ML20238E993
| ML20238E993 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/09/1987 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ULNRC-1598, NUDOCS 8709150327 | |
| Download: ML20238E993 (5) | |
Text
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s 1901 Gratiot Street St. Louis Donald F. Schndl.
1 Vice Raiosnt September 9, 1987 l
,t-U.S.-Nuclear Regulatory Commission ATTN:
Document Control Desk Wanhington, D.C. 20555 ULNRC-1598-Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT RESPONSE TO ADDITIONAL.INFORMATION REQUEST REGARDING CYCLE 3 RELOAD-APPLICATION
Reference:
1.
ULNRC-1740 dated March 31, 1987-2.
ULNRC-1590 dated August 31, 1987 Reference 1 transmitted the license application for Callaway Cycle 3.
Attached to reference 12 are responses to the Staff's L
(C. R. Nichols) informal request for additional information.
Attached to this letter are amended responses to questions 1 and
-2 as transmitted by reference 2.
If^there are any~further questions, please contact us.
Very truly
- ours,
/
Donald F. Schnell NGS/plh l
l Attachment.
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I B709150327 B70909 PDR ADOCK 050004B3 PDR i
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I Mailing Address: P,0. Box 149, St. Louis, MO 63166 gU
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STATE OF MISSOURI- )
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Donald F. Schnell,.of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Unior. Electric Company; that he has rePd the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his-knowledge, information and belief.
By Donaf ~if. ochnell Vice President Nuclear SUBSCRIBED and sworn to.before me this 95 day of 1987
/bWS lhy BARUARA EPFAfk NOTARY PUBUC, STATE OF MISSOURI MY COMMISSION EXPIRES APRIL 22, 1989 ST. LOUIS COUNTY.
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cc: ' Gerald Charnoff, Esq.
Shaw, Pittman, Potts:& Trowbridge 2300 N. Street, N.W.
Washington, D.C.
20037 Dr. J. O. Cermak-CFA, Inc.
4 Professional Drive (Suite 110)
'Gaithersburg, MD 20879 W. L. Forney Chief, Reactor Project Branch 1-U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S.. Nuclear Regulatory. Commission RR#1-Steedman, Missouri '65077 Tom Alexion (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014 Ron Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jef f er son City, MO 653.02 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 l
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i Attachmtnt ULNRC-159 8 RESPONS'E TO-ADDITIONAL INFORMATION REQUEST REGARDING CYCLE 3 RELOAD APPLICATION i
1.
SRP 11.1 provides, among the specific criteria necessary to meet the relevant requirements of 10 CFR 20 & 50, that the source terms result in meeting design objectives for doses in an unrestricted area as set forth in Appendix I of 10 CFR 50.
Provide an estimate of the effect of extended burnup on
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concentrations of significant nuclides in.the Reactor Coolant System and, based on this, the effect on effluents from the plant and doses to persons in unrestricted areas.
Response
Reactor Coolant System concentrations were previously calculated using NRC's GALE code per the requirements of
'SRP 11.1.
The'use of source terms in the GALE code is not intended to explicitly model releases for any particular plant but to provide an estimate based on operating histories of' current plants.
A specific plant may have releases higher or lower than the standard values depending on plant operation.
Operational flexibility was intended by the regulations.
If plant operating experience were to show an unacceptable increase in the effluent releases, corrective action would be taken to reduce the releases and to assure that releases'were as low as reasonably achievable and below the guidelines given in 10 CFR 50, Appendix I in accordance with Callaway Plant Technical Specifications.
1 I
Notwithstanding the above, a core inventory comparison was performed by Westinghouse for fission products with significant contributions to offsite dose.
This comparison indicates that, while most significant fission products decrease, some relatively long-lived radionuclides increase as much es 35% with increasing burnup.
This increase in inventory corresponds to an increase in reactor coolant concentration for these isotopes.
The effect on offsite dose was evaluated and showed an increase in dose due to
'I gaseous effluents of less than 30% and an increase in dose due to liquid effluents of less than 8% for all significant pathways.
Since the regulations allow for operational flexibility and the increase is still well within 10 CFR 50 Appendix I guidelines, we see no reason to revise the original analysis and conclusions previously reported.
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1 12.
In.your submittal'it is-indicated'in Attachment 3, Table 1 that the extended burnup has no significant effect.on the total' activity (Ci) of solid' waste to be disposed of.
Elsewhere.in the Attachment, it is stated that a reduced number:of shipments are required due to extended burnup.
From.this statement, it can be concluded that the
. concentrations are higher.
How does this affect Fy classification and. processing of solid waste'under.10:CFR4 61, 71,-and the requirements.of burial sites?
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Response
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.c, The statement that a reduced number of shipmentsLwere
>-, M required due to extended burnup was intended to specific' ally:
refer to shipments of irradiated spent fuel assemblies.!bloes
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Since spent fuel is. classified as a High Level. Waste it not effect classification under 10 CFR 61.
With respect to Low-Level Waste generation, the dominant contributor is'from reactor operations.
Recent Low-Level Waste data show a large variability from plant to plant, and from year to year.
These variations are much greater than what.would:be expected from increased burnup.' Radwaste quantities previously reported in licensing documents were based in part, on industry operating experience then available.
Since that time political uncertainties associated with passage of the Low Level Waste Policy Act have caused many plants, including Callaway, to significantly reduce low level waste volume.
A' reduction in the number of refueling outages resulting from increased t
fuel burnup will likely result in still further volume reductions for some waste streams such as dry activated waste.
For other waste' streams, the quantity of radioactive material accumulated in a particular waste system or l
component over the period of'its operating cycle or the process run time is proportional to the quantity of radioactive material in the reactor coolant during that period.
Based on our response to question 1, some fission product concentrations in reactor coolant will increase and come will decrease.
This,'in turn, could result in increased' concentrations of some isotopes in radwaste generated but is unlikely to increase the volume generated L
due to other factors discussed above.
l An evaluation.was performed of radwaste classification requirements contained in 10 CFR 61 using methodologies contained ~in AIF/NESP-027, " Methodologies for Classification of Low-Level Radioactive Wastes from Nuclear Power Plants".
-It was found that none of the expected waste classifications would' change as a result of the minor increases in concentration.
It is therefore expected that the quantity, classification and processing of Low-Level Waste under 10 CFR 61, 71~and the requirements of burial sites will be unrelated to increased burnup.
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