ML19290E357
| ML19290E357 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/28/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| 800225-01, 800225-1, NUDOCS 8003110026 | |
| Download: ML19290E357 (3) | |
Text
Reissued 2/28/80 due to ormnission of Notary's sworn statement date line not completed.
6(::::;% CORSumBIS k
n Power g* ^ Company yg gp General Offices: 212 West MecNgan Avenue. Jao son MicNgan 49201. Area Code 517788-0550 February 25, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - TECHNICAL SPECIFICATIONS CHANGE REQUEST:
ECCS OPERATING LIMITS Transmitted herewith are three (3) original and thirty-seven (37) conformed copies of a request for change to the Technical Specifications of License DPR-6.
The proposed change revises operating limits based on Loss of Cooling Accident analysis to be consistent with the new analysis submitted by Consumers Power Company letter dated March 7, 1979. The proposed change also incorporates limits for single loop operations as requested by NRC letter dated October 9, 1979.
Also transmitted herewith, in support of the proposed change, find the following attachments:
Exxon Nuclear Company Report XN-NF-79-21, Revision 1, " Big Rock Point LOCA Analysis Using the Exxon Nuclear Company WREM NJP-BWR ECCS Evaluation Model -
MAPLHGR Analysis." This report describes the techniques used in deriving the proposed new limits on Maximum Average Planar Linear Heat Generation Rate (MAPLHGR).
General Electric Company Report dated March 31, 1977, " Big Rock Point Plant Single-Loop Operation Loss-of-Coolant Accident Analysis for General Electric Fuel in Conformance With 10 CFR 50 Appendix K (Non-Jet Pump Boiling Water Reactor)." This report describes the MAPLHGR limits for single loop operation.
Exxon Nuclear Company Report dated July 13, 1979, " Big Rock Point LOCA-ECCS Analysis With Delayed Start of Diesel Drive Spray Pumps." This report shows that a delay in diesel drive spray pump start from 26.9 seconds used in Exxon Report XN-NF-29-21, Revision 1, to 39.3 seconds does not affect the proposed MAPLHGR limits.
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February 25, 1980 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCATT 50-155 - LICENSE DPR BIG ROCK POINT PLANT - TECHNICAL SPECIFICATIONS CHANGE REQUEST:
ECCS OPERATING LIMITS Transmitted herewith are three (3) original and thirty-seven (37) conformed copies of a request for change to the Technical Specifications of License DPR-6.
The proposed change revises operating limits based on Loss of Cooling Accident analysis to be consistent with the new analysis submitted by Consumers Power Company letter dated March 7, 1979.
The proposed change also incorporates limits for single loop operations as requested by NRC letter dated October 9, 1979.
Also transmitted herewith, in support of the proposed change, find the following attachments:
Exxon Nuclear Company Report XN-NF-79-21, Revision 1, " Big Rock Point LOCA Analysis Using the Exxon Nuclear Company WREM NJP-BWR ECCS Evaluation Model -
MAPLHGR Analysis." This report describes the techniques used in deriving the proposed new limits on Maximum Average Planar Linear Heat Generation Rate (MAPLHGR).
General Electric Company Report dated March 31, 1977, " Big Rock Point Plant Single-Loop Operation Loss-of-Coolant Accident Analysis for General Electric Fuel in Conformance With 10 CFR 50 Appendix K (Non-Jet Pump Boiling Water Reactor)." This report describes the MAPLHGR limits for single loop operation.
Exxon Nuclear Company Report dated July 13, 1979, " Big Rock Point LOCA-ECCS Analysis With Delayed Start of Diesel Drive Spray Pumps." This report shows that a delay in diesel drive spray pump start from 26.9 seconds used in Exxon Report XN-NF-29-21, Revision 1, to 39.3 seconds does not affect the proposed MAPLHGR limits.
2 It has been determined that this proposed change involves a single safety issue and, accordingly, is classified as Class III pursuant to 10 CFR 170.22.
A check for $4,000 is attached.
Timely review and approval of this proposed change would be appreciated.
David P Hoffman (Signed)
David P Hoffman Nuclear Licensing Administrator CC JGKeppler, USNRC Attachments:
Technical Specifications Change Request MAPLHGR Analysis - Exxon BRP Single Loop Operation LOCA Analysis for GE Fuel BRP LOCA-ECCS Analysis With Delayed Start of Spray Pumps - Exxon M
BIG ROCK POINT Technical specifications Change Request f.
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1 CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technial Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 1964 for the Big Rock Point Plant be changed as described in Section I below:
I.
CHANGES A.
Change the column headings of Table 1 of Section 5.2.1.(b) to read:
Reloads Reload G Reload Reload F & Modified F G-1U G-3/G-4 B.
Change the following entries in Table 1 of Section 5.2.1.(b) as shown:
Minimum Bundle Figure 1 Dry Out Time **
Maximum Bundle Figure 2 x 0.95 Figure 2 Figure 2 Figure 2 Power, MW
- To be determined by linear extrapolation from Table 2.
For opera-tion with only one recirculating loop in service, these limits shall be reduced by 5 percent for reload F & Modified F and 10 percent for other fuel types.
C.
Replace Table 2 of Section 5.2.1.(b) with the new Table 2 attached.
D.
Delete Figure 1 of Section 5.2.1.(b).
E.
Redesignate Fieure 2 of Section 5.2.1.(b) as Figure 1.
F.
Redesignate Figure 3 of Section 5.2.1. (b) as Figure 2 and revise this figure as attached.
NOTE:
Corrected Technical Specifications pages are attached.
II.
DISCUSSION These changes revise reactor operating limits which are based on the Loss of Coolant Accident (LOCA) analysis required by 10 CFR 50.46 to be consistent with the new LOCA analysis submitted by Consumers Power Company letter dated March 7,1979 (Exxon Nuclear Company (ENC) Report XN-NF-78-53).
The derivation of new Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits using this new LOCA analysis is described in ENC Report XN-NF-79-21, Revision 1, " Big Rock Point LOCA Analysis Using the Exxon Nuclear Company WREM NJP-BWR ECCS Evaluation Madel - MAPLHGR Analysis" which is forwarded herewith.
MAPLHGR limits were not recalculated for General Electric fuel Types F and Modified F since the
2 existing limits were calculated in 1975 using General Electric integrated blowdown / fuel rod heatup analysis methods.
The limits for fuel Types F and Modified F have not been changed in the proposed new Table 2 from those currently included in the Big Rock Point Technical Specifications.
Table 1 is also modified to limit MAPLHGR for operation with a single recirculating loop.
In this case, MAPLHGR limits are reduced by 5 percent for GE fuel types and 10 percent for Exxon fuel types. These limits are based on a single loop Los; of Coolant Accident analysis performed by General Electric and described in a report dated March 31, 1977 (attached). This analysis shows that MAPLHGR limits must be reduced by 5 percent for GE fuel types, thereby showing that MAPLHGR is relatively insensitive to the flow reduction associated with single loop operation.
An equivalent analysis has not been performed for Exxon fuel; however, reducing MAPLHGR limits by 10 percent for single loop operation is believed to be quite conservative based on the insensitivity to flow shown by the GE analysis.
The proposed changes include deletion of dry out time limits for ENC fuel types (G, G-lU and G3/G4).
The dry out time limits currently included in the Technical Specifications resulted from previous ENC methodology for performing LOCA analyses. The WREM NJP-BWR ECCS Evaluation Model used in developing the proposed limits explicitly calculates fuel dry out time using the RELAP4-EM and HUXY computer codes Fuel dry out is primarily related to the bundle peaking factor at the initiation of the event; accordingly, a conservatively high radial peaking factor of 1.4 (corresponding to a bundle power of 4.0 MW ) was used in the beatup analysis.
The proposed Figure 2 has been modified to reflect this peaking factor limit.
To assure that available emergency core cooling system core spray flow is adequate to remove decay heat, Amendment 26 to the Big Rock Point Technical Specifications added limits on bunale thermal power.
As discussed in Consumers Power Company letter dated March 28, 1979, these limits were calculated using the decay heat present at the earliest time for which rated core spray was assumed in the LOCA analysis.
This time is increased in the analysis reported in KN-NF-78-53 to 26.9 seconds from the 20.4 seconds used as the basis for bundle thermal power limits.
The reduction in decay heat fraction from 20.4 seconds to 26.9 seconds is sufficient to permit an increase in bundle power limits of 4.69 percent while maintaining the same safety margin.
Proposed Figure 2 has been revised to increase bundle thermal power limits by 4.69 percent for all core bundles not otherwise limited to 4.0 MW by the radial peaking factor t
assumption discussed above.
Since GE fuel types (F and Modified F) were not reanalyzed, bundle thermal power limits for these fuel types are limited to 95 percent of the values in proposed Figure 2.
Also, as an attachment find Exxon Nuclear Company, Inc Report dated July 13, 1979 which describes the results of a " Big Rock Point LOCA-ECCS Analysis With Delayed Start of Diesel Drive Spray Pumps."
This report shows that the MAPLHGR limits established in Report XN-NF-29-21, Revision 1 (attached), remain valid when maximum allowed start time for the diesel-driven spray pump is increased from 20 to 45 seconds.
Based on these results, the acceptance criteria for the weekly diesel generator
3 start test at the Big Rock Point Plant will be relaxed to 39.3 seconds from the 26.9 seconds used in Report XN-NF-78-53 (attached).
This change also corrects an editorial error in that the dry out time limits for different fuel types were previously referenced to the wrong figure by Table 1.
The limits have been applied correctly during operation.
This change also deletes limits for fuel Type J-2 since this fuel type is not expected to be used in future cycles at Big Rock Point.
III. CONCLUSION Based on the foregoing, both the Big Rock Point Plant Review Committee and the Safety and Audit Review Board have concluded that this change is acceptable from a safety standpoint.
CONSUMERS POWER C0!!PANY By R B DeWitt (Signed)
R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 25th day of February 1980.
Linda K Carstens (Signed)
Linda K Carstens (SEAL)
Notary Public, Jackson County, Michigan My commission expires June 10, 1981.
TABLE 1 Reloads:
Reload Reload F & Modified F Reload G G-1U G-3/G-4 Minimum Critical Heat Flux Ratio at Normal Operating Conditions
- 3.0 3.0 3.0 3.0 Minimum Bundle Dry Out Time **
Figure 1 Maximum Heat Flux at Overpower, Btu /h-Ftz 500,000 395,000 407,000 392,900 Maximum Steady State Heat Flux, Btu /h-Ft2 410,000 324,000 333,600 322,100 Maximum Average Planar Linear Heat Generation Rate, Steady State, kW/Ft***
Table 2 Table 2 Table 2 Table 2 Maximum Bundle Power, MW Figure 2 x 0.95 Figure 2 Figure 2 Figure 2 e
Stability Criterion: Maximum Measured Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20 20 20 20 Maximum Steady State Power Level, MW 240 240 240 240 e
Maximum Value of Average Core Power Density @ 240 MW, kW/L 46 46 46 46 Nominal Reactor Pressure During Steady State Power Operation, Psig 1,335 1,335 1,335 1,335 Minimum Recirculation Flow Rate Lb/h 6 x 106 6 x 106 6 x 106 6 x 106 Rate-of-Change-of-Reactor-Power During Power Operation:
Control rod withdrawal during power operation shall be such that the average rate-of-c'ange-of-reactor power is less than 50 MWe per minute when power is less than 120 c;W, less than 20 MWe per minute when power is between 120 MW and 200 MW, and e
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10 MWe per minute when power is between 200 MW and 240 MW.
e e
- The bundle Minimum Critical Heat Flux Ration (MCHFR), based on the Exxon Nuclear Corporation Synthesized Hench-Levy Correlation, must be above this value.
- The actual dry out time for GE 9x9 fuel (based on the General Electric Dry Out Correlation for non-jet Pump Boiling Water Reactors, KEDE-20566) should be above the dry out time shown in Figure 1.
- To be determined by linear extrapolation from Table 2.
For operation with only one recirculating loop in service, these limits shall be reduced by 5 percent for Reloads F and Modified F and 10 percent for other fuel types.
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TABLE 2 MAPLHGR (kW/FT) LIMITS Planar Average Exposure Reload Reload Reload (MWD /STM)
Modified F Reload F Reload G G-1U G-3/G-4 0
7.21 200 9.5 9.4 360 7.62 1,000 7.95 1,630 7.56 7.81 3,810 7.57 3,900 7.65 5,000 9.9 9.7 6,440 7.28 6,620 7.50 7.48 10,000 9.9 9.7 1,880 7.17 13,520 7.49 13,610 7.56 15,000 9.8 9.6 19,050 7.11 20,000 8.7 8.6 20,320 7.56 20,870 7.78 24,580 6.84 25,000 8.4 8.3 26,400 7.32 26,760 7.64 28,210 6.08 31,210 6.73 33,020 7.12 33,380 6.69 34,470 5.73 36,290 5.73
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U Q = 22 AP U:GR L l.'3 I T X ow NU!JBER OF ACTI'/E FUEL RODS 1.0
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N 600 700 000 TOTAL BUNDLE PEAK LINEAR HEAT GENERATION RATE G(KW/FT)
FIGURE 1 FUNCTir'l T(0) FOR GE S X 0 FUEL
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2.30 3.22 3.22 3.22 3.22 2.30 3.69 h.00 h.00 h.00 h.00 3.69 2.30 3.69 h.00 h.00 3.9h 4.00 k.00 h.00 3.63 2.30 3.22 h.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 3.22 h.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 3.22 h.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 3.22 h.00 h.00 h.00 h.00 h.00 h.00 h.00 h.00 3.22 2.30 3.69 h.00 h.00 h.00 h.00 h.00 h.00 3.69 2.30 3.69 h.00 h.00 h.00 h.00 3.69 2.30 3.22 3.22 3.22 3.22 2.30 Figure 2 Maximum Bundle Power, W
XN-NF-79-21 Revision 1 Issue Date: 04/09/79 BIG ROCK POINT LOCA ANALYSIS USING THE EXXON NUCLEAR COMPANY WREM NJP-BWR ECCS EVALUATION MODEL MAPLHGR ANALYSIS Prepared by P. J. Valentine S. E. Jensen G. C. Cooke
/1 4,5 Concur:
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M-4/-19 K. P. fa braith, Manager Nuclear} Safety Engineering Concu h
bV-2 y g'Mafger G. A. So[8els Engineering e r Nuclear 4 Y ky. MW[+
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G. J.vBusselman, Manager Contract Performance
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Approved:
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/u R.INilson', Manager
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(" Licensing i
DUPLICATE DOCUMENT E
N NUCL Entire document previously entered into system under:
h ANO No. of pages:
1M BIG ROCK POINT ?LA'.iT SINGLE-LOOP OPERATION LOSS-OF-COOLANT ACCIDE:iT 12iALYSIS FOR GFl!ERAL ELECTRIC IVEL IN CONF 0P3) lice 'JITF.10CF?d0 APPEIDII E (NO.Y-JET PUMP SOILING L'ATER REACIOR)
HARCH 31, 1977 GENERAL ELECTRIC COM?.UTI h.
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of pages:
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Exxon Nuclear Company, Inc Report to Consumers Power Company July 13, 1979 s
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entered into s stem under:
k k_/.![.I' t S' ANO No. of pages: