ML20050C829
| ML20050C829 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/07/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-15-09, TASK-15-9, TASK-RR LSO5-82-04-017, LSO5-82-4-17, NUDOCS 8204090390 | |
| Download: ML20050C829 (7) | |
Text
' DESIGIiATED ORICINAL 7
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April 7,1982 9
Docket No. 50-155 s
LS05-82-04-017 C
RECEIVED
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Mr. David J. VandeWalle tra nuam u Nuclear Licensing Administrator b
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Consumers Power Company 4
p 1945 W. Parnall Road m
Jackson, Michigan 49201
Dear Mr. VandeWalle:
SUBJECT:
BIG ROCK POINT - SEP TOPIC XV-9 STARTUP OF AN INACTIVE LOOP AT AN INCORRECT TEMPERATURE In your letter dated July 15, 1981, you submitted a safety assessment report on the above topic. The staff has reviewed your assessment and our conclusions are presented in the enclosed safety evaluation report.
Our report completes this topic evaluation for the Big Rock Point Plant.
The enclosed safety evaluation will be a basic input to the integrated safety assessment for your facility. The assessment may be revised in the future if your facility design is changed or if NRC criteria rela-ting to this topic are modified before the integrated assessment is completed.
Sincerely, h_.._ m.d LI(
$ goy s
Dennis M. Crutchfield, Chief ff l
Operating Reactors Branch No. 5 y uf6 (IB) l Division of Licensing
Enclosure:
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As stated
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Big Rock Point Docket No. 50-155.
Revised 3/30/82 Mr. David J. VandeWalle CC Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
Regional Radiation Representative Judd L. Bacon, Escuire 230 South Dearborn Street
- Consumers Power Ccepany Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTN:
Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44' Charlevcix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Mr. Jim E. Mills Route 2, Box 108C Route 2, Box 108C Charlevoix, Michigan 49720 Charlevoix, Michigan 49720 William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Of fice of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Sommel Counsel for Christa Maria, et al.
Urban Law Institute Antioch School of Law 2633 16th Street, NW Washington, D. C.
20460
Big Rock Point
- Dockat No. 155 Revised 3/30/82 Mr. David J. VandeWalle CC Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 G
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SYSTEMATIC EVALUATION PROGRAM TOPIC XV-9 BIG ROCK POINT TOPIC:
XV-9, Startup of an Inactive Loop I.
INTRODUCTION
.i The st art up of an i n a c t.i v e or idle recirculation loop at an incorrect tenperature is examined to assure that the consequences are acceptable.
The guidance for the review of this topic is provided by SRP Sections 15.4.4 and 15.4.5.
This transient is evaluated because it reduces voids in the core, which causes an increase in power and reduces thermal margins.
The calculated Minimum Critical Power Ratio (MCPR) is compared to the MCPR safety limit to demonstrate that fuel failures will not occur.
II.
REVIEW CRITERIA 4, i
Section 50.34 of 10 J f R Part 50 requires that each applicant for a c on st ruc t ion permit or operating license p r ov id e an analysis and evaluation of the design and performance of structures, systense and ccrponents of the facility wit h t he objective of assessing the risk to, public hcalth and safety result ing from operation of the f ac ilit y, inc ly d ing deternination of the margins of sa f et y during n o r r. a t cperatins and transients ccnditions anticipated during the life of the f a c i l i t y.
Section 50. t of 10 C f R Part 50 requires the Technical Spec i f ic at ion s to include <afety l i.m i t s wh ic h protect the integrity of the physical barriers which guard lagainst the uncontrolled release of radicactivity.
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The General Design C rii t e r i a (Appendix A to 10 CFR Part 50) set forth the criteria for the besign of water-cooled reactors.
GDC 10 " Reactor Design" requires that the core and associated coolingr control and protecticn system be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during normal operation, including the effects of ant ic ipat ed opera-tional occurrences.
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_p-GDC 15 "Reac t or Coolant System Design" requires that the reactor coolant and associated protection systems be designed wit h sufficient margin to assure th'at the design conditions of the reactor coolant pressure boundary are not exceeded during normal operation, including the effects of ant ic ipat ed operational occurrences.
GDC 20 " Protection System f un c t ion s" requires that the protection system be designed to init iat e automatically the operation of reactivity conteol systems to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences.
GDC 26 "Reac t ivit y Control System Redundancy and C a pab il it y" requires that the r eac t ivit y control system be c a pa bl e of reliably controlling reactivity changes to assure that under c ond it ion s of normal opera-tion, inc l ud ing anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck r;ds, specified acceptable fuel design limits are not exceeded.
GDC 28 "Reac t ivit y L im it s" requires that the reactivity control sys-tems be dcrigned with ogpropriate limit s on the potential arount and rate of reac t ivit y increase to ensure that the ef f ect s of postulated reactivity ac c ident s can neither (1 ) result in da. age to the rcactor coolant pressure boundary greater than limited local yielding nor (2) su f f ic ient ly disturb the core, its support st ruc tures or other reactor pretture vessel in t e rna l s to impair significantly the capa-bilit y to cool the core.
III.
REIATED SAFETY TOPICS Various other SEP topics evaluate such items as the reactor protection system. The ef f ects of single f ailure on saf e shutdown capability are considered under Topic VII-3.
- - _ - - =.
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l IV.
REVIEW GUIDELINES The review is conducted in accordance with SRP 15.4.4 and 15.4.5.
The evaluation includes review of the analysis for the event and identification of the features in the plant that mitigate the consequences of the event as 4
well as the ability of these systems to function as required. The extent to which operator action is required is also evaluated. Deviations from the cri-teria specified in the Standard Review Plan are identified.
1 V.
EVALUATION j
The startup of an inactive loop was analyzed for the Big Rock Point plant in the reference below.
The more important assumptions were:
i 1.
Init ial power is 102% of singte loop cperating j
power (188.7 MWt )
i 2.
Water in isolated loop is at 100 r 1
i 3.
Scram initiated on high flux (120% power) 4 Conservative reac t iv it y coe f fic ient s and scram charact erist ic s are used 1
i S.
Pump in idle loop reaches full speed in 1 second, bypass and discharge valves open sequentially at i
design speed These and other a s sumpt i on s de sc r ibed in the reference are in accordance with the SRP.
The computer code used in the analysis I
is COBRA-IV-I nodified for the big Rock Point plant.
i l
The result s of the analysis show that the peak power of 127 % in it ial value is reached 8.25 seconds after initiation of the The l
reactor pressure r ises 19 psi to 1349 psia, which is belt,Jesign pressure.
The mininum critical power ratio wa s 1.7 7, which is abeve j
the specified acceptable fuel design limit for MCPR (1.32).
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_4-VI.
CONCLUSION The staf f has reviewed the big Rock Point submittal on SEP Topic XV-9, Startup of an Inactive Loop. The assumptions used in the analysis are in conformance with SRP Sections 15.4.4 and 15.4.5 and the results satisf y the SRP acceptance criteria and are therefore, acceptable.
REFERENCE:
Letter to D. Crutchfield, NRC from R. A. Vincent, Consumers Power l
Company, " Big Rock Point Plant - SEP Design Basis Event Topics",
dated July 15, 1981.