ML20053A254
| ML20053A254 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 05/18/1982 |
| From: | Longenecker J ENERGY, DEPT. OF |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| HQ:S:82:025, HQ:S:82:25, NUDOCS 8205250143 | |
| Download: ML20053A254 (5) | |
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Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:82:025 MAY 181992 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Check:
RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION - EFFLUENT TREATMENT
Reference:
Letter, P. S. Check to J. R. Longenecker, "CRBRP Request for Additional Information," dated March 4,1982 This letter fonnally responds to your request for additional information contained in the reference letter.
Enclosed are responses to Questions CS 460.1, CS 460.2, and CS 460.3 that will also be incorporated into the PSAR Amendment 69; scheduled for submittal later in May.
Sincerely, k
John R. Longenecker, Manage
\\
Licensing & Environmental Coordination Office of Nuclear Energy Enclosures cc: Service List 9
Standard Distribution Licensing Distribution jj 8205250143 820518 PDR ADOCK 05000537 A
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Question CS460.1
%e model that was used to calculate the source terms for normal operation assumes 1% failed fuel. Please provide the basis for such a high percentage of failed fuel. For light water reactors, the staff assumes that the reactor coolant activity concentrations are roughly equivalent to a failed fuel fraction of 0.12% for purposes of calculation of radiological effluent source terms.
Response
It is expected that during normal operation, the best estimate of the failed fuel fraction will be 0.1% or less. %e use of the 1% failed fuel assumption was to:
Provide an a'bitrarily conservative basis for the design of biological a.
r shielding in normally occupied areas of the plant. For areas in which infrequent maintenance activities occur, the shielding is based on a range of failed fuel of 0.1%-1.0% depending upon ALARA considerations, b.
Provide plant capability for operation with larger than expected occurrences of failed fuel.
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QCS460.1-1 Amend. 68 May 1982
Ouestion CS460.2 Page 11.5-3 of the PSAR discusses the options available for processing, storing and disposing of retallic sodium and sodium bearing solids.
It states that a firm decision has not been made regarding method and assigned responsibility for ultinate disposal.
At the operating license (OL) st$ge, the applicant will be required to demonstrate that methods for processing, packaging, transporting and ultirate disposal of the waste have been developed that will satisfy the applicable criteria of 10 GR Part 61,10 GR Part 71, DUT, disposal site license conditions, Regulatory Guide 1.143 and Standard Review Plan Section 11.4.
%e applicant should commit to develcping waste processing, packaging, transportation and disposal methods in accordance with these applicable criteria.
Resoonse:
ne ultimate disposal of netallic sodium and sodium bearing solids requires the conversion of the metallic sodium to a disposable form and the cleaning of sodium bearing solids to a disposable level.
We DOE will develope methods for processing, packaging, transporting, and ultinately disposing of sodium waste to meet the intent of the appropriate criteria of 10TR Part 61, IOGR Part 71, DOT, disposal site licensed conditions, Regulatory Guide 1.143 and Standard Review Plan Section 11.4.
nese will be denenstrated in tine for the operating license (OL).
QCS460.2-1 Amend. 68 May 1982
0 OUESTION CS 460.3 Show that you will be in cmpliance with iters II.F.1, Attachnent 1, Noble Gas Effluent Monitor, II.F., Attachnent 2, Sampling and Analysis of Plant Effluents, and III.D.I.1, Integrity of Systers Outside Containment Likely to Contain Radioactive Material (as applicable to the CRBRP) of NURDG-0737,
" Clarification of 'IMI Action Plan Requirements".
RESPONSE
NUPBG 0737 ITEM II.F.1. Attachment 1. " Noble Gas Effluent Monitor" In regard to II.F.1, Attachnent 1, Noble Gas Effluent Monitor, of NURDG-0737, CRBRF will continuously monitor the following potential accident release paths, for gaseous radioactivity:
PA'lli UPPER. RANGE 1.
Radwaste Building Ventilation Exhaust 10-6-102 micro Ci/cc 2.
Reactor Service Building Exhaust 10-6-103 micro Ci/cc 3.
Steam Generator Building (Intermediate 10-6-103 micro Ci/cc Bay) Exhaust 4.
Annulus Cooling Exhaust 10-6-104 micro Ci/cc 5.
Annulus and Containment Purge ('IMBm) 10-6-105 micro Ci/cc Effluent Each of the above monitors will be environmentally qualified, in accordance with Reference 13 of Section 1.6.
Monitors will be powered from highly reliable power sources. All monitors will enploy side-stream monitoring with a beta detector and will obtain a representative sample in accordance with ANSI 13.1.
The radiation level will be continuously provided for display and alarm signals which are permanently recorded by the redundant Radiation Monitoring Consoles located in the Control Room and Health Physics Area.
Initial calibration will be performed by monitor manufacturer subsequent in-plant calibrations will be performed by secondary sources which are traceable to the National Bureau of Standards.
OCS460.3-1 Amend. 68 May 1982
tM WG 0737 Item II.P.l. Attachment _2. "Samolina and Analysis of Plant Effluents Attactnent 2, Sampling and Analysis of Plant Effluents, of NURED-0737, requires sampling and analyzing plant effluents for radioiodine and particulates. CRBRP will continuously monitor the paths listed in Attachment will be 10giodine and particulate activity. g upper range for radiciodine 1 for radi micro Ci/cc and for particulates 10 micro Ci/cc. Absorption for iodine will be 95% and particulate filter efficiency will be 99% for 0.3 micron and larger. Provisicns shall be provided to ensure that the absorber is not degraded by entrained water in the effluent stream. Monitors will meet the same requirements described above for Noble Gas Effluent Monitors.
In addition to the monitoring described above, removal of samples for laboratory analysis may also be performed. Tenporary shielding, as necessary, will be provided and procedures developed to ensure personnel safety when collecting samples.
NUPIG 0737 Item III.D.l.l. "Intearity_of Systems Outside Containment Likely to Contain Radioactive Material" Appendix H of the PSAR provides CRBRP's evaluation of and resolution to the requirements delineated in NUREG-0718. NUREG-0718 defines requirements of NUREE-0737 applicable to Applications for Construction Permits.
Included is discussion of Item III.D.l.l.
%is requirement has been determined to be applicable to CRBRP in principle, recognizing that the detailed requirements are specific to IE's and do not reflect the unique technology of INBRs.
By features of design and operational controls, CRBRP will confine primary coolant fluids to within containment and will not process them outside of containment. Any leakage of systems containing these primary coolant fluids would be to the containment only.
Wus, CRBRP will be in compliance with the principle of concern of Item III.D.l.l.
OCS460.3-2 Amend. 68 May 1982
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