ML19282C621
| ML19282C621 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/28/1979 |
| From: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19282C622 | List: |
| References | |
| NUDOCS 7903300398 | |
| Download: ML19282C621 (5) | |
Text
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T Consumers hlPOV/Br C, 1 M Company
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Ger* oral OMacer 212 West Macnegan Avenue, Jackson, Michsgsan 49201. Area Code S17 783 OSSO March 28, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Recctors Branch !!o 2 US Nuclear Regulatory Co= mission
'4ashington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLAUT - TECHUICAL SPECIFICATI0I!8 CHA'!GE REQUEST:
EMERGENCY CORE C00LI:iG Forwarded 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 adds a limit on therm' power for each fuel bundle to ensure that available emergency core coo.'ing flew is always sufficient.
Also forwarded herewith is Apperdix V to General Electric Report HEDC-2197h " Big Rock Point Core Spray Sparger and Steam Baffle Design Report." This appendix reports the results of full-scals testing of the Big Rock Point energer r core cooling sparger ring.
These te',t results were used in developing t'.a proposed bundle power limits as descrioed in the attached request for change.
General Electric Report NEDC-219Th and its Appendices I through IV vere previously for-varded by Consumers Power Company letters dated Iiovember 21, 1978 and January:16, 1979 Your prcmpt approval of I!EDC-2197h and this Technical Specifications change request is needed to support plant start-up at the end of the current refueling outage.
Plant start-up is currently scheduled for April 17, 1979 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 $h,000 is attached.
e!
b1xg David A Bixel nuclear Licensing Administrator CC JGKeppler, US:iRC 7s733003W m
CONSUMERS POVER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical Specifi-cations 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 es described in Section I below:
I.
CHANGES A/l an entry to Table 1 of Section 5.2.l(b) reading:
a.
" Maximum Sundle Power, M'4 Figure 3 Figure 3 Figure 3 Figure 3" t
~
b.
Add a new Figure 3 to Section 5 2.l(b) as shown in the attached.
Note: Corrected Technical Specifications pages are attached.
II.
DISCUSSION The proposed change adds bundle thermal power limits which are intended to ensure that the flow provided by either of the two emergency core cooling spray systems vould be adequate in the event of a loss of cooling accident (LOCA).
The minimum flow available from the redundant core spray system based on full-scale test data was described in Consumers Power Company letter dated September 19, 1977 The results of full-scale testing of the original core spray system (as modified) are reported in Appendix V af General Electric Report NEDC-219Th which is forwarded as an attachment to this Technical Speci-fications change request. General Electric Report HEDC-21974 and its Appendices I through IV, which describe modifications made to the original core spray system and the associated test program, vere forwarded by Consumers Power Company letters dated November 21, 1978 and January 16, 1979 The bundle thermal power limits proposed in this change request were developed to insure that emergency core cooling spray flow is available at each core loca-tion to carry away, with margin, the decay heat as computed in the LOCA analysi; for the plant.
A single minimum av_ilable spray flow, for all vessel conditions, was determined at each core location by taking the minimum of:
- 1) The measured sparger spray flow to each location from the confirmatory tests (Figure 26 of Appendix V to NEDC-2197h).
- 2) The desired (design target) spray facv to each location as defined in Appendix I (Figure 1) to UEDC-2197h.
i
2
- 3) The minimum measured redundant nozzle spray flow to each location from the combined steam entry and bottom-only steam entry tests at 25, 50, and 75 psig (Consumers Power Company letter lated September 19, 1977).
Each break size in the break spectrum from the LOCA analysis was considered.
Tha decay heat fraction (P/Po) at the earliest time for 'thich rated spray was assumed and the vessel conditions (h,, V ) at the time af rated spray were These,alongwiththefkBvratesdeterminedabove,wereusedto f
determined.
compute a maximum bundle power such that the minimum available spray flow could remove, by evaporation alone (hg ), at least 1.2 times decay heat.
Decay heat was calculated based on the corr $lations of proposed American National Standard
" Decay Energy Release Rates Following Shutdown of Uranirm-Field Thermal Reac-tors" supplemented by the calculated decay heat contribution of principle radio-active actinides Uranium-239 and Neptuniur z39 No credit was taken for the subcooling of the spray water.
The design basis accident (rated spray at 20.4 seconds with reactor vessel pressure of 25 psig) was found to dictate the lowest allcvable bundle power.
The riser break (rated spray at 30.8 seconds with reactor vessel pressure at 75 psic) was, however, only slightly less limiting.
III. CONCLUSIONS Based on the foregoing, both the Big Rock Point Plant Eeview Committee and the Safety and Audit Review Board have concluded that this change is accept-able from a safety standpoint.
CONSUMERS PO'4ER COMPANY By C-M C R Bilby, Vice Prep'ijienc Production & TransmMsion Sworn and subscribed to before me this 28th day of March 1979 O ) k d2 d u
fainda R Thayer, Nota 7y Public Jackson County, Michigan My Commission expires July 9, 1979
h3 TABLE 1 Reloads:
Reload Reload Modified F & J-2 Reload G G-lU 3-3 Minimum Critical Heat Flux Ratio at Normal Operating Conditions
- 3.00 3.00 3.00 3.00 tunimum Bundle Dry Cut Tine **
Figure 1 Figure 2 Figure 2 Figure 2 Maximum yeat Flux at Overpower, Stu/h-Ft" 500,000 395,000 h07,000 392,900 Maximum Steady State Heat Flux, Btu /h-Ft2 h10,000 32h,000 333,600 322,100 Maximum A' erage Planar Linear Heat Generation Rate, Steady State, kW/Ft***
Table 2 Table 2 Table 2 Table 2 Maximum Bundle Power, MW Figure 3 Figure 3 Figure 3 ligure 3 Stability Criterion: Maximum Measured Zero-to-Peak hux-Amplitude, Percent of Average Operating Flux 20 20 20 20 Maximum Steady State Pover Level, MW 2hD 2ho 2h0 2h0 Maximum Value of Average Core Power Density @ 2h0 MW, kW/L h6 h6 h6 h6 t
Nominal Reactor Pressure During Steady State Power Operation, Psig 1335 1335 1335 1335 Minitum Recirculation Flow Rate, Lb/h 6 x 10' 6 x 10 6 x 10 6 x 10 6
Rate-of-Change-of-Reactor Power During Power Operation:
Control rod withdrawal during power operation shall be sucP that the everage rate-of-change-of-reactor power is less than 50 LM Der ndnute when power is less than 12) EM.,
less than 20 MWt per minute when power is fatveen 120 an 200 MW., and 10 MW E*#
minute when power is between 200 and 2h0 MW.
t g
- The bundle Minimum Critical Heat Flux Ratio (MOHFR), based on the Exxon Uuclear Corporation Synthesized Hench-Levy Correlation, must be above this value.
- The actual dry out time for each bundle (based en the General Electric Dry Out Correlation for Honjet Pump boiling Water Reactors, UEDE-20566) should be above the dry out time shown in Figure 1 or 2, as appropriate.
- To be determined by linear extrapolation fren Table 2.
h3D IiORTH I
2.20 3.08 3.08 3.08 3.08 2.20 3.52 h.18 h.ho h.ho h.18 3.52 2.20 3.52 h.18 h.ho 3 76 h.13 h.ho 4.18 3.h7 2.20 3.08 h.18 L.ho h.h0 h.ho h.ho h.ho h.ho h.18 3.08 3.08 h.ho h.13 h.ho h.2h h.2h h.ho h.13 h.ho 3.08 3.08 h.h0 h.13 h.ho h.2h h.2h h.L0 h.13 h.ho 3.08 3.08 h.18 4.ho h.ho h.ho h.ho h.h0 h.h0 h.18 3.08 2.20 3.52 h.18 4.ho h.13 h.13 h.ho h.18 3.52 2.20 J
3.52 h.18 h.ho h.h0 h.18 3.52 2.20 3.08 3.08 3.08 3.08 2.20 Figure 3 Maximun Bundle Fcver, W
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