ML20052A697
| ML20052A697 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 03/23/1982 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Longenecker J ENERGY, DEPT. OF |
| References | |
| NUDOCS 8204290043 | |
| Download: ML20052A697 (5) | |
Text
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,s Distribution DocketFile.j March 23, 1982 NRC PDR
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CRBR Reading fjf
'A Docket No.:
50-537 R. Stark
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- d. D ' 4 C. Thomas P. Check G4 F
- ;"~" / d" Mr. John R. Longenecker P. Wu m
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h Licensing and Environmental Coordination W, Foster
- a Clinch River Breeder Reactor Plant P. Shuttleworth k Q
U. S. Department of Energy, HE-561 E. Tomlinson
-gh Washington, D.C.
20545 i %
Dear Hr. Longenecker:
SUBJECT:
CLINCH RIVER BREEDER REACTOR PLANT, REQUEST FOR ADDITIONAL INFORMATION As a result of our review of your application for a construction pemit for the Clinch River Breeder Reactor Plant, we find that we need addi-tional information in the area of Chemical Engineering. Please provide your final responses by April 19, 1982.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is not required under P.L.96-511.
If you desire any discussion or clarification of the infomation requested, please contact R. H. Stark, Project Manager (301) 492-9732.
Sincerely.
Original Signed by Paul S. Check Paul S. Check, Director CRBR Program Office Office of Huclear Reactor Regulation
Enclosure:
As stated cc: Service List 820429 coy 3 pm(
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Dr. Cadet H. Hand, Jr., Director Barbara A. Finamore Bodega Marine Laboratory S. Jacob Scherr University of California Ellyn R. Weiss P. O. Box 247 Dr. Thomas B. Cochran Bodega Bay, California 94923 Natural Resources Defense Council, Inc.
Daniel Swanson 1725 I Street, N.W.
Office of the Executive Suite 600 Legal Director Washington, D.C.
20006 U. S. Nuclear Regulatory Consnission Eldon V. C. Greenberg Washington, D.C.
20555 Tuttle & Taylor 1901 L Street, N.W.
William B. Hubbard, Esq.
Suite 805 Assistant Attorney General Washington, D.C.
20036 State of Tennessec Office of the Attorney General L. Ribb 450 James Robertson Parkway LNR Associates Nashville, TN 37219 Nuclear Power Safety Consultants 8605 Grimsby Court William E. Lantrip, Esq.
Potomac, MD 20854 City Attorney Municipal Building P. O. Box 1 Oak Ridge, TN 37830 George L. Edgar, Esq.
Morgan, Lewis & Bockius 1800 M Street, N.W.
Washington, D.C.
20036 Herbert S. Sanger, Jr., Esq.
General Counsel Tennessee Valley Authority Knoxville, TN 37902 Chase Stephens, Chief Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Raymond L. Copeland Project Management Corp.
P. O. Box U Oak Ridge, Tennessee 37830
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ATTACHMENT k
ADDITIONAL INFORMATION REQUIRED BY CHEMICAL ENGINEERING BRANCH FROM CLINCH RIVER BREEDER REACTOR PLANT DOCKET NO. 50-537 CS 281.1 Degradation of CRBR fuel cladding may be caused by (a) selective leaching (4.2) of nickel and chromium due to sodium exposure, (b) formation of double oxides and intergranular attack by sodium corrosion, (c) loss of mechant-cal strength due to loss of carbon and nitrogen, or (d) fission product attack on cladding internal surface.
In your cladding strain and Cumulative Damage function Analysis of the cladding integrity, you assumed uniform cladding wastage.
Provide additional cladding performance analysis including the effect of localized attack and the loss of strength, due to interstitial transfer and the formation of a ferrite layer on the cladding surface, to demonstrate that the cladding integrity will be maintained under normal operating and design basis accident conditions.
i CS 281.2 In the PSAR you state that the design objective of the primary control I
(4.2) rod system (PCRS) is to achieve a service life of minimum of 17,000 ft.
travel and 732 scrams.
To improve the resistance to wear and friction, carbide coating was applied on certain FCRS component surfaces.
Describe the design criteria and limits established for maximum carbon transfer in the primary coolant system due to the presence of carbide coating.
Include in your analysis the problem of carburization of the fuel cladding surface which leads to cladding embrittlement due to the use of chromium carbide on the coupling head of PCRS.
CS 281.3 Carbides formed by Nb and Ti in the Alloy 718 are thermodynamically more (4.2) stable than the chromium carbides formed in the type 316 SS fuel cladding.
Provide analyses that the presence of Inconel 718 in the CRBR core reginn would not lead to decarburization and subsequent loss of strength of the fuel cladding.
l CS 281.4 On page 5.3-16 of the PSAR you state that sodium leak tests have shown (5.3) corrosion rates of steam generator tubes by Na-water reaction product; e.g. Na0H, to be 0.12 mils /hr at 1050 F,1000 vppm H2O and 1.2 v/o 02 or less, and this accelerated corrosion from the presence of water vapor and sodium is acceptable in that propagation of a leak from corrosion at this rate will not sign;ficantly affect plant capability to safe shutdown and maintain safe shutdown conditions.
Provide the technical basis and l
analysis for the above statement, and demonstrate the validity of leak before break criteria in your analysis.
CS 281.5 The heat transport system liquid metal (Na and NaK) chemistry is selected (5.3, to minimize corrosion and to ensure the fuel cladding integrity and to 9.3) prevent radiation leakage.
In the PSAR you state that periodic analyse.
I of the liquid metal chemistry is performed to verify that the Na and NaK quality meets the proposed specification.
The liquid metal purity is l
maintained by the use of cold traps.
Describe the freguency and chemical and radiochemical analysis to be performed for liquid metal analysis, and l
l the criteria ir cold trap replacement to ensure the liquid metal qualit y l
meets the prowsed specifications.
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CS 281.6 In the CRBR primary and intermediate sodium piping system, Fe, Cr, and (5.3)
Ni are dissolved from the high-temperature regions and deposited in the lower temperature regions because of super saturation.
Included in this process of mass transfer is the formation and decomposition of various transition metal and sodium double oxides.
Deposition of these mass transfer and corrosion products may cause flow restrictions and loss of heat transport efficiency of heat exchangers.
Describe the criteria and bases in your analyses of mass transfer and deposition of corrosion products in the CRBR primary and IHX sodium systems to assure necessary system flow and heat transfer.
Include the instrumentation and detection system which will alarm when these limits are exceeded.
CS 281.7 Provide a Failure Mode and Effects Analysis (FMEA) to demonstrate that (5.5) the sodium dump subsystem of the CRBR steam generating system is designed such that no single failure of the isolation and dump equipment causes the loss of shutdown heat removal capability, including that a single failure does not cause two sodium dump valves in the same dump path to open.
CS 281.8 Provide the design criteria and bases that demonstrate wastage allowance (5.5) of the CRBR steam generator tubes, caused by. sodium-water reaction products, is acceptable.
The analysis should include Na-water reaction temperature and other major variables in the small water leak situation.
CS 281.9 Describe the sample and instrument readings, and the frequency of measure-(5.5, ment that will be performed to monitor the feedwa.er purity and need for 10.3) condensate cleanup system demineralizer resin and filter replacement.
State the chemical limits and precautions to be taken to protect the steam generator tubes against excessive corrosion and deposition.
- Also, provide the basis of establishing the chemistry limits.
CS 281.10 Describe the chemistry and radiochemical limits, monitoring frequency, (9.1) and criteria for cold trap replacement to ensure the soidum purity in the spent fuel storage pool.
Provide the basis for establishing these limits.
(
CS 281.11 Provide an analysis and any experimental results to demonstrate that (9.8) the plugging meter, on-line impurity monitoring device, can provide quantitative results on sodium chemistry.
Include correlation of these i
results with those obtained by the vanadium wire equilibration device j
(VWED) technique.
l CS 281.12 The Impurity Monitoring and Analysis System consists of primary heat (9.8) transport system (PHTS), ex-vessel storage tank (EVST), and intermediate heat transport system (IHTS) sodium characterization, fuel handling cell (FHC) and IHTS Cover Gas Sampling Systems.
Provide the chemical and radiochemical limits for the sodium and the cover qas analyses.
In addition, describe.the method, sampling procedures, and frequency of sampling.
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_3-CS 281.13 The NRC position and clarifications on post accident sampling (TMI Action capability of light water reactors is presented in Item II.B.3 Plan) of NUREG-0737.
Provide the design bases and criteria for a system that will provide post accident sampling and analysis capability for the CRBR which will be equivalent to the functional requirements for light water reactor plants.
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