ML20030A564
| ML20030A564 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/11/1975 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101100062 | |
| Download: ML20030A564 (3) | |
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- Docket 50-155 Division of Reactor Licensing Licence DPR-6 US Nuclear Regulatory Commission Washington, DC 20555 Big Rock Point Plant Gentlemen:
On October 11, 1974 Consumers Power Company requested an exten-sion until April 1, 1976 for submittal of any ATWS consequence analysis.
By letter dated October 29, Consumers Power Company was requested to sub-mit an explanation for the delay and a schedule of the detailed plan for completing the analysis :.nd Consumers Power Company review. On November 12, 197h, consumers Power Ce pany responded with the requested information.
l The prime reason for the delay in the submittal of the ATWS analysis was that General Electric Company (our consultant performing the analysis) vill not have personnel avellable to perform analysis on oper-ating plants until after completion of their analysis for BWR in WAS!!-1270 Category B.
In addition, the BWR-1 plants (which includes Big Rock Point) were scheduled to be done following the BWR-3 and BWR-2 plants. Thus, work could not be commenced on the BWR-1 plants until May 1975 Cn February 24, 1975 representatives of Consumers Power Company, General Electric and the Regulatory Staff met in Bethesda to discuss the schedule for submittal of the ATWS consequence analysis. These discussions concluded that the consequence analysis could be completed and submitted to the US Nuclear Regulatory Commission by October 1, 1975 It was con-cluded at that time thTt the schedule for the analysis could be shortened by use of uisting transient analysis information for the Big Rock Point Plant an<'. use of analyses already performed on other BWR to determine the most liw. lag transients for purpoces of the ATWS consequence analysis.
These possibilities were not considered on October 11 when the request for extensior. to Apt'l 1, 1976 was submitted.
Thus, Consumers Power Company hereby withdraws its October 11, 1974 ATWS consequence analysis extension request and now requests an extension for submittal of this analysis until October 1, 1975 The scope of the analysis to be submitted October 1,1975 is as follows:
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Divition of Rscetor Lictn22ng 2
Dockst 50-155 License DPR-6 March 11, 1975 1.
Establishment of appropriate initial operating conditions, operating parameters and expected performance of key components.
2.
Review of latest abnormal transient analysis ' submittal (s) for selec-tion of appropriate events for ATWS consideration.
3.
Selection of worst case and estimation of power, vessel pressure and
. steam relief flow variations for case with failure to scram. Use of currently documented safety valve sizing analysis is expected.
h.
Evaluation of impact of potential alleviating actions such as pump trip and ooison initiation.
5 Calculatic i of containment pressure trend following worst assumed event (s).
Const ers Power Company has concluded that approval of this extension reqaest will not result in an increased risk to the health and safety of the public. As stated in our October.11,197h letter, the con-sequences of the worst ATWS appeared to be within the design pressure of the primary coolant boundary. The steam drum safety valves were sized to limit the pressure resulting from a coincident steam shutoff with fail-ure to scram (see Sections 12.5.8, 12.12.6 and Figure 12.10 of the Final
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Hazard Summary Report for the Big Rock Point Plant). These previous eval-uations show that the peak transient pressure, assuming the unlikely event
' did occur, would be less than the reactor vessel design pressure. The validity of this analysis has been confirmed by comparison with analyses performed on never BWRs.
Further evaluation of the event, assuming it were to occur, re-veals several mitigating actions are available to plant operators that will preclude damage to the containment pressurc boundary. These actions include the ability to manually reduce the power level by tripping recir-culation pumps, the ability to manually trip the reactor (described in the
" Reactor Protection System Common Mode Failure Analysis" submitted for the Big Rock Point Plant in October 197h) and the ability to actuate the liquid poison system to shut down the reactor. Review of consequence analysis perforned on other BWRs and extrapolation to the Big Rock Point Plant re-veals that adequate time exists for the operator to recognize the required actions and initiate them.
Yours very truly,
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NRC Dw(RIBUTION FOR PART 50 DOCKE'i iATERI AL (TEMPORARY FORM)
CONTROL NO: 2 W/
FILE:
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Consumers Power Company DATE OF DOC DATE REC'D LTR TWX RPT OTHER Jackson, Mi 3-11-75 3-13-75 XX RR Sewell TO:
ORIG CC OTHER SENT AEC PDR XX DL one signed SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXXXX 1
50-155 DESCRIPTION:
ENCLOSURES:
Ltr re our request feo ATWS info......
requesting a change in the date of their scheduled submittal of ATWS criteria....
PLANT NAME:
Big Rock Point FOR ACTION /INFORMATION 3-13-75 ehr BUTLER (L)
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FILE:
h' ROM: Exxon Nucicar Co.
DATE OF DOC DATE REC'D LTR TWX fiPT 01HER vichland, Wash. 99352
.' thomas W..Crale 7-28-75 8-1-75 XX TO:
ORIG CC OTHER SENTlac PDR xx DRL 1 signed SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
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50-155 DESCRIPTION: Ltr trans the following:
ENCLOSURES:
"Heatup Analysis for Exxon Nuclear Company, Inc. G Fuel in the Big Rock Plant in conformance with 10CFR50, Appendix K" da ted 7-26-75....
(40 cys, enc 1 rec'd) 3 cys enc 1 rec'd 8-1-75 & addl 37 cys rec'd later on 8-1-7,5,...
PLANT NAME: Big Rock Point Plant
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