated and determined to fall within the definition of Class III of 10 C.F.R. 170,22 thereby requiring a fee of four thousand dollars (SO,O0O.O0).
The proposed amendment for Nine Mile Point Unit 1 involves only a single safety issue. Therefore, it meets the requirements of Class III of 10 C.F.R. 170.22.