ML18018B289
| ML18018B289 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/01/1978 |
| From: | Dise D Niagara Mohawk Power Corp |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18018B289 (50) | |
Text
M V f~>AGAN 0 @AHA NIAGARA MOHAWK POWER CORPORATION/300 ERIE SOULEVARD WEST. SYRACUSE, N.Y. 13202/TELEPHONE (3>>) 4~< 1S1 September 1, 1978 Director of Nuclear Reactor Regulation Attn: Mr. Thomas Ippolito, Chief Operating Reactors Branch ~$ 3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
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Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
'iagara Mohawk Power Corporation plans to install a Radwaste Reduction System and associated waste handling equipment at Nine Mile Point Unit 1.
The advantage of the Radwaste Reduction System will be to decrease the amount of solid waste that is shipped to offsite burial grounds. The System is expected to achieve an overall volume reduction factor of about 10. This, will result in fewer shipments of radwaste, will extend the existing space at offsite burial grounds and result in handling fewer radwaste containers. ~
Radwaste Reduction System information contained 'he herein as Attachment A is submitted in accordance with the requirements of 10CFR20.305. Additionally, Attachment A contains descr'ption of the associated waste handling equipment for your information.
The associated waste handling equipment will be capable of solidifying waste without operation of the Radwaste Reduction System. Design of the associated handling system will proceed independently of the Nuclear Regulatory of the Radwaste Reduction System.
Commission review An evaluation was made relative to 10CFR50.59(a) and it was concluded that the Radwaste Reduction System and associated waste handling equipmcnt do not involve an unreviewed safety question since:
(1) The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety pxeviously evaluated in the saxety analysis report will not increase and (2) The possibility for an acc dent or malfunction of a different type than any evaluated pre-
.viously in the safety analysis report will not be created; and (3) The margin of safety as defined in the basis for any technical specification will not be reduced.
These conclusions are based on the fact that none of the equipment to be contained within the radwaste building is important'o safety. Analyses have been performed assuming release of the maxianm> amount of incinerated, but non-solidified. radwaste on-hand. The results show that only the building structure is important to safety. This structure will be equal to or better than the existing radwaste building in terms of probability or consequences of failure. The building will be a. seismic Class I Structuxe.
No new accidents will be introduced other than different types of postulated handling accidents within the building structure. Releases from such accidents have been. demonstrated.
to be insignificant when compared to failure of the building structure analyzed herein.
These modifications do not involve any changes to the Technical Specifications. No Technical Specifications are affected by these modifications.
Haste processed by the Radwaste Reduction System will be no different from those previously described in the Final Safety Analysis Report. These wastes include:
- 1) Filter sludges
- 2) Deep bed and powdered demineralizex resins
- 3) Concentrated waste
- 4) Filters, paper, wood and other combustible matexials which may have been radioactively contaminated.
The Radwaste Reduction System will be housed in a building adjacent to the existing waste building on the east side of the plant. This building will also contain the solidification and handling equipment necessary to process the product for final offsite shipment. Building dimensions will be toabout 60 feet by 270 feet. The building will be designed the Class I seismic requirements described in the Final Safety Analysis Report.
Any spillage of liquid waste will be controlled by the floor drains in the building. There will be no increases in liquid waste effluents to the environment due totheoperation of the System. The. equipment will be designed to requirements outlined in Nuclear Regulatory Commission Branch Technical Position 11-1. (Revision 1).
The final product (ash) from the Radwaste Reducation System will be processed. through the solidification system into 55-gallon containers. in the event tnat the Radwaste Reduction System is not operating, for any reason, the waste will go directly to solidification. The solidification system will be remotely operated.
or It will be capable of Radwaste Reduction processing any of the raw waste the System ash described above into a. free-standing solid with no free water.
Under the present schedule, groundbreaking for the new building is to take place in February, 1979. The system is expected to be operational by October, 1980.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION r ~ 1 Donald P. Disc President-Engineering 'ice LMM/szd
Attachment A Back round The Radwaste Reduction System for radwaste volume reduction has been des-cribed in detail in the Licensing Topical Report. The installation at Nine Mile Point Unit 1 will not vary significantly from the System described in this Licensing Topical Report.
As was stated in the Licensing Topical Report, the basic processes of liquid calcination and com~ustible waste incineration which are used in the Radwaste Reduction System has been used in industrial plants for decades. Fluidized bed calcination of radioactive wastes was developed during the period 1952-1959 at the Idaho National Engineering Laboratory.
Use of calcination for liquid radwaste reduction was first demonstrated in an engineering scale facility, the Waste Calcining Facility, at the Idaho Chemical Processing Plant in 1963. The successful operation of the Waste Calcining Facility has demonstrated that liquid wastes can be routinely calcined into a granular free-flowing powder which can sub-sequently be handled in a simplified manner. Since 1963, the Waste Calcining Facility has handled over 2.5 million gal3.ons of radioactive aqueous wastes which have been calcined to approximately 42,500 cubic feet of solids.
Xncineration of combustible radioactive wastes has been in use as a disposal technique since 1948 when a pilot plant incinerator and offgas cleanup system were built at Mound Laboratory. Early systems were adaptations of standard refuse incinerators and did show that con-siderable volume reduction in waste handling was possible.
The Radwaste Reduction System is based on advanced fluidized bed technology using an inert bed medium to incinerate and calcine with a single-chamber process vessel. The purpose is to reduce the volume of the radwaste shipped offsite. Efficient volume reduction process depends upon.
complete combustion and effective separation of gases and solids in the effluent gas stream. This separation takes place in the offgas cleanup
. system. The high heat capacity of the fluidized bed gives the high temperature stability and results in very efficient combustion. The
, air, which maintains the bed in its fluid state, provides an ample supply of oxygen for combustion. Some wastes such as sludges and slurries do not have sufficient caloric content to maintain the bed desired temperature. In these cases, additional"heat is provided by at'the the combustion of supplemental fuel. The thermal inertia of the bed ensures that the system is relatively insensitive to moderate variations and caloric content of the feed. In the calcination mode, heat is used to drive off water as a vapor, leaving behind an incombustible residue.
This incombustible residue is ground off the bed particles by the agitation of the bed and exits from the process vessel to a dry cyclone. The calcination process is endothermic, and heat is supplied by the combustion of supplemental fuel. The use of special inert bed material means that the bed does not have to be changed when switching from incineration to calcination.
Topical Report, Radwaste Volume Reduction System, EI/NNI-77-7-P, Newport News Industrial Corporation and Energy Incorporated, June
. 1077.
S stem Descri tion The system consists of the process vessel, a dry cyclone, a product hopper, a wet scrubbing system and filtration system. Solids (ash) are removed as the gas exits from the process vessel cyclone. A product hopper collects the solids from the cyclone. Figure 1 shows the major components in a block flow diagram.
Process off-gas leaving the incinerator-calcinator vessel is cleaned in a mechanical dry cyclone, a wet scrubbing system and filtration system.
The wet scrubbing system is comprised of a spray quench tank, a high energy venturi scrubber followed by a wet cyclone, a condenser, and mist eliminator. Gaseous fission products (iodines) are removed by the scrub liquid and by an adsorber in the filtration system. Particulate material is removed by the dry cyclone, wet scrub system, and high efficiency particulate absolute filters. Cleaned offgas is vented to the atmosphere (via the plant stack) while the product, a dry granular residue from the dry cyclone; is removed for solidification, storage and shipment. Scrub liquid will be processed through the liquid waste system.
The system is designed to operate at a negative pressure with respect to its surroundings, thereby providing further assurance that no leakage of radioactive material will occur. Continuous air monitors are intended to monitor the room air.
The high efficiency treatment of the offgas cleanup system minimizes the release of gaseous effluents to the atmosphere. Xn case a portion of the, offgas cleanup system should fail to clean adequately, the Radwaste Reduction System has the capability of recirculating the offgas through the cleanup system instead of releasing it to the atmosphere. This action is initiated by the radiation monitor in the exhaust stream.
There will be no liquid releases from the System directly to the environ-ment. Scrub liquid goes to an internal hold-up tank berore returning to the liquid radwaste system.
Appropriate instrumentation will be provided to detect. conditions that may result in excessive radiation levels within the System. Controls designed to sense and activate an alarm upon the occurrence of a wide variety of off-normal operating conditions will be included. A part of the controls will be an annunciator panel, which will provide identification of the causes of an alarm. Corrective action will be taken either automatically or manually, depending on the potential seriousness of the occurrence. Offgas from the system is routed to the main stack. The stack monitoring system vill monitor these releases. Zn addition, a separate system radioactivity monitor will be located in the offgas exhaust line to the plant stack. The incremental dose rates, as shown in Table 1 for normal operation, are well below'the limits set in Appendix I to 10CFR50. The radioactive effluents produced by the System during normal operations 'vill be so small that their addition to other effluents currently discharged from Nine Mile Point will have no significant environ ental impact.
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, The solid granula esidue, or pxoduct, of the S m will be packaged and transported to a licensed disposal site. In accordance with Regulatorv Guide 1.21, provisions will be made to monitor and to limit the radiation from each package of solid waste. This will permit the opexator to control radiation exposure to personnel and to meet the regulatory requirements of 10CFR71.
Accident Anal sis The System as installed at Nine Nile Point Unit 1, will be in compliance with Federal Regulations concerning protection of personnel against radiation and other technical and legal licensing requirements.
The system design results in very low radiation levels. The individual cuM.cles formed by the concrete shield walls, and the operation of the System at less than at<osphezic pressure, will assure that the operational dose tate is below the levels required by 10CFR20 and are consistent with the original plant design czitezia. The emissions from ooeration of the system result in concentrations and dose rates at the site boundary, which aze well below the limiting values of 10CFR20 for unrestricted areas.
In this report two types of releases to the atmosphere are considered:
normal releases from regular operations and abnormal releases due to a
-transient event or an accident. Because of the high efficiency of the offgas cleanup system; normal releases are inconsequential. The normal release rates from the system have been computed, and axe shown in Table 1, using the maximum activities and composition shown on Table 2 and the decontamination factors from Table 4-2 of the Licensing Topical Report.
The dose factors are from Regulatory Guide 1.109; a breathing rate of 20 cubic meters/day has been used. The annual dose contributions are all less than 0.001 millizem.
Exposures from transient events and accidents have been discussed in Section 4.3 of the Licensing Topical Report. No additional coverage of transients will be presented here. None of the transient events have consequences which are more severe than the maximum credible accident.
As in the Licensing Topical Report, the maximum credible accident for the Nine Mile Point Unit 1 Radwaste Reduction System is the gross failure of the product container.
The doses presented for this accident are presented in Table 3. These doses are conservative since it was assumed that only 90 percent of the activity was zetained by the building and ventilation system. The building hous ng of the System is a seismic I structure and the building ventilation dischaxges to the plant stack. In addition, the system will also be located in a cubicle within the radwaste building. If the product container were to catastrophically fail, much of the material would be retained inside the cubicle. The amount escaping the cubicle would be drawn into the ventilation system. The ventilation system will contain a high efficiency particulate absolute filter having a removal efficiency of 99.97 percent. Therefore, of the amount escaping the cubicle, approximate'y 0.03 percent would escape the filter and be discharged to the plant stack.
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The capacity of the product container is equivalent to three 55-gallon drums (0.624 cubic meters), and it is conservatively calculated that 1710 curies is the maximum credible activity that can be expected to accumulate in the product cont'ainer. This is based on the maximum specific activity for filter sludge shipped reported for any si:c months (68.5 curies/cubic meter). This occurred in the second half of 1975.
This has been multiplied by a factor of 2 to allow for variations with'n this six-month period. Thus, it is assumed that enough feed is available at 137 curies/cuoic meter factor to fill up the product container.
envisioned for waste The ma~urn other than dry, combustible volume reduction solids is 20:1. The 1710 curies is over 2/3 of the annual expected activity for resin/sludge. It is extremely unlikely that such a large portion of the activity in a year's waste would accumulate in such a small volume. The composition of the 1710 curies is taken to be that given in the resin/sludge column of Table 2.
Despite the above, it is conservatively assumed that 10 percent of the granular ash (171 curies) in the product container escapes from the building containing the System and remains airborne long enough to reach the site boundary. The doses due to this release are shown in Table 3. The site boundary closest to Nine Mile Point Unit 1 is 1,500 meters in the southwest sector. The dilut"'on factor, X/Q, from Regulatory Guide 1.3 for an elevated (100 meter) release and fumigation conditions are assumed. The material was assumed to be released in the first four (4) hours. These assumptions are from the latest Regulatory in the Guides and are therefore different from the assumptions used Nine Mile Point Unit 1 Final Safety Analysis Report. The dose factors have been taken from Regulatory Guide 1.109, and the breathing rate vas 20 cubic meters/day. The maximum dose was found to be 534 mrem to the'lung.
Associated Paste Handlin E ui ment A solidification system will be added to solidify wastes processed by the System and the existing radwaste facil'ty. It will consist of dry cement storage and handling equipment, 55-gallon barrel filling, mixing equipment, and settling/decant tanks. This equipment will be ef the same basic design as that at Dresden 2 and 3.
An overhead crane will be installed for transporting barrels from the mixing station to storage and for loading them onto trucks for shipment and offsite burial."
Existing wastes such as filter sludges, resins and evaporator bottoms vill either be processed by the system as described earlier or will be if solidified directly, will be solidified directly. These wastes, settled and decanted to the desired concentration. They will then be mixed with a premeasured amount of cement in a 55-gallon barrel. A test will be conducted after solidif'cation to ensure that no free water is present.
The 55-gallon barrels will then be transported by the crane to the storage area(s). A barrel grab mechanism equipped with TV cameras wiM be used to pick up and locate the barrels in the storage areas. However, the storage areas will be inaccessible to personnel and the entire operation will b'e remotely operated. Adequate shielding will ensure that radiation levels in normal plant access areas are consistent with the existing plant design. In addition, the roof over the barrel storage areas will be two (2) feet thick to ensure acceptable radiation levels outside the building.
The crane described above will have access from the barrel storage axea{s) to the truck loading bay. Barrels handled by the crane will be located by position in the storage area, picked up and placed in a cask on a truck. These operations will be remotely controlled.
Controls fox the system as well as alarms and monitoring equipment important for the operation of the system will be located in a control room in the new building. Each barrel in storage will have a number assigned corresponding to its location. Other information on each barrel will also be recorded on a board in the contxol room such as radiation level, weight and date placed in storage.
ADDITIONAL EMISSION RATES~ BOUNDARY CONGE'iiATIONS~ AND DOSE RATES DUE TO OPERATION OF THE RADMASTE REDUCTION SYSTEM Maximum Maximum ,.Decontamination Release .Concentration Boundary Dose Rates Feed Rate Factor Rate .Lait Concentration Thyroid Lung tal Ci/ ear Ci/ ear Ci/m3 Ci/m3 mrem/ r NA-24 15 4 x 10 4 3.8 x 10 5000 6.7 K 10 8.3 x 10 8.3 x 10 8.3 Mn-54 125 4 x 10 4 3.1 x 10 1000 5,5 x 10 0.0 7.0 x 10 3o2 }
4! Co-60 915 4 x 10 2.3 x 10 300 4.0 x 10 0.0 2,2x 10 5.5 y Sr-89 10 4x10 4 2.5 x 10 300 4.4 x 10 0.0 5.6 x 10
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7 3.5 I-131 50 1x10 4 5.0 x 10 100 8.8 x 10 9.6 x 10 6.0 1.7 >
Cs-134 1225 4x10 4 3.06 x 10 400 5.4 x 10 0.0 4.8 x 10 3.6 >
4 Cs-137 2160 4 x 10 5.4 x 10 500 9.5 x 10 0.0 6.6x 10 ~ 7 q I
TOTAL 4500 1.16 x 10 2.1 x 10 9.5 x 10 2.4 x 10 7.4:
TABLE 2
'PROJECTED ACTIVITIES IN THE LI(UID AND RESIN)SLUDGE FEED TO THE RADMASTE REDUCTION SYSTEM FOR NINE MILE POINT UNIT ONE Liquid Resin/Sludge Expected Maximum Expected Maximum
~ercent ~Ci/ r ~Cj/~i ~ercent ~Ci/ r ~C$ /~r Na-.24 1.5 9 15 Mn-54 2 12 20 3 75 105 Co-60 11 66 110 23 575 . 805 51'-89 1 6 10 I"131 1.5 9 15 25 35 Cs-134 35 210 350 25 '25 875 Cs-137 48 288 480 48 '200 1680 Total 600 1000 2500 3500
'TABLE 3 DOSES AT THE SITE BOUNDARY DUE TO THE MAXIMUM CREDIBLE ACCIDENT FOR THE NINE MILE POINT UNIT il RAD'rlASTE REDUCTION SYSTEM 10K of the Ash Released Organ Dose (mrem)
Nuclide Bone Liver Thyroid Kidney Lung Total Body Hn- 54 0.0 0.4 0.0 O.l 15.3 0.1 Co- 60 0.0 1.0 0.0 . 0.0 496.5 1.2 I-131 O.l ..0.1 43.2 0.2 0.0 0.1 Cs-134 33. 5 76.5 0.0 26.1 8.7 65. 7 Cs-137 82.8 107.7 0.0 38.7 13.2 74.4 TOTAL ~ 116.4 185. 7 43.2 65.1 533.7'41.5
Pigura gl Radwaste Reduction S stem Block Plow Dia ram Cases and Credo Rater Vapor ench Scrubber Pet Hist Tank Condenser Cyclone Eliminato.
Scrub Liquid Liquids Dry Scrub Cyclone Liquid Tank High Process Ef ficieacy Vessel Solids azticuleto Piltcz Product To Liquid Container Paste Processing Iodine Adsorber To Solidification High Efficiency Piltex'o Plant Stack
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Attn: Secretary of the'ommission
Dear Sir,
Please provide me with any technical information you have describing the health ahd safety consequences of operating the low level waste incinerator planned for installation at Nine Mile Point Unit No. 1 in New York.
Have you, or do you intend to prepare an environmental assessment of this technology?
why not? If so, please send me a copy when it If not, becomes available.
Given the public. concern over the installation of this incinerator, an environmental impact statement, or at least an environmental assessment would appear appropriate.
Sincerely, Thomas B. Cochran ll 5 5
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. ~ocket ORB III3 UNITED STATES NUCLEAR REGULATORY COMMISSION SSheppard WASHINGTON, O,C. 20555 September 22, 'l978 Docket Noa a 50-220 See attached list of addressees e
Subject:
Nine Nile Point Unit No. 1 Niagara Nohawk Power Corporation The following documents concerning our review of the subject facility are transmitted for your information:,
Notice of Receipt of Application.
Draft/Final Environmental Statement, dated 0 Safety Evaluation, oi Supplement No.. dated of Hearing on Application for Construction Permit.
'otice Notice of Consideration of Issuance of Facility. Operating License.
Application and Safety Analysis, Report, Vol.
Amendment No. to Application/SAR, dated Construction Permit No. CPPR- ~ dated Facility Operating License No. DPR- , NPF-, dated Amendment No. to DPPR- or DRR-, dated X p~<<Ltr dtd 8 31 78 from Effluent Release Sem -
NNPC nnua transmitting Radioactive eport or e peno 1 78 throu h 6 30 78 w att meteorolo ica1 data.
Office of Nuclear Reactor Regulation ORB g3 DOR
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'Washington, D. C. 20234 Head uarters Dr. Nei ll Thomasson (AW-459)
Chief, Energy Systems Analysis Branch Office of Radiation Programs Environmental Protection Agency 401 N Street S.W.
Washington, D.C. 20460
~AR U. S. Environmental Protection Agency Region II Office ATTN: E'IS COORDINATOR 26 Federal Plaza New York, N. Y. 10007
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, Docket UNITED STATES ORB ¹3 NUCLEAR REGULATORY COMMISSION SSheppard WASHINGTON, O.C. 20555 Ouly 28, 1978 Docket No. 50-220 See attached list of addressees Nine Nile Point Unit No. 1 N agara No aw Power CosIpany The following documents concerning our review of the subject facility are transmitted for your information:
Notice of Receipt of Application.
Draft/Final Environmental Statement, dated Safetp Evaluation, or Supplement No., dated Notice of Hearing on Application for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
Application and Safety Analysis Report, VoL Amendment No. to Application/SAR, dated Construction Permit No. CPPR- dated NPF- dated Facility Operating License No. DPR- , ,
Amendment No. to CPPR- or DRR-, dated Other:
transmitting 1977 Nine Nile-Point Aquatic Ecology Office of Nuclear Reactor Regulation ORB ¹3
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. U. S. Department of Commerce Washington, 0. C. 20235 Dr. James T.
Bureau Tanner'ational of Standards Reactor Bui1ding 235 llashington, D. C. 20234
~Head uarters Dr. Neill Thomasson (AW-459)
Chief, Energy Systems Analysis Branch Office of Radiation Programs Environmental Protection Agency 401 l1 Street S.W.
Washington, D.C. 20460 EPA Re ion U, S. Environmental Protection Agency Region II Office ATTN: E IS COORDINATOR 26 Federal Plaza New York, N. Y. 10007 Lab.
Dr. Philip F. Gustafson Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439
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ORB III3 UNITED STATES SSheppard NUCLEAR REGULATORY COMMISSION
'ASHINGTONO,C. 20555 flay 11, 1978 Docket No. 50-220 See attached list of addressees subject: Nine Nile Point Unit No. 1 N agara Nohaw Power Corporation The following documents concerning our review of the subject facility, are transmitted for your information:
Notice of Receipt of Application.
Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No., dated Notice of Hearing on Application for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
Application and Safety Analysis Report, Vol.
Amendment No. to Application/SAR, dated Construction Permit, No. CPPR- . dated Facility Operating License No. DPR-Amendment No.
Q oth<<Ltr dtd 5 3 to CPPR- 'r DRR-,
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, dafed 78 from Nia ara tIohawk Pwr Cor . transmitting an addendum to the Annual Environ. Operating Rpt. for the eriod 2 Office of Nuclear Reactor Regulation ORB 83
Enclosures:
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OFFICE 0 ORB 83 SURNAME y SSheypard:
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.~ Division of Ecolooical Services Bureau of Sport Fisheries and Wildlife U. S. Department of the Interior Washington, D. C. 20240 Director National Oceanographic Data Center Environmental Data Service National Oceanic & Atmospheric Administration U. S. Department of Commerce Washington, D. C. 20235 Dr. James T. Tanner National Bureau of Standards Reactor Building 235 Washington, D. C. 20234 Head uarters Dr. Neill Thomasson (AW-459)
Chief, Energy Systems Analysis Branch Office of Radiation Programs Environmental Protection Agency 401 li Street S.W.
Washington, D.C. .20460 EPA Re ion U. S. Environmental Protection Agency Region II Office ATTN: E IS COORDINATOR 26 Federal Pl aza New York, N. Y. 10007 LAB Dr . Philip F. Gustafson Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439
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MAR 31 1977 Mr. Paul A. Giardina, Chief Regional Office of Radiation Programs U.S. Environmental Protection Agency Region II 26 Federal Plaza New York, New York 10007
Dear Mr. Giardina:
This is in response to your letter to Dr. C. 0. Gallina of this office, dated March 23, 1977, relative to effluent and solid waste reporting by the James A. FitzPatrick and Nine Mile Point Unit 1 plants.
The licensee, Niagara Mohawk Power Corporation, submits the effluent and waste disposal reports semi-annually as separate documents and makes the same distribution as for the Annual Report and Environ-mental Operating Report, which you indicated had been received by your office.
The Effluent and Waste Disposal reports for the period of interest have been received by this office and are dated as follows:
Plant Period Re ort Date JAF Jan-Jun 1976 August 31, 1976 JAF July-Dec 1976 February 23, 1977 NMP-1 Jan-Jun 1976 August 30, 1976 NMP" 1 July-Dec 1976 February 23, 1977 If this information does not prove helpful in locating these reports from your usual source, please contact this office.
E1don J. Brunner, Chief Reactor Operations and Nuclear Support Branch
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26 FEDERAL PLAZA NEW YORK. NEW YORK 10007 March 23, 1977 Mr. Charles Gallina Region I Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19006
Dear Mr. G na:
The Regional Office of Radiation Programs has received the Annual Environmental Operating Reports for the Nine Mile Point Nuclear Station Unit N and for the James A. Fitzpatrick Nuclear Power Plant covering the period January 1, 1976 through December 31, 1976, and the Annual Report of Operation for the Nine Mile Point Station for the same period.
According to Paragraph (a)(2) of Section 50.36a, 10 CFR Part 50, the Nuclear Regulatory Commission requires reports from utilities which specify the quantity of each of the principal radionuclides released in liquid and gaseous effluents during the operation of a nuclear power plant. This effluent release and solid waste data, as well as dose readings were not contained in these reports we received. We would appreciate any information you can provide concerning these apparent omissions.
Sincerely ours, Paul A. Giardina Chief Regional Office of Radiation Programs
Distribution
~Docket UNITED STATES ORB ¹3 NUCLEAR REGULATORY COMMISSION CParrish WASHINGTON, O.C. 20555 March 2, 1977 Docket No. 50-220 SEE ATTACHED LIST OF ADDRESSEES Subjecr,: Nine Mile Point Nuclear Station Unit No. 1'located in Oswego County, New York The following documents concerning our review of the subject facility are transmitted for your information:
Notice of Receipt of Application Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.. dated Notice of Hearing on Application for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
Application and Safety Analysis Report, Vol.
Amendment No. to Application/SAR, dated Construction Permit No. CPPR- , dated Facility Operating License No. DPR- , NPF- , dated AmendmentNo. to CPFR- or DRR- . dated Q Oth<<; Ltrs. from Nia ara Mohawk Power Cor 1 dtd 2 24 77 trans-mitting Annual Report of Operations for the period 1/1/76 thru 123 6 nd 2 dd2 Yizggmgg tal Operating Report for the period 1/1/76 thru 12/31/76.
Office of Nuclear Reactor Regulation Operating Reactors Branch ¹3
Enclosures:
Division of Operating Reactors As stated CC:
OFFICE IP ORB ¹3 SUIINAME Io CPavris mj OATS 3/2/77 NRC-21 I6 761
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.0 Chief .
Division of Ecological Services Bureau of. Sport Fisheries and Wildlife '-
U. S. Department of the Interior Washington,. D. C. 20240
'A Director
. National Oceanographic Data Center Environmental Data Service National Oceanic 8 Atmospheric Adminis tration U'. S'. Department of Commerce
'Ptashington, D. C. 20235 A
Director Division of Chemical Technology Fo'od and Drug Administration U:'S. Department of Health
'. 'ducation an'd Welfare
'Washington, D. C. 20240
~dd Dr. Neill Thomasson (All-459)
Chief, Energy Systems Analysis Branch Office of Radiation Programs Protection Agency'nvironmental 401. M Street S'.W.
Was'hington, D.C. 20460
~EPA R U. S..Environmental Protection Agency Region II Office ATTN: EIS COORDINATOR 26 Federal Plaza
, New York, N. Y. 10007 LAB Dr. Philip F. Gustafson Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439