ML20044A093
| ML20044A093 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/07/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044A094 | List: |
| References | |
| NUDOCS 9006280063 | |
| Download: ML20044A093 (10) | |
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UNITED STATES n=
NUCLEAR REGULATORY COMMISSION EL i
WASHINGTON, D. C. 20655
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ENVIRONMENTAL ASSESSMENT 1
BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO THE EXPANSION OF THE SPENT FUEL POOL FACILITY OPERATING LICENSE NO. NPF-57 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION DOCKET NO. 50-354
1.0 INTRODUCTION
1.1 Description of Proposed Action By letter dated October 11, 1989, Public Service Electric and Gas Company 1
(PSE&G or the licensee) requested an amendment to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (HCGS) to permit the inste11ation of-sufficient rack modules to bring the spent fuel pool storage capacity up to the original design value of 4006 fuel assemblies.
The requested increase in allowed spent fuel storage capacity:
a.
consists of placing original racks of the original design on the spent fuel pool floor; i
b..
does not involve rod consolidation or double tiering;
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does not result in the Keff of the pool exceeding 0.95;-and d.
-will utilize no new or unaroven technology in the construction process or analytical teciniques necessary to justify the expansion.
4 1.2 Need.for Increased Storage Capacity
'l Amendment 27 to-the (HCGS)-Technical Specifications increased the capacity of a
the spent fuel storage 1ool from 1108 to the presently allowed 1290 fuel assemblies. However, tiat change did not increase the storage capacity to the
. plant design limit of:4006 assemblies, but merely provided sufficient storage cepacity to accomodate the third fuel cycle while PSE&G completed a review of its long range fuel cycle strategy. PSE&G's current long range plans involve the utilization of the same fuel rack design-as that of the original racks for all future fuel cycles. Therefore, PSE&G is requesting that TS 5.6.3 be reworded to permit the installation of the necessary rack capacity for storage of the FSAR design limit of 4006 spent fuel assemblies.
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. The proposed plan for installing the new racks fundamentally meets the objective of keeping occupational exposures to a level that is as low as reasonably achievable. The operations will occur in pool areas as remote as possible from the currently stored spent fuel.
The Nuclear Waste Policy Act of 1982 provided for limited away-from-reactor j
storepe, and stipulated that a spent fuel repository would be available by 1998. Since the Act does not require a repository before this date, it is not clear whether there will be any place to ship spent fuel in the early-to-mid-1990's. Therefore, in the interim the licensee needs to provide more storage capacity.
-1 1.3 Alternatives Commercial reprocessing of spent fuel has not developed as originally articipated, in 1975, the Nuclear Regulatory Commission directed its staff to prepare a Generic Environmental Impact Statement (GEIS) on spent fuel storage.
The Corrmission directed the-staff to analyre alternatives for the handling and i
storage of spent light water power reactor fuel with particular emphasis on
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developing long-range policy.
The GEIS was to consider alternative methods of spent fuel storage, as well as the possible restriction or termination of the peneration of spent fuel through nuclear power shutdown.
A " Final Generic Environmental Impact Statenent (FGEIS) on Handline and Storage of Spent Light Water Power Peactor Fuel" (HUREG-0575), Volumes 1-3, was issued by the NRC in August 1979. The finding of the FGEIS is that the environmental impact costs of interin storage are essentially negligible, i
regardless of where such spent fuel is stored.
A comparison of the impact costs of various alternatives reflects the adventage of continued generation of nuclear power versus its replacement by coal-fired power generation.
Continued nuclear generation of power versus its replacement by oil-fired generation prcvides an even greater economic advantage.
In the bounding case considered in the FGEIS, that of shutting down the reactor when the existing spent fuel storage capacity is filled, the cost of replacing nuclear stations before the end of their normal lifetime makes this alternative uneconomical.
The storage of spent fuel as evaluated in NUREG-0575 is considered to be an interim action, not a final solution to permanent disposal.
One spent fuel storage alternative considered in detail in the FGEIS is the expansion of the onsite fuel storage capacity by modification of the existing spent fuel pools. Applications for more than 100 spent fuel pool expansions have been received and have been approved or are under review by the NRC. The finding in each case has been that the environmental impact of such increased storage capacity is negligible. However, since there are variations in storage design and limitations caused by the spent fuel already stored in some of the pools, the FGEIS recommends that licensing reviews be done on a case-by-J case basis to resolve plant-specific concerns.
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The continuing validity and site specific applicability of the conclusions in the HUREG-0575 have also been confirmed in the Environmental Assessments for the Surry and H. B. Robinson Plants' independent spent fuel storage installations.
The. staff has evaluated other alternatives with respect to the need for proposed action as discussed in Section 1.2 of this assessment. The following alternatives were considered by the staff:
(1) Shipment of spent fuel to a permanent federal fuel storage / disposal facility; (2) Shipment of fuel to a reprocessing facility; (3) Shipment of fuel to another utility or site for storage; (4) Reduction of spent fuel generation; (5) Constructionofanewindependentspentfuelstorageinsta11atico(ISFST);
(6) No action taken.
Each of these alternatives is discussed below, t
1.
Shipment of Spent Fuel to a Permanent Federal Fuel Storace/ Disposal Facility Shipment to_a permanent federal fuel storage disposal facility is an alternative to increasing the onsite spent fuel storage capacity. The U.S.
Departnent of Energy (00E) is developing a repository urder the Nuclear Waste 1
Policy. Act of 1982 (NWPA). However, the facility is not likely to be-ready to receive spent fuel ur,til the year 2003, at the eerliest. Therefore, spent fuel acceptance and disposal by DOE is not an availetle alternative to increased onsite pool storage capacity.
f.s-aninterimmeasure,shipmenttoaMonitoredRetrievableStorage(PRS) facility is another alternative to increasing the onsite spent fuel stcrage capacity. DOE, under the NWPA, has recently submitted its MRS proposal to Congress. Because Congress has not authorized an MRS and because one is not projected to be available until 1998, this alternative does not meet the near-term storage needs of Hope Creek Generating Station.
Under-the NWPA, the federal government has the responsibility to provide not more than 1900 metric tons capacity for the interim storage of spent fuel. The impacts of storing fuel at a Federal Interim Storage (FIS) facility fall within these already assessed by the NRC in NUREG-0575.
In enacting NWPA, Congress found that the owners and operators of nuclear power stations have the primary responsibility for providing interim storage of spent nucleer fuel.
In accordance with the NWPA and 10 CFR Part 53, shipping of spent fuel to an FIS facility is considered a last resort alternative. At this time, the
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licensee cannot take advantage of FIS because existing storage capacity is not i
maximized. Therefore, the licensee has been pursuing this application for the spent fuel pool expansion at this time.
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4 2.
Shipment of Fuel to a Reprocessing Facility Reprocessing of spent fuel from Hope Creek Generating Station is not viable because presently there is no operating connercial reprocessing facility in the United States, nor is there the prospect for one in the foreseeable future.
3.
Shipment of Fuel to Another Utility or Site for Storage The shipment of spent fuel from Hope Creek Generating Station to the storage facility of another utility company could provide short-term relief for the storage capacity problem.
However, the NWPA and 10 CFR Part 53 clearly place the responsibility for the interim storage of spent nuclear fuel with each owner or operator of a nuclear power plant. Moreover, transshipment of spent fuel to and its storage at another site would entail potential environmental impacts greater than those associated with the proposed increased storage at Hope Creek Generating Station site. Therefore, this is not considered a practical or reasonable alternative.
4 Reduction of Spent Fuel Generation Improved usage of fuel in the reactor and/or operation at a reduced power level would extend the life to the fuel in the reactor.
In the case of extended burnup of fuel essemblies, the fuel cycle would be extended and fewer offloads would take place. However, the current storage capacity would still be quickly exhausted as discussed in Item 1 above. Operation at reduced power would not make effective use of-available resources and would-result in economic penalties.
5.
Construction of A New independent Spent Fuel Storage Installation Additional storage capacity could be developed by building a new, independent spent fuel storage installation (ISFST), similar either to the existing pool or a dry storage installation. The NRC staff has generically assessed the impacts of the pool alternative and found, as reported in NUREG-0575,.that "the storage of LWR spent fuels in water pools has an insignificant impact on the environment." A generic assessment for the dry storage alternative has not been made by the staff.
However, assessments for the dry cask ISFSI at the Surry Power Station, the dry modular concrete ISFSIs at the H. B. Robinson Steam Electric Plant Unit 2 and the Oconee Nuclear Station resulted in findings of no significant impact.
While these alternatives are environmentally acceptable, such a new storage facility, either at Hope Creek Generating Station or at a location offsite, would require new site-specific design and construction, including equipment for the transfer of spent fuel. NRC review, evaluation and licensing of such a facility would also be required.
It is not likely that this entire effort would be completed in time to meet the need for additional capacity as discussed above.
Furthermore, such construction would not utilize the existing expansion capability of the existing pool and thus would waste resources.
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Ne Action Taken i
If no Mtion were taken, i.e., the spent fuel pool storage capacity remains at 1290 lo:;ations, the storage capacity would become exhausted in the very near future and Hope Creek Generating Station would have to be shut down. Such termination of operations would result in no further generation of spent fuel, thereby eliminating the need for increased spent fuel storage capacity. The impacts of terminating the generation of spent fuel by ceasing the operation ofexistingnuclearpowerplants(i.e.,ceasinggenerationofelectricpower) when their spent fuel pools become filled were evaluated in HUREG-0575 and found to be undesirable. This alternative would be a waste of an available resource, Hope Creek Generating Station itself, and is not considered viable.
In sumary, the only long-term alternative that could provide an alternative solution to the licensee's spent fuel storage capacity problem is the construction of a new independent spent fuel storage installation at the Hope Creek Generating Station site or at a location away from the site.
Construction of such an additional spent fuel storage facility could provide long-tcrm increased storage cepacity for Hope Creek Generation Station.
However, it is net likely that this alternative could be implemented in a timely manner to meet the need for additional capacity for Hope Creek 1
Generating Station.
Further, this alternative would waste resources.
1.4 Fuel Reprocessing History Currently, spent fuel is not being reprocessed on a commercial basis in the United States. The Nuclear Fuel Services (NFS) plant at West Valley, New York, was shut down in 1972 for elterations and expansion.
In September 1976, FFS informed the Commission that it was withdrawing from the nuclear fuel reprocessing business. The Allied General Nuclear Services (AGNS) proposed plant in Barnwell, South Carolina, is not licensed to operate. The General Electric Company (GE) Morris Operation (formerly Midwest Recovery Plant) in Merris, Illinois, is in a decommissioned condition.
In 1977, President Carter issued a policy statement on commercial reprocessing of spent nuclear fuel, which effectively eliminated reprocessing as part of the relatively near-term nuclear fuel cycle.
Although no plants are licensed for reprocessing fuel, the storage pools at Morris and at West Valley are licensed to store spent fuel. The storage pool at West Valley is not full, but the licensee (the current licensee is New York Energy Research and Development Authority) is not accepting any additional spent fuel for storage, even from those power generating facilitics that had contractual arrangements with West Valley.
removed from NFS and returned to its owners)(In fact, spent fuel is being j
On May 4, 1982, the license held by GE for spent fuel stcrage activities at its Morris operation was renewed for another 20 years; however GE is committed to accept only limited quantities of additional spent fuel for storage at this facility from Cooper and San Onofre 4
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i 2.0 RADI0 ACTIVE WASTES Hope Creek Generating Station contains radioactive waste treatment systems designed to collect and process the gaseous, liquid, and solid waste that might contain radioactive material. The radioactive waste treatment systems are evaluated in the Final Environmental Statement (FES) dated December 1984.
There will be no change in the waste treatment systems described in the FES because of the proposed spent fuel pool (SFP) expansion.
2.1 Radioactive Material Released to the Atmosphere With respect to releases of gaseous materials to the atmosphere, the only radioactive gas of significance that could be attributable to storing additional spent fuel assemblies for a longer period of the time is the noble gas radio-nuclide Krypton-85 (Kr-85).
Experience has demonstrated that after spent fuel has. decayed 4 to 6 months, there is no longer a significant release of fission products, including Kr-85, from stored spent fuel containing cladding defects.
To determine the average annual release of Kr-85, we assumed that all of the Kr-85 released from any defective fuel discharged to the SFP would be released prior to the next refueling. Enlarging the storage capacity of the SFP has no effect on the calculated average annual quantities of Kr-85 released to the atmosphere each year. There may be some small change in the calculated quantities due to a change in the fuel burnup; this is expected to be a small fraction of the calculated annual quantities.
However, for the purpose of estimating potential radiation doses to members of the public due to the proposed increased storage of spent fuel assemblies, the NRC staff conservatively assumed an additional release of 125 Ci/ year of Kr-85 (US NRC 1985).
Todine-131 releases from spent fuel assemblies to the SFP water will not be significantly increased because of the expension of the fuel storage capacity since the lodine-131 inventory in the fuel will decay to negligible levels between refuelings.
Most of the tritium in the SFP water results from activation of boron and lithium in the primary coolant and this will not be affected by the proposed changes because BWR-primary coolant does not use chemical neutron absorbers like boron. A relatively small amount of tritium is contributed during reactor operation by fissioning of reactor fuel and subsequent diffusion of tritium through the fuel and fuel cladding. Tritium release from the fuel essentially occurs while the fuel-is hot, that is, during operations and, to a limited extent, shortly after shutdown. Thus, expanding the SFP capacity will not significantly increase the tritium activity in the SFP.
Storing additional spent fuel. assemblies is not expected to increase the bulk water temperature during normal refueling above the value used in the design analysis. Therefore, it is not expected that there will be any significant change in the annual release of tritium or iodine as a result of the proposed modifications from that previously evaluated. Most airborne releases of tritium and iodine result from evaporation of reactor coolant, which contains tritium and iodine in higher concentrations than the SFP. Therefore, even if
l 9 there were a higher evaporation rate from the SFP the increase in tritium and iodine releases from the plant, as a result of the increase in stored spent fuel, would be small compared to the amount normally released frcm the plant and that which was previously evaluated in the FES. Section 3/4.11 of the Hope Creek Generating Station TS, which sets limits for liquid and gaseous radioactive effluent discharges from the plant, is not being changed by this action.
2.2-Solid Radioactive Wastes The concentration of radionuclides in the pool water is controlled by the SFP cleanup system and by decay of short-lived isotopes. The activity is highest during refueling operations when reactor coolant water is introduced into the pool, and decreases as the pool water is processed through the SFP cooling and cleanup system. The increase, if any, of radioactivity due to the proposed modification should be minor because of the capability of the cooling and cleanup system to continuously remove radioectivity in the SFP water to accept-able levels.
We do not expect any significant increase in the amount of solid waste generated from the SFP cleanup due to the proposed modification. The expected increase in total waste volume shipped from the Hope Creek Generating Station would be minimal and would not have.any significant additional environmental impact.
2.3 Radioactive flaterial Released to Receiving Waters It is not expected that there will be a significant increase in the liquid release of radionuclides from the plant as a result of the modifications.
It is expected that neither the flow rate nor the radionuclide concentration of the floor cleanup water will change as a result of these modifications. The SFP deminere.lizer removes soluble r.adioactive materials from the SFP water.
The amount of radioactivity on the SFP demineralizer resin may increase slightly due to the additional spent fuel in the pool, but the soluble redioactive material should be retained on the resins. After processing, the amount of radioectivity released to the environment as a result of the modification-would be negligible.
3.0 -RADIOLOGICAL IMPACT ASSESSMENT The radiation dose for this project will net affect the licensee's ability to maintain individual occupational doses within the limits of 10 CFR Part 20, and is as low as is reasonably achievable. Normal radiation control procedures (NUREG-0800, US NRC 1981) and Regulatory Guide 8.8 (US NRC 1978) will preclude any significant occupational radiation exposures.
li The increase in storage capacity from 1290 to 4006 fuel assemblies is not expected to increase the direct radiation dose to operating personnel because of extensive shielding by pool water and by the pool structure. Any dose i
l from the spent fuel is expected to be minimal and, in most cases, undetectable.
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9 - Based on present and projected operations in the SFP area, we. estimate that the proposed operation of the modified SFP will add only e small fraction to the total annual occupational radiation dose at Hope Creek Generating Station.
-Thus, we conclude that the proposed storage of spent fuel in the modified SFP will not result in any significant long term increase in doses received by workers.
4.0 NON-RADIOLOGICAL IMPACT The new spent fuel racks will be shipped by truck to the Hope Creek site for installation in the pool. This is not expected to impact terrestrial resources not previously disturbed during the original construction.
The only nonradiological effluent affected by the SFP expansion is the additional waste heat rejected from the plant. The total increase in heat load rejected to the environment will be insignificant compared to the current total heat load from all plant sources to the environment.
No impact on aquatic biota is anticipated. Thus, the increase in rejected heat will have negligible impact on the environment.
The licensee has not proposed any change in the use or discharge of chemicals in conjunction with the expansion of the fuel pool. The proposed' fuel pool expansion will not require any change to the NPDES permit.
Therefore, the staff concludes that the non-radiological environmental impacts of expanding the spent pool will be insignificant.
5.0 ACCIDENT CONSIDERATIONS 5.1 Design Basis Accidents
- The staff, in the Safety Evaluation Report issued in October 1984,- addressed -
both the safety and environmental aspects of a fuel handling accident. A fuel handling accident may be viewed as a " reasonably foreseeable" design basis event which the pool and its associated structures, systems, and components (including the racks) are designed and constructed to prevent. The environmental impacts of the accident were found not to be significant.
5.2 Severe Accidents-The staff has considered accidents whose consequences might exceed a fuel i
handling accident, that is, beyond design basis events. An accident investigated L
by the NRC involves a structural failure of SFP resulting in a rapid loss of L
all Ftained cooling water, followed by fuel heatua and a zirconium cladding l
fire.
The initiating events that might result in tais severe accident are L
discussed in NUREG/CR-4982, entitled " Severe Accidents in Spent Fuel Pools in l
Support of Generic Issue 82." In addition, the staff issued NUREG/CR-5176, I
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-g-i entitled " Seismic Failure and Cask Drop Analysis of the Spent Fuel Pools at Two Representative Nuclear Power Plants." This report considers the structural integrity of the SFP and the pool response to the initiating events considered.
The staff has recently concluded, nn the basis of the two NUREG documents cited I
above and on NUREG/CR-5281, "Value/ Impact Analyses of Accident Preventive and Mitigative Options for Spent Fuel Pools," and NUREG 1353, " Regulatory Analysis for Resolution of Generic Issue 82, Beyond Design Basis Accidents in Spent Fuel Pools," that no action need be taken to reduce the risk of beyond design accidents in spent fuel pools because of the large inherent safety margin in the design and construction of spent fuel aools.
In view of the i
resolution of Generic Issue 82 the staff concludes t1at an Environmental Impact Statement need not be prepared.
6.0
SUMMARY
The Final Generic Environmental Impact Statement (FGEIS) on Handling and Storage of Spent Light Water Power Reactor Fuel concluded that the cost of the various alternatives reflects the advantage of continued generation of nuclear power with the accompanying spent fuel storage. Because of the differences in SFP designs, the FGEIS recommended environmental evaluation of SFP expansions on a case-by-case basis.-
The occupational radiation dose for the proposed operation of the expanded spent fuel pool is estimated by the staff to be less than one percent of the total arrual occupational radiation exposure for a facility of this type. The small increase in radiation dose should not affect the licensee's ability to maintain individual occupational doses at Hope Creek Generating Station, within the limits of 10 CFR Part 20, and as low as is reasonably achievable.
Further-more, the non-radiological impacts of expanding the spent fuel pool will be insignificant, and none of tbc alternatives are practical or reasonable.
6.1 Alternative Use of Resources This action does not involve the use of resources not previously considered in connection with the Nuclear Regulatory Comission's Final Environmental State-ment, dated December 1984.
6.2 Agencies and Persons Consulted The NRC staff reviewed the licenste's request. No other agencies or persons were consulted.
7.0 BASIS AND CONCLUSIONS FOR NOT PREPARING AN ENVIRONMENTAL IMPACT STATEMENT The steff has reviewed the proposed spent fuel pool modification to Hope Creek Generating Station relative to the requirements set forth in 10 CFR Part 51.
Based upon the environmental essessment, the staff has concluded that there are no significant radioTogical or non-radiological impacts associated with the proposed action and that the proposed license amendment will not have a significant effect on the quality of the human environment. Therefore, the Comission has determined statementfortheproposedamendment. pursuant to 10 CFR 51.31, not to prepare an environmental impac
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8.0 REFERENCES
1.
USNRC,NUREG-0575,"FinalGenericEnvironmentalImpactStatement(FGEIS) on Handling and Storage of Spent-Light Water Power Reactor Fuel," Volumes 1-3, August 1979.
2.
USNRC, NUREG-0800, " Standard Review Plan," Section 13, July 1981 (formerly issued as NUREG-75/087).
3.
USNRC, NilREG/CR-4982 " Severe Accidents in Spent Fuel Pools in Support of Generic Issue 82, July 1987.
4.
USNRC, NUREG/CR-5176, " Seismic Failure and Cask Drop Analyses of the Spent Fuel Pools at Two Representative Nuclear Power Plants," January 1989.
5.
USNRC, Regulatory Guide 8.8, Revision 3, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be as Low as is Reasonably Achievable," June 1978.
6.
USNRC, " Environmental Assessment Related to the Construction and Operation of the Surry Dry Cask Independent Spent Fuel Storage Installation," 1985.
7.
USNRC, " Environmental Assessment Related to the Construction and Operation of the H.B. Robinson Independent Spent Fuel Storage Installation," 1986.
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'USNRC, " Environmental Assessment Related to the Construction and Operation of the Oconee Nuclear Station Independent Spent Fuel Storage Installation,"
1988.
9.
USNRC, NUREG-1074, " Final Environmental Statement," December 1984.
- 10. USNRC, NUREG/CR-1353, " Regulatory Analysis for the Resolution of Generic Issue 82, Beyond Design Basis Accidents in Spent Fuel Pools," April 1989,
- 11. USNRC, NUREG/CR-5281, "Value/ Impact Analyses of Accident Preventive and Mitigative Options.for Spent Fuel Pools," March 1909.
- 12. ' USNRC, NUREG-1048, " Safety Evaluation Report," October 1984.
Dated: June 7, 1990 Principal Contributor:
Clyde Y. Shiraki l
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