NUREG/CR-5281

BNL-NUREG-52180

Value/Impact Analyses of

Accident Preventive and

Mitigative Options for

Spent Fuel Pools

Prepared by J.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor,

K.R. Perkins, A.G. Tingle.

Brookhaven National Laboratory

Prepared for

U.S. Nuclear Regulatory

Commission

NUREG/CR-5281

BNL-NUREG-52180

R4, 9H

Value/Impact Analyses of

Accident Preventive and

Mitigative Options for

Spent Fuel Pools

Manuscript Completed: January 1989

Date Published: March 1989

Prepared by

J.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor,

K.R. Perkins, A.G. Tingle

Brookhaven National Laboratory

Upton, NY 11973

Prepared for

Division of Safety Issue Resolution

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

NRC FIN A3963

ABSTRACT

A series of value/Impact studies were performed for accident preventive

and mitigative options intended to reduce the risks posed by the storage of

spent fuel at nuclear power plants in spent fuel storage pools. Options

studied Included limited low-density reracking of spent fuel, installation of

water sprays above the spent fuel pool, and the installation of redundant

cooling and/or makeup systems. The results of these studies indicated that

the measures were in general not likely to be cost effective. The reason for

this is due to both the low likelihood of a spent fuel pool accident that

could result in a significant radiological release and the high cost of proposed modifications. These insights are largely contingent upon compliance

with guidelines developed for licensees to assure the safe handling of heavy

loads in the vicinity of spent fuel pools thus reducing the likelihood of the

structural failure of the pool and rapid loss of water inventory due to a cask

drop event.

iii

EXECUTIVE SUMMARY

S.1 Introduction

In light of the possibility of a Zircaloy fire in a spent fuel pool,

Generic Safety Issue 82, "Beyond Design Basis Accidents in Spent Fuel Pools,"

was assigned a MEDIUM priority in November 1983.

In a previous study undertaken at Brookhaven National Laboratory (BNL) 1

the radiological risks posed by the storage of spent reactor fuel at commercial reactor sites in the United States was characterized through evaluation

of the likelihood and the consequences of identified scenarios involving loss

of integrity in spent fuel pools. In the current study various options

intended to reduce the risk posed by nuclear power plant spent fuel pools have

been assessed within a value/impact methodological framework. These 6ptions

included both accident preventive and mitigative measures as discussed below.

Limited low-density reracking of spent fuel is a mitigative option which

is intended to reduce radiological releases through obviating the onset of

self-sustaining clad oxidation in the event of loss of pool water inventory.

An assessment of the cost impact of this option was made including the costs

for the provision of the additional storage space required due to earlier

exhaustion of pool capacity. These included pool, drywell, vault, cask, and

silo facilities.

The NRC Standard Review plant (SRP) requires, as a minimum, redundant

cooling systems as well as redundant coolant makeup systems for the spent fuel

pool. To assess the risk control efficacy of these requirements and the

potential for further risk-reduction in plants complying with the SRP, a preliminary evaluation of the risk impact of assuming system redundancy above the

minimum currently required was undertaken. Additionally, for older plants

with comparable SRP requirements, the risk-reduction potential of backfits was

also assessed. Based upon a spectrum of assumed plant configurations, the

financial impact of such modifications were also estimated.

Several methods that might serve to mitigate the consequences of "beyonddesign-basis accidents" in commercial nuclear power plant spent fuel storage

pools were proposed and evaluated to identify which mitigating measures, if

any, appear to merit more detailed analyses.

S.2 Spent Fuel Pool Inventory Reduction Options

The potential risk reduction value and the cost impact of storage pool

system modifications and of alternative onsite spent fuel storage strategies

were assessed.

Structural failure that could result in rapid and complete draining of

water from the pool are predominantly caused by two typfs of initiators, i.e.,

seismic events and a cask drop on the spent fuel pool. The probability of a

severe seismic event has been recently re-evaluated 2 and data from this more

recent document has been used in this study.

v
The limited low density storage option is one in which fuel discharged

from the reactor within the last two years is stored in a low-density configuration. Calculations indicate that it reduces the likelihood of fire initiation following loss of pool inventory, by increasing air circulation

capability, by a factor of five. 3 In order to obtain insight into the

potential cost-effectiveness of the limited low-density reracking option, a

value-impact assessment was performed fotlowing guidelines in the Handbook for

Value-Impact Assessment (NUREG/CR-3568).

Attributes considered included public health occupational exposure, offsite and onsite costs, and cost of industry implementation and operation. The

associated incremental costs to the industry include the replacement of highdensity storage racks with low-density racks, and the cost of increased dry

storage requirements due to the consequent decrease in pool capacity.

A summary of the results is presented in Table S.1. It indicates that

the costs outweigh the potential benefits due to both the low probability of

the accidents under consideration and the high cost of proposed modifications.

S.3 Improvement of Pool Make-up Reliability

The risk-control efficacy of the Standard Review Plan (SRP) requirements

upon pool make-up capability was characterized within a value/impact framework. The approach taken was one of evaluating first the risk-reduction

profile of requirements exceeding those of the SRP. For older plants with

comparable _SRP requirements, -the risk-reduction potential for similar

requirements was also assessed.

The cost/benefit characteristics of adding these improvements to the

spent fuel pool cooling systems is summarized in Table S.2. Only the Installation of an additional cooling pump to System C (Old Existing Plant with Both

Cooling Pumps Required 30% of Time) appears to have non-negligible economic

risk impact. The generalized representation of the Standard Review Plan

requirements indicate that additional requirements would not result in

cost/beneficial improvements.

S.4 Water Spray System

Several accident mitigative measures such as water spray systems,

building ventilation gas treatment systems, and covering fuel debris with

solid materials were considered and evaluated to identify which mitigative

measures, if any, appear to merit further analyses. Only the installation of

a water spray above the spent fuel pool was studied within the value/impact

framework due to its potentially significant risk-reduction properties. In

the event of loss of pool water inventory, and subsequently, fuel damage due

to the generation of fission product decay heat, the pool sprays would serve

the function of decontaminating the radiological release. However, a scoping

value-impact assessment indicates that the addition of a water spray system is

not cost effective.

vi
Table S.1 Summary of Industry-Wide Value-Impact Analysis of

the Inventory Reduction Option

Attributes Best Estimate Evaluation ($1983)*

Public Health 4.00 x 107

Offsite/Onsite Property 6.96 x 106

Industry Implementation

and Operation -1.38 x 109

Net Benefit ($) -1.33 x 10O

Benefit ($)/Cost ($) Ratio 0.035

Ratio of Public Dose Reduction per Million Dollars

Cost (Person-rem/$10 6 ) 29.0

Cost of Implementation per

Averted Person-rem

($/Person-rem) 3.45x10 '

*Based on 1988-dollars, the Best Estimate Net Benefit, Benefit/

Cost Ratio, Public Dose Reduction per Million Dollars Cost and

Cost per Averted Person-rem would be -1.47x10 9 Dollars, 0.032,

26.4 Person-rem and 3.79x10 4 Dollar/Person-rem, respectively.

Cost escalation during 1983-1988 was assu•;;d to be 9.8%.

Table S.2 Value-Impact for Generic Improvements to the Spent Fuel Pool Cooling System*

Improvement Expected Averted Uenefit/

System Description Improvement Cost (1983$) Cost (1983$) Cast Ratio

A. Minimum SRP 1. Additional pump 50,000 None 0.0

2. Additional train 1.0E6 645 to 6640 'C0.01

B. Minimum SRP 1. Additional pump 5.OOO None 0.0

Requirement

With Credit 2. Additional train L.0E6 27 to 330 0.0

for Fire

System

C. Old Existing 1. Additional pump 50,000 2500 to 30.400 .05 to 0.61

Plant With

Both Cooling 2. Additional train L.OES 3160 to 38,550 .003 to 0.04

Pumps Required

30% of Time

0. Old Existing 1. Additional pump 50.000 125 to 1500 .0025 to 0.03

Plant With

Credit for Fire 2. Additional train 1.0E6 159 to 1940 (.002

System

"Quantification reflects a single spent fuel pool.

vii
S.5 Summary and Discussion

Generic analyses of various potential modifications to nuclear power

plant spent fuel pools have been performed. Cast within the framework of

value/impact analysis methodology, the risk-reduction value and the cost

impact of these modifications were evaluated and compared. These were as

follows:

I. The limited low-density reracking of recently discharged fuel to decrease the likelihood of the initiation of self-sustaining clad oxidation in the event of loss of pool water inventory.

2. The addition of a full capacity pump in one pool coolant makeup train

to increase pool cooling reliability.

3. The addition of a completely independent pool coolant makeup train.

4. The installation of pool sprays to attenuate fission product releases

in the event of fuel degradation.

Value/impact assessments were performed. A $1000/per person-rem averted

conversion factor was utilized to convert dose-reduction measures into a monetary measure in the best estimate calculations. None of the risk-reduction

measures were assessed to have a value/impact ratio greater than 1.

Executive Summary References

1. V.L. Sailor et al., "Severe Accidents in Spent Fuel Pools in Support of

Generic Safety Issue 82," NUREG/CR-4982 (July 1987).

2. P.G. Prassinos et al., "Seismic Failure and Cask Drop Analysis of the

Spent Fuel Pools at Two Representative Nuclear Power Plants," NUREG/CR5176 (January 1989).

3. A.S. BenJamin et al., "Spent. Fuel Heatup Following Loss of Water During

Storage,* NUREG/CR-0649 (March 1979).

4. S.W. Heaberlin et al., "A Handbook for Value-Impact Assessment," NUREG/CR3568 (December 1983).

viii
TABLE OF CONTENTS

Page

ABSTRACT ............................................................... iii

EXECUTIVE SUMMARY. ................................... v

LIST OF TABLES ................... ............................. xi

ACKNOWLEDGEMENTS... ..................... ............... x i i

1. INTRODUCTION ...................... 1

1.1 Risk of Accidents in Spent Fuel Pools......................... 2

2. RISK REDUCTION MEASURES ........ ...................... ... .. 5

3. SPENT FUEL POOL INVENTORY REDUCTION ................................ 7

3.1 Introduction .................................................. 7

3.2 Development of Value/Impact Quantification.................... 7

3.2.1 Accident Sequence Frequencies ......... .... .... ;........ 8

3.2.2 Public Health and Offsite Property Damage............ 8

3.2.3 Occupational Exposure (Accidental) ........... . ..... *.. 9

3.2.4 Onsite Property Damage .......... . ..................... 9

3.2.5 Industry Implementation................................ 10

3.2.5.1 Spent Fuel Storage Requirements............... 10

3.2.5.2 Cost Estimate .................... 12

3.3 Value-Impact Assessment............ . .......................... 14

3.3.1 Assumption and Checklist for Identification of

Affected Attributes .................................... 14

3.3.2 Value/Impact Comparison................................ 14

3.3.3 Sensitivity Studies ..................................... 15

4. IMPROVEMENTS OF POOL MAKE-UP RELIABILITY ........................... 31

4.1 Introduction .................................................. 31

4.2 Quantification ................................................ 31

4.3 Results and Conclusions of Value-Impact Study ................. 34

5. ACCIDENT MITIGATIVE OPTIONS .................... ................ 37

5.1 It out o . .. ... . .... .. . .. .. .. . ... . . 37

5.2 Definition of Accident Sequences .............................. 37

5.2.1 Accident Sequence "Al," A Complete Loss of Pool

Water Inventory Followed by a Zircaloy Fire ............ 38

5.2.2 Accident Sequence "A2,u A Complete Loss of Pool

Water Inventory Followed by Clad Failures but Not

Zi rcaloy Fi re .......................................... 38

5.3 Definitions of Mitigative Measures............................ 39

5.3.1 Mitigative Measure "M1," Covering Fuel Debris With

Solid Materials................ ... .................... 39

5.3.2 Mitigative Measure "M2," Water Spray Systems........... 39

5.3.3 Mitigative Measure "M3," Building Ventilation Gas

Treatment System.................., ..................... 39

ix
Page

5.4 Discussion of the Efficacies of Mitigative Measures for Two

Accident Sequences .................... ........... ........... 40

5.4.1 Zircaloy Fires (Al): Mitigative Options ............... 40

5.4.2 Clad Failure Without Zircaloy Fire (A2): Mitigative Options ................................................ 41

5.5 Value-Impact Assessment of a Post-Accident Spray System ....... 41

5.5.1 Characterization of Post-Accident Spray Systems ........ 41

5.5.2 Quantification ......................................... 42

5.6 AnDlDisCUSO. .................................. ......... 43

6. SUMMARY AND DISCUSSION ................. ............ , 47

7. REFERENCES ...................................... 49

APPENDIX A ................... . . ... . .. .......................... 51

x
LIST OF TABLES

Table Page

3.1 Estimated Risks From Spent Fuel Pool Fires ..................... 17

3.2 Offslte Consequence Calculations ............................... 18

3.3 Onslte Property Damage Costs per Accident ($) .................. 19

3.4 Nuclear Power Plant Spent Fuel Storage Data .................... 20

3.5 Storage Options ................................................ 24

3.6 Incremental Storage Costs Associated with Limited Low-Density

Racking in the Primary Pool (1983 Dollars) ..................... 24

3.7 Checklist for Identification of Affected Attributes ............ 25

3.8 Summary of Parameters Affecting Attributes for the Spent

Fuel Pool Inventory Reduction Option ........................... 26

3.9 Summary of Industry Wide Value-Impact Analysis of the

Inventory Reduction Option ..................................... 28

3.10 Value-Impact Sensitivity Analysis of the Inventory Reduction

Option ......................................................... 29

4.1 Failure Frequency for Generic Spent Fuel Pool Cooling and

Makeup SstS esstem .s 0...... a 0 0.. a.........aa..........................a.*.... 0 0 00 0 35

4.2 Value-Impact for Generic Improvements to the Spent Fuel Pool

Cooling System........o ............................. ........... 36

5.1 Offsite Property Damage and Health Costs per Accident .......... 44

5.2 Summary of Industry-Wide Value-Impact Analysis of the PostAccident Spray System ......... ......... ............. 45

xi

ACKNOWLEDGEMENTS

This work was performed for the Reactor and Plant Safety Issues Branch of

the Division of Safety Issue Resolution, NRC/RES. The authors would like to

thank Mr. E. Throm of the NRC for his technical guidance and the many helpful

suggestions he provided throughout this study.

The authors also wish to thank Ms. S. Flippen and Ms. C. Conrad for their

excellent typing of this report.

xiii

1. INTRODUCTION

The Reactor Safety Study (RSS, WASH-1400) concluded that risks associated

with spent fuel storage were extremely small In comparison with severe accidents involving the reactor core. Since publication of the RSS, however, various factors have provided a basis for reexamination of the risks associated

with the storage of spent fuel. First, the storage of spent fuel rather than

its shipment for reprocessing or disposal is resulting in larger spent fuel

pool inventories than anticipated in WASH-1400. Second, the accommodation of

these larger inventories can involve the high-density racking of fuel assemblies and, third, various theoretical models have identified the possibility

of a Zircaloy fire propagating from recently discharged assemblies to lower

power assemblies in the event of a loss of pool water inventory. In the light

of such factors, Generic Safety Issue 82, nBeyond Design Basis Accidents in

Spent Fuel Pools" was assigned a MEDIUM priority in November, 1983.

In a previous study undertaken at Brookhaven National Laboratory (BNL)1

current information and models regarding the likelihood and the consequences

of pool drainage scenarios were adopted to generate a risk profile of the

storage of spent fuel. In this study various options intended to reduce the

risk posed by nuclear power plant spent fuel pools have been considered within

a value/impact methodological framework. These options included both accident

preventive and mitigative measures.

Limited low-density reracking of spent fuel, a risk reduction option

which involves maintenance of recently discharged fuel batches (i.e., discharged within the last two years) in a low-density configuration, is a mitigative option which is intended to reduce radiological releases through obviating the onset of self-sustaining clad oxidation in the event of-loss of pool

water inventory. An assessment of the cost impact of this option was made

including the costs for the provision of the additional storage space required

due to.earlier exhaustion of pool capacity. These included pool, drywell,

vault, cask, and silo facilities.

Of the accident mitigative options considered, one option was studied

within the value impact framework due to its potentially significant riskreduction properties. This involved the installation of a water spray above

the spent fuel pool. In the event of loss of pool water inventory, and subsequently, fuel damage due to the generation of fission product decay heat, the

pool sprays would serve the function of decontaminating the radiological release.

The NRC Standard Review plant (SRP) provides guidance and defines the

acceptance criteria for spent fuel cooling systems and is used by the NRC

staff to determine whether a specific design complies with the Commission's

Rules and Regulations. The SRP requires, as a minimum, redundant cooling systems as well as redundant coolant makeup systems for the spent fuel pool. To

assess the risk control efficacy of these requirements and the potential for

further risk-reduction in plants complying with the SRP, a preliminary evaluation of the risk impact of assuming system redundancy above the minimum currently required was undertaken. Such requirements affect risk through influencing the expected frequency with which loss of water inventory accidents

occur in the spent fuel pool. Additionally, for older plants with comparable

SRP requirements, the risk-reduction potential of backfits was also assessed.

1
Based upon a spectrum of assumed plant configurations, the financial impact of

such modifications were also estimated.

1.1 Risk of Accidents in Spent Fuel Pools

With the U.S. moratorium on spent fuel reprocessing, spent fuel storage

demands are being increased. To accommodate this growing need, existing storage pools are being expanded with the use of high-density storage of fuel.

Furthermore, various dry storage options are being developed and used for extended storage.

To characterize the safety profile of spent fuel pool facilities, a range

of postulated accident sequences was considered, and predictions of the probability of occurrence of these accidents and the resulting consequences were

made in NUREG/CR-4982.' This work was performed under the auspices of the

U.S. Nuclear Regulatory Commission in support of their technical analysis related to Generic Safety Issue 82, "Beyond Design Basis Accidents in Spent Fuel

Pool s."

The objective of the current report is to identify and to assess those

additions or modifications to spent fuel pools that have the potential to

reduce the risk associated with the storage of spent fuel in the spent fuel

storage pool. The methodological framework of value/impact analysis is

adopted in which the risk reduction value, and the cost impact of a given plant benefit are evaluated, .and cast into a numerical framework that permits

the direct comparison of benefitwith cost.

Attention is focused upon those accident sequences that were assessed in

Reference I to dominate the risk posed by spent fuel storage. Consideration

of those measures that reduce the likelihood of, or the consequences of the

accident sequences assessed to be risk dominant is an approach that permits

investigations to be directed towards the plant backfits with the greatest

potential risk reduction effect.

The risk dominant sequences fall into two categories. The first category

involves structural failure of the spent fuel pool due to a seismic event and

the consequent rapid loss of pool water inventory. The probability of such a

severe seismic event has been discussed in NUREG/CR-4982, and has been recently re-evaluated. 2 Data from this more recent document has been used in

the present study.

The generation of fission product decay heat raises the temperature of

the uncovered fuel assemblies to the point where self-sustaining Zircaloy

cladding oxidation is initiated in the most recently discharged assemblies

and, possibly propagation of the cladding fire to neighboring assemblies

ensues. The concomitant radiological releases result in health and economic

consequences both onsite and offsite.

The second category of risk dominant accident sequences differ from those

just described only with respect to the initiating event. Here the structural

integrity of the-pool is compromised through the impact of a heavy object

(i.e., the dropping of a storage cask) upon the pool wall rather than through

a seismic event. The probability of a cask dropping in the spent fuel pool is

2
given in NUREG/CR-4982 conditional upon a probability of 0.1 for structural

failure. The present study uses a conditional probability of 1.0 as discussed

in Reference 2.

Standard improvements in operator training, heavy load procedures, and

equipment as outlined in NUREG-0612 3 are part of the resolution for Generic

Issue A-36 and have been assessed to significantly reduce the likelihood of

the accidental dropping of heavy loads, thus reducing the risk associated with

the cask drop sequence significantly. The risk-reduction multiplicative

factor associated with this resolution has been estimated to be 0.0011 for

affected sequences and has been incorporated in the present study.

The phenomenological progression of the cask-drop accident from the point

of pool drainage is identical to that associated with the seismic sequence

category.

3

2. RISK REDUCTION MEASURES

Given the diversity of plant-specific design and construction of spent

fuel pools, the applicability of any generic analysis of risk-reduction measures is limited both with respect to the characterization of risk impact, and

to the cost of implementation for any one plant. As with any generic assessment, therefore, the current analyses are intended only to provide a broad

evaluation of the value/impact attributes of a given plant modification. In

the event that more detailed analyses are found to be merited, such evaluations may need to be carried out on a plant specific basis.

In general, risk-reduction options may be classified into one of two categories reflecting the fashion in which the plant modification affects risk.

A preventive option is one intended to reduce the frequency of conditions potentially conducive to the release of fission products from the fuel assemblies. The course of events leading to such conditions is defined as an accident sequence. Hence, an option intended to reduce the likelihood of the loss

of pool integrity subsequent to a seismic event, or to reduce the unavailability of the pool cooling systems is classified as a preventive option. A mitigative option is one intended to reduce the magnitude of the consequences that

would result from a selected set of accident sequences. This objective is

generally achieved through reduction of the environmental radiological release

associated with each of the affected sequences.

Given the occurrence of an accident sequence initiator (seismic event,

load drop, loss of pool cooling, etc.), there exists the potential to arrest

the progression of the accident at various stages of its development. For

example, in the event of loss of pool cooling and the gradual boil-off of pool

water inventory, measures taken to increase the reliability of inventory makeup will have direct impact upon the risk profile of such a sequence. Such a

measure, characterized as accident preventive, is addressed in this report.

Given a loss of pool coolant inventory and the uncovery of spent fuel

assemblies, measures taken to reduce the likelihood of the subsequent initiation of self-sustaining clad oxidation will also impact upon the risk profile

of pool coolant-loss accidents. Such a measure, involving the reracking of

in-pool fuel into lower density configurations in order to promote air cooling

subsequent to .water loss is assessed in the current report. Whether this

measure be characterized as accident preventive or accident mitigative is

dependent upon whether the initiation of clad oxidation is viewed as part of

the accident sequence itself, or as part of the consequence scenario. For

definiteness, the former viewpoint will be adopted such that the low-density

fuel reracking measure is viewed as an accident preventive option.

Finally, given loss of water inventory, fuel uncovery and the onset of

clad degradation, measures may be taken to minimize the subsequent release of

radiological fission products. Such measures characterized as accident mitigative, actuation of installed pool sprays and the installation of filtering

systems, are assessed in the current report.

5
0.
3. SPENT FUEL POOL INVENTORY REDUCTION

3.1 Introduction

In NUREG/CR-4982 1 the radiological risks posed by the storage of spent

reactor fuel at commercial reactor sites in the United States was characterized through evaluation of the likelihood and the consequences of Identified

scenarios involving loss of integrity in spent fuel pools. This section addresses the potential risk reduction value and the cost impact of storage pool

system modifications and of alternative onsite spent fuel storage strategies,.

A series of storage concepts were considered. The limited low density

storage option is one in which fuel discharged from the reactor within the

last two years is stored in a low-density configuration. The associated incremental costs to the utility include the replacement of high-density storage

racks with low-density racks, and the cost of increased dry storage requirements due to the consequent decrease in pool capacity.

The risk-reduction basis for low-density racking of fuel is the promotion of air cooling in the event of loss of water inventory of the pool. The

new high-density fuel storage racks restrict air flow and render recently discharged fuel (one to two years) susceptible to self-sustaining oxidation in

the event of pool drainage. The older style fuel baskets with large inlet

holes (3 inch diameter or more per assembly) allow less impeded air circulation. If all recently discharged fuel (less than two years) is kept in low

density fuel baskets and they are separated from the wall and the older fuel

by a one foot gap then the likelihood of the initiation of self-sustaining

oxidation would be significantly reduced compared to the high density storage

configuration. 4 Calculations with the SFUEL Code indicate that for plants

which use a high density storage rack configuration a factor of five reduction

in the likelihood of fire initiation (given loss of pool inventory) can be

achieved by improved air circulation capability." This reduction factor is

based upon the time period following discharge for which SFUEL predicted sufficient decay heat to initiate clad fire.

In order to obtain insight into the potential cost-effectiveness of the

limited low-density reracking option, a value-impact assessment was performed

following guidelines in the Handbook for Value-Impact Assessment (NUREG/CR3568).s

3.2 Development of Value/Impact Quantification

The principal components of any value-impact assessment are the attributes (costs and benefits) that are used to characterize the consequences of

the action proposed in Section 3.1. The attributes described represent the

factors that are affected by this proposed plant modification. Each attribute

measures the change from the existing condition due to implementation of the

option.

Comparisons of the benefit and cost in our value/impact analysis were

carried out in 1983 dollars throughout this report, since many of the available data were expressed in 1983 dollars. , Our results are not sensitive to

the reference year since both costs and benefits were computed on the same

cost index. Furthermore, the cost escalation between 1983 and 1988 was only

7.
9.8% (Reference 17). Our final results (Tables 3.9 and 5.2), however, include

data expressed in 1988 dollars.

3.2.1 Accident Sequence Frequencies

Because of the strong and reinforced concrete structure of LWR spent fuel

storage pools, designed to Category I seismic criteria, initiating events that

would lead to structural failure are extremely unlikely. However, a structural failure that results in rapid and complete draining of water from the pool

could have significant consequences. The study presented in NUREG/CR-4982

concludes that the risk dominant sequences fall into two main categories.

The first category involves structural failure of the spent fuel pool due

to a seismic event and the consequent rapid loss of pool water inventory. Ths

probability of such a severe seismic event has been recently re-evaluated.

Data from. the more recent document has been used in the present study (see

Table 3.1).

The second category of risk involves the compromise of the structural

integrity of the pool through the impact of a heavy object (i.e., the dropping

of a storage cask) upon the pool. The frequency of a cask drop onto a spent

fuel pool is given in NUREG/CR-4982. The conditional frequency of structural

failure of the pool is assumed to be 0.1 in Reference 1. The present study

uses a conditional probability of 1.0 based upon the more recent analyses

reported in Reference 2. The assumed frequencies of the accident sequences

considered in the current analyses are summarized in Table 3.1. Sensitivity

to these assumptions is discussed in Section 3.3.3.

3.2.2 Public Health and Offsite Property Damage

The health and economic consequences of spent fuel pool accidents were

calculated using the MELCOR Accident Consequence Code System (MACCS) Version

1.4. MACCS is a new consequence code developed at Sandia National Laboratories (SNL) and is intended to replace the older CRAC2. The code models are

described in NUREG-1150 (Appendix 0).6 The principal differences from CRAC2

are that MACCS uses a multipuff atmospheric dispersion model and has a new.

radiological health effects model described in NUREG/CR-4214. 7

Two radiological source terms were utilized to reflect a range of. release

assumptions. The worst case assumes an accident that results in a Zircaloy

fire that propagates throughout the entire spent fuel inventory in the pool,

and that the accident occurs 30 days after the reactor was shut down for discharge of the last fuel batch. The best estimate assumes an accident that results in a Zircaloy fire that involves only the last fuel batch to be discharged, and that the accident occurs 90 days after the reactor was shut

down. The source inventory was based on the Millstone I reactor as.discussed

in NUREG/CR-4982.1 The release fractions were also based upon Reference 1.

These are 100% of the noble gases, halogens, and alkali metals, a negligible

release of lanthanides and actinides, 0.2% of the alkali earths and assorted

releases of other isotopes from the fuel and cladding. The source was assumed

to be released in one puff with a uniform particle size distribution and a deposition velocity of 0.01 m/s.

8
The Zion site was used to represent worst case conditions with respect to

population density. Hence Zion data was combined with high source term assumptions to characterize 'worst case' consequences. MACCS sorts meteorological data into 29 categories (or bins) depending on rain, stability and wind

speed. Four random samples from each bin are taken. This assures that

weather sequences which can produce serious consequences are aaequately represented (NUREG/CR-2239)..e The population data for Zion were supplied by the

NRC for 16 angular and 20 radial Intervals out to 500 miles. Within 50 miles

the population density is 860 people per square mile. The data also included

the site-specific wind rose. The land fraction for intervals near Zion were

obtained from the Zion FSAR and for large distances from a national map. For

each grid element the appropriate state average land use and economic data

current in 1980 was used.

For the best estimate calculations the Zion meteorology, and Illinois

state average land use and economic data were employed in conjunction with a

95% land fraction uniform population density of 340 people per square mile

(average of all U.S. nuclear power plant sites). Hence, this site data was

employed in conjunction with the best estimate source term to evaluate bestestimate consequences. No planned evacuation was modeled since this has a

small effect on the total cost and dose impact. However, people were assumed

to be engaged in normal activities which provides some protection from the

cloud shine, ground and inhalation dose pathways. Also people were relocated

at one day if their projected ground shine dose in 7 days would exceed 25

rems. An additional dose limit over 30 years was set to 25 rems.

With this information the offsite costs and public dose impact were computed. The offsite costs include emergency actions, decontamination, interdiction, food disposal, and loss of use of farmland and residential areas.

These costs do not include costs associated with health effects (see Table

3.2).

3.2.3 Occupational Exposure (Accidental)

Exposures for a major spent fuel pool accident were assumed to be similar

to those associated with the TMI-2 accident. For this accident the eslimated

occupational radiation dose from cleanup was less than 4,580 man-rem. This

exposure is small compared to the potential offsite dose impact and more refined quantification appears to be unwarranted.

3.2.4 Onsite Property Damage

Economic risks from light water reactor (LWR) operation are dominated by

onsite losses resulting from replacement power costs. 9 Severe accident risks

also have significant contributions from plant monetary losses (i.e., repair

and refurbishment) and plant decontamination.

The risk-dominant accident sequence as identified in Reference 1 involve:

(1) failure of the pool due to seismic or load drop events resulting in a complete loss of water inventory, (2) Zircaloy fire initiation and propagation

through the spent fuel assemblies stored in the pool, and (3) loss of containment integrity as the spent fuel pool building is breached. The consequences

of these scenarios are expected to be similar to the Category II accident as

defined in Reference 9, i.e., 50% clad melting and contamination. For this

9
case clepnup and decontamination costs are estimated to be approximately. $165

million. Outage times (5 to 7 years) are estimated from EPRI-NP-3380. The

costs for replacement of the spent fuel pool ($46 million for a 400 MT pool)

and costs of permanent disposal of the damaged fuel ($26 million) are also

estimated from EPRI-NP-3380.

The cost of replacement power can be approximated by

C - (0.13 * R + 0.12)106 $/MW year

where R is the fraction of replacement energy by oil fired or noneconomical

power purchases for a given NERC (National Electric Reliability Council)

region. This formula includes credit for the avoided variable fuel cycle cost

of the shutdown reactor. For this study R = 0.41 was used as a best estimate

(national average) and R - 0.9 was used for the worst case. 5 A plant capacity

factor of 65% is factored into the above equation and a 1,000 MW generic plant

was assumed.

The onsite costs are calculated from

U (Cc + Cr + Crp) e-rti -- 2 (1 - e-r(tf'ti))(1 - e~rm) m r2

where U = present (1983) value of onsite property damage,

Cc = cleanup and decontamination cost,

Cr = repair, replacement of spent fuel pool, and disposal of damaged

fuel cost,

Crp - replacement power cost,

tf = years remaining till end of reactor life, taken as 29.8,

ti = year plant starts operating -- 0.0,

-r = discount rate (10%), and

m = years plant is out of service.

The values of U must be multiplied by the accident frequency and number

of plants. U reflects the expected loss due to an accident. When U is multiplied by the accident frequency the result is the expected loss over a reactor

life discounted to 1983 dollars. Table 3.3 summarizes these calculations.

3.2.5 Industry Implementation

3.2.5.1 Spent fuel storage requirements

It has been assessed1 that the risks of self-sustaining cladding oxidation for bundles in high density racks is confined to those that have been

discharged from the core within the last two years. For plants with a reloading period of less than two years, the fuel with the greater likelihood of

cladding oxidation initiation and propagation would be associated therefore

with the last two reload batches. For plants with a reload period of two

years or more, the higher-risk fuel would be confined to the last reload

batch. Where two plants share a spent fuel pool and each has a reloading

period of less than two years, the assumption of staggered reloading emplaces

the last three reload batches entering the pool in the higher-risk category.

Limited low-density reracking of spent fuel is a risk-reduction option that

10
Involves maintenance of recently discharged fuel batches (i.e., discharged

within the last two years) in a low-density configuration. This is a mitigative option in that, subsequent to an accident sequence leading to loss of

cooling to the fuel, implementation of the option is intended to reduce radiological releases through obviating the onset of self-sustaining clad oxidation. Adopting the high density configuration as a base case, the degree of

risk-reduction achieved through a limited low density racking option can be

investigated.

The cost impact of this option involves, first, the cost associated with

the installation of low density racks and, second, the incremental cost associated with altered additional storage requirements resulting from earlier

exhaustion of the spent fuel pool capacity. To evaluate the latter cost, the

time at which additional storage will be required and the degree of that storage must first be evaluated both in the base case and in the case for which

limited low density racking is assumed. The costs associated with fulfulling

these requirements must then be estimated.

Available spent fuel and fuel pool data have been collated for all U.S.

operating PWR and BWR plants. Spent fuel management schemes have been developed for the low density racking option and of evaluating the modified storage

requirements. The results are presented in Table 3.4, "Nuclear Power Plant

Spent Fuel Storage Data.*

Data needed for completion of this collation was assembled with the aid

of the DOE document "Spent Fuel Storage Requirements 1987," DOE/RL-87-11

(Sept. 1987).11 This document provides spent fuel storage inventories and

capacities and utility estimates of future discharges from U.S. commercial

nuclear reactors through the year 2005. Historical data through 1986 are

presented, and projected discharge through the end of each reactor life are

estimated.

Information relative to the low density storage option are reflected in

Columns 12-15 of Table 3.4.

fn estimating the storage capacity decrement of the storage pools, it was

assumed that the fuel bundle packing area densities for PWR and BWR high density racks exceed the low density rack densities by factors of 4 and 3 respectively. These ratios were based on the inter-bundle spacing for high and low

density racks. For PWRs, the bundle center to center spacing ranges from 10.5

to 13 inches for high density racks while for the low density racks the range

is 18 to 22 inches, giving area ratios ranging from 2 to 4.4. For BWRs, these

sizes are 6.5-8 inches for high density racks and 10-13 inches for low density

racks, yielding area ratios of 1.5-4. A sample of spent fuel pool capacity

expansion amendments 1 2 requested by licensees indicated that the average ratio

of modified capacity to the initial capacity was about 3.5 for PWRs and 3.0

for BWRs. For many PWRs, however, the appropriate ratio was approximately 4

and, therefore,, this value was assumed as the generic scaling factor.

Based on the pool storage capacity decrement due to conversion to low

density configurations, the year in which the current pool storage space will

become full (Column 13) and the additional storage space required to the end-*

of-life of the plants (Column 14) were adjusted relative to the base case.

11
The plants were classified into four groups based upon the year in which

the additional storage space will be required. In the majority of the plants

(denoted as X in Column 15), conversion to the low density option would result

in a storage capacity that would not accommodate the current spent fuel pool

inventory. In these plants, construction of additional storage space would

need to begin concurrently with conversion to low density racking and, in certain cases, this additional space would need to be in a low density configuration to accommodate recent fuel discharges. Several plants, denoted Y in

Column 15, have sufficient capacity to accommuodate the low density racking

requirements presently but this space may be exhausted in a time-frame shorter

than that associated with construction of additional storage space.

In estimating the design, construction and licensing time for additional

storage, the lead time estimates of Reference 10 were used.

Plants denoted Z in Column 15 would have no immediate need for additional

storage in the low density racking option. Based upon the lead time estimates

of Reference 10, the year in which construction procedures would need to be

initiated is given in Column 15. One plant, denoted U, currently has

sufficient storage space to .the end-of-life even allowing for low density

storage of the full core reserve and the last 2 reload batches.

It is reiterated that the approach adopted here to evaluate the modified

storage requirements, given implementation of the limited' low density racking

option, is based upon a generic assessment of the relative packing densities

of high and low density racks. No plant'specific variation in this ratio, nor

factors associated with pool-specific geometries have been accounted for in

the assessment. Further, *-the projected storage requirements are based upon

the current maximum storage capacities provided in Reference 11. Offsite

transshipments of fuel and onsite transfers were not accounted for unless the

spent fuel pools are connected by some means as indicated in Table 3.4. These

projecti~ons are anticipated to be sensitive to adjustment of the approximated

pool capacities in Reference 11 and to transshipment assumptions.

3.2.5.2 Cost estimate

Cost estimate for replacing high-density storage racks with low-density

racks for recently discharged fuel have been evaluated. Also the cost for

required additional spent fuel storage capacity based on the storage require*-

ment in Table 3.4 have been evaluated. for four dry-storage concepts and for

additional wet-pool storage. The cost estimates were broken down into two

assumptions:

1. Wait until capacity is required.

2. Provide for required capacity now.

Various societal discount rates, were selected (0, 5 and 10%) to show the

sensitivity to the discount rate for future or delayed actions.

Costing data presented in EPRI NP-3380 provided the basis for the evaluation. This data were parameterized to facilitate calculations and involved:

1. Capital Costs.

2. Operation and Maintenance Costs (O&M).

3. Implementation time for design, licensing and construction (allowing

for overlap).

12
The storage options selected for this study are shown in Table 3.5.

Reracking costs have been discussed in EPRI NP-3380 which involve construction and installation of high-density racks to replace low-density

racks. This data pertained to three reracking options: low-density racks to

borated stainless steel racks, low density to stainless steel racks and stainless steel to borated stainless steel racks.

The cost of conversion from high- to low-density racks per assembly space

was approximated to be equal to the cost of the reracking options considered

in the EPRI report. (Each cost per assembly was approximately equal for the

three options considered.) Since these reracking costs were ultimately

assessed to be typically one to two orders of magnitude less than the incremental cost of additional storage, this approximation did not introduce signi ficant inaccuracies.

Operational and maintenance costs are incurred when the auxiliary storage

capacity is put into operation. From then on these costs will be constant on

an annual basis for the remaining life of the reactor. These costs have been

estimated with the aid of EPRI NP-3380.

Table 3.6 summarizes the results of the cost assessments performed. For

discount rates of 0%, 5% and 10%, the table displays the incremental cost of

spent fuel storage to the end of plant use given conversion to limited lowdensity in-pool storage. The discounts are applied assuming that construction

is Initiated when required. Zero discount is equivalent to the assumption

that construction Is initiated immediately for each plant. The costs are

averaged over LWR units and are provided in 1983 dollars. Data are provided

for the five storage options outlined in Table 3.5. Unit-averaged costs are

provided for each.

Additional statistics generated in the evaluation of the net incremental

costs associated with the limited low-density storage of spent fuel are presented in Appendix A. They may be consulted for confirmation of the summary

figure provided in Table 3.6. All costs are quoted in 1983 dollars. The

tables contain the following information.

Table Al: The incremental cost of additional storage associated with

limited low-density in-pool storage under 'build now' and

'build when needed' (10% discount rate) assumptions.

Tables A2-A6: Cost of additional storage assuming high-density and assuming

limited low-density in-pool storage. Storage-type options:

pool (Table 4), drywell (Table 5), vault- (Table 6), cask

(Table 7) and silo (Table 8). Evaluated at 0%, 5% and 10%

discount rates.

Tables A2a-A6a: Assuming high-density in-pool storage, these tables provide a

breakdown of additional storage costs into construction, and

operation and maintenance components for each option.

13
Tables A2b-A6b: Assuming limited low-density in-pool storage, these tables

provide a breakdown of additional storage costs into construction, and operation and maintenance costs for each

opt i on.

3.3 Value-Impact Assessment

3.3.1 Assumptions and Checklist for Identification of Affected Attributes

. Table 3.7 summarizes the affected attributes of this study while Table

3.8 summarizes the quantification of the affected parameters. Following Reference 1, the mechanism for risk-reduction by the limited low-density reracking option is the reduction of the conditional probability of the initiation

of self-sustaining Zircaloy clad oxidation given loss of pool water inventory. Hence an 80% (see Reference 1) reduction in sequence frequency is

applied uniformly both to the seismic and the cask-drop categories of

sequences to model the risk-reduction value of the option. It should be noted

that an additional, potential risk-reduction mechanism associated with lowdensity racking is a mitigative nature and involves reduction of the potential radiological source term, given fuel degradation. Such an effect could be

modeled in the 'worst case' conditions where participation of older fuel discharge in the clad fire is assumed. Since 80% sequence frequency reduction

removes most of the risk (i.e., 80%) associated with the sequences, and Table

3.9 reveals that the cost impact of this option significantly outweighs its

value, then the modeling of additional accident mitigative values of the

option would not alter the cost/benefit insights.

3.3.2 Value/Impact Comparison

Table 3.9 presents a summary of the value-impact analysis. For the industrial cost of implementation, the best estimate uses the costs associated

with the wet pool storage option while the high estimate utilized dry cask

storage costs. Monetary attributes in Table 3.9 were expressed in 1983 dollars as well as 1988 dollars to account for the escalation of costs in this

period. The cost escalation between 1983-1988 was assumed to be 9.8% (Reference 17).

The results indicate that the costs outweigh the benefits due primarily

to the low probability of the accidents under consideration. An important

factor is the probability of pool failure due to heavy load drops. Table 3.9.

is predicated upon compliance with the guidelines which were developed for

licensees to assure the safe handling of heavy loads.

These recommended guidelines include general rules for all facilities to

reduce the potential for uncontrolled movement of a load or a load drop, such

as by calling for: definition of safe load paths; development of load handling procedures, periodic inspection and testing of the crane; qualifications,

training and specified conduct of the crane operator; and use of guidelines on

rigging.

If these guidelines are not part of the standard operating procedures for

a facility then plant-specific human reliability analyses may be warranted to

characterize the value/impact properties of the current option.

14
3.3.3 Sensitivity Studies

The results presented in Table 3.9 are based on assumptions listed in

Table 3.8. In Table 3.9 best estimate/worst case evaluations are presented.

However, other parameters might be varied to investigate the sensitivity of

these parameters to the final results. Those parameters include:

1. Pool Failure Probability,

2. Discount Rate,

3. Monetary Conversion of Health Effects,

4. Plant Site Economics,

5. Meteorology, and

6. Industrial Implementation.

The sensitivity of the value-impact assessment to variations in each of

these parameters is examined below and* the results are summarized in Table

3.10.

1. Pool Failure Probability

There is a large uncertainty in the risks associated with the structural

failure of the spent fuel pool. It is significantly dependent upon the magnitude of the probability of pool failure due to seismic events and the probability of a cask drop induced pool failure. Since the risk-reduction impact

of low-density reracking is effected through reduction in the frequency of all

pool drainage sequences by a multiplicative factor, then any fractional increase in the assumed frequencies of the sequences is reflected by the same

factorial increase in the risk-reduction value of reracking. For example, if

the base frequency of pool drainage sequences is increased by a factor of 100,

then the risk-reduction value of reracking is increased by a factor of 100

also. Hence, in the high risk-reduction estimate case (Zion demography and

high source term), increasing the assumed frequency of pool drainage sequences

by an order of magnitude results in a benefit/cost ratio of 3.5.

2. Discount Rate

The baseline assumption for the discount rate was 10%. The effect of

changing the discount rate can be seen by using a 5% rate. The affected

attributes are offsite and onsite property costs as well as industrial

implementation. Public dose reduction is not affected since it Is not

discounted in accordance with the guidelines of Reference 5. The impact of a

change in discount rate is relatively small. The best estimate net benefit

would remain somewhat the same since both benefits and costs increase. The

best estimate benefit/cost ratio decreases to 0.028 from 0.035.

3. Monetary Conversion of Health Effects

A major difficulty in the net-benefit method is the evaluation of health

effects in monetary units. The sensitivity of this particular analysis to

that evaluation can be demonstrated by substituting values of $500 and $2,000

per person-rem averted instead of $1,000 per person-rem. The ratio estimates

(public dose reduction/$10 6 cost) are not affected by these variations. Revised best estimates of the net-benefit are $-1.35E9 and $-1.29E9 for $500 and

15
$2,000 conversion respectively relative to the net-benefit of $-1.33E9 associated with the $1,000 conversion factor.

4. Plant-Site Economics

The baseline calculations adopted the economic factors of the surrounding

area of the Zion plant site as a best estimate. However, the economic value

of land at the Zion site is somewhat higher than that of the U.S. average.

The impact of the economics of the area surrounding the plant site was assessed by recalculating the offsite consequence attributes using the economy

of West Virginia as input to the MACCS code. 6 The economy of the West

Virginia site is considered to be much below the national average. The results indicated that site economics do not impact the cost benefit ratio significantly since it may be seen from Table 3.9 that dollar-converted health

effects exceed economic risk by an order of magnitude.

5. Meteorology

The baseline calculations employed Zion weather conditions. Several additional severe accident calculations indicated that varying weather models

caused only a small change in the public health/offsite consequences.

6. Industrial Implementation

The incremental costs associated with spent fuel storage construction

costs and overhead/maintenance is known quite accurately as indicated in

Reference 10. Therefore, the sensitivity to industrial implementation was not

investigated.

Table 3.10 displays the results of the sensitivity studies. It can be

seen that the net benefit is quite sensitive to 4he spent fuel pool failure

probability and to a lesser degree sensitive to the monetary conversion of

health effects. The net benefits are less sensitive to discount rate, economics, and meteorology of the plant site.

16
Table 3.1 Estimated Risks From Spent Fuel Pool Fires

Probability

Event PWR Plant BWR Plant

Structural Failure of Pool Resulting

from Seismic Events 1.8E-6/Ry* 6.7E-6/Ry

Probability of a Cask Drop Caused

by Human Error 3.1E-4/Ry 3.1E-4/Ry

Reduction in Failure Rate for Cask

Drop Implementing Generic Issue A-36 1.OE-3 1.OE-3

Conditional Probability of Pool

Structural Failure Given a Cask Drop 1.0 1.0

Conditional Probability of a Clad

Fire Given a Pool Structural Failure** 1.0 0.25

Frequency of Spent Fuel Pool Fire

from Seismic Initiator 1.8E-6/Ry 1.68E-6/Ry

Frequency of Spent Fuel Pool Fire

from a Cask Drop Initiator 3.IE-7/Ry 7.75E-8/Ry

*Ry = Reactor year.

**NUREG/CR-4982, p. 75.

17
Table 3.2 Offsite Consequence Calculations

Offsite

Public Property Health Dose Damage Case Characterization Source Term* Population (person-rem) ($1983)

1 Average Case Last fuel discharged 340 persons/ 7.97x10 6 3.41x10 9

90 days after dis- mile 2

charge

2 Worst Case Entire pool inventory Zion population 2.56x10 7 2.62x101 ° 30 days after dis- (roughly 860

charge persons/mile2)

*From NUREG/CR-4982.

0O
Table 3.3 Onsite Property Damage Costs Per Accident ($)

Item Best Estimate Worst Case

Cleanup and

Decontamination 1.65E8 1.65E8

Repair 7.2E7 7.2E7

Replacement Power 8.67E8 1.66E9

Total Number of

Operating Years

Remaining 29.8 years 29.8 years

Number of Years

Plant is Out of

Service 5 years 7 years

Expected Dollar

Loss 8.24E9 1.29E10

19
PLANT NAME

TABLE 3.4 Nuclear Power Plant Spent Fuel Storage Dota(&)

CURRENT RACK CONF MODIFIED CONF(c)

TYPE STARTUP SHUTDOWN FULL RE- FUEL INV. W. FILLUP ADD. ST--- UA FILLUP ADD. U--

YEAR YEAR CORE LOAD CYCLE 1986 CAP. YEAR RACE REQ. CAP. YEAR RACE REQ.

(d) (.) (e) (MON.) (e) (b) (.) (1) (e) (9) (e) (h) (M) (e) (9)

CLASSIFICATION

(I)

ARK NUCLEAR I P 1974 2008

ARK NUCLEAR 2 P 1980 2012

BEAVER VALLEY I P 1976 2016

BEAVER VALLEY 2 P 1987 2028

BELLEFONTE I P 1992(f) 2028

BELLEFONTE 2 P 1996(J) 2030

BIG ROCK I B 1965 2001

A BRAIDWOOD I P 1987 2026

A BRAIDWOOD 2 P 1988 2027

B BROWNS FERRY 1 B 1974 2014

B BROWNS FERRY 2 B 1976 2014

BROWNS FERRY 3 B 1977 2017

BRUNSWICK 1 B 1977 2010

P (u)

BRUNSWICK 2 a 1976 2010

P (u)

A BYRON I P 1985" 2024

A BYRON 2 P 1987 2026

CALLAWAY 1 p 1984 2024

B CALVERT CLF1 P 1975 2014

B CALVERT CLF 2 P 1977 2018

CATAWBA 1 P 1986 2026

r• CATAWBA 2 P 1988 2028

0 CLINTON 1 B 1987(,i) 2027

B COMANCHE PK 1 P 1989 2030

B COMANCHE PK 2 p 1989 2030

A COOK I p 1976 2009

A COOK 2 p 1978. 2009

COOPER STN B 1974 2008

CRYSTAL RVR 3 P 1977 2018

DAVIS-BESSE 1 P 1978 2017

DIABLO CANYON 1 P 1985 2025

DIABLO CANYON 2 P 1988 2025

DRESDEN 1 B 1980 1984

DRESDEN 2 B 1970 2008

DRESDEN 3 B 1971 2008

DUANE ARNOLD B 1975 2010

ENRICO FERMI 2 B 1987(J) 2025

FARLEY I P 1977 2012

FARLEY 2 P 1981 2012

FITZPATRICK B 1975 2016

FORT CALHOUN P 1973 2808

FT ST VRAIN a 1979 207

GINNA P 1970 200

GRAND GULF 1 B 1985 2022

HADDAM NECK P 1968 2007

HARRIS I P 1987(J) 2028

B (v)

B HATCH 1 a 1974 209

B HATCH 2 B 1979 2012

HOPE CREEK B 1987(j) 2026

HUMBOLDT BAY B 1983 1978-

177 60 18 448 988 1998 377

177 68 18 288 988 1999 85s

167 69 18 283 833 1998 853

167 73 18 0 1088 2009 8s8

206 84 18 0 1058 209 1900

205 84 18 0 1065 2011 1900

84 20 12 188 441 1995 95

193 64 19 0 lo5o 199 3827

193 84 18 0 (a) (n) (.)

784 228 20 1328 3471 2602 3226

784 228 20 1192 3471 (.) (.)

784 228 20 1004 3471 201 2441

580 188 18 840 1883 1990 2401

0 160 180

50 188 18 750 1839 1991 2281

0 144 144

193 88 18 0 1050 1994 3827

193 88 18 0 (m) (n) (m)

193 84 18 84 1340 2005 1129

217 96 24 618 830 1992 2213

217 96 24 432 1000 (n) (m)

193 72 16 84 2816 2026 0

193 72 16 0 2816 2028 0

824 172 18 0 2672 2008 2672

193 80 12 0 1895 2016 2087

193 GO 12 0 1687 (n) (m)

193 80 18 646 2270 1998 1241

193 88 Is 424 (m) () (.)

548 118 12 648 2388 197 1238

177 72 24 302 1167 2006 482

177 60 18 197 735 1996 2490

193 86 24 51 1324 2011 617

193 86 24 0 1324 2011 517

464 0 - 683" 720 0

724 168 18 168 3637 1998 1015

724 158 18 1468 3537 200 693

388- 128 18 698 2860 1999 998

764 276 20 0 2306 1997 6365

167 68 18 410 1407 2008 298

157 88 18 268 1407 2008 140

680 180 18 1012 2864 1997 2248

133 46 18 834 729 1994 413

1482 240 24 0 604

121 32 12 470 1016 200 219

80 268 18 284 3124 1998 4392

157 52 18 694 1168 1997 319

167 52 18 0 3361 2026 0

0 - 0 2057(w) - -

650 198 18 1107 3181 200 2874

680 198 18 745 2845 (n) (m)

764 232 18 0 3976 207 2820

184 a - 390 488 - 0

8(8120) (k)

50 136) 1989

419(138 (k) 650(146) 2000

554 5168) 2000

654 1IGO 202

381 40 1992

294 2521 1998

(m) 1990

5574(684) 1998

(0) 1998

2659(468) 1996

1051(376) (k)

1s07 (376) (k)

264(284)

(m) (k)

830(289) 1998 1264(292)(. M~

2183 144) 2021

2188 144) 2023

1984(344) 2000

2788(198) 2010

(m) 2010

1602(266) 1991

(W) 1991

1902 C232) 1993

941 72) 1999

375(120) 1988

1089(85) 200

1069 (86) 20"6

2905(816 1992

2905 316 1994

1638 2568 1991

1201 652 1990

999 188 1997

9991138 1999

2134 ,38 1991

459 90 WIc

240

824 64 1994

2062 636 1992

858 104 1990

3039(104 2028

4850(588) 1998

(W) 1998

3946(464) 201

737

973

1287

1298

2404

2404

175

4383

(0)

4594 Cm)

3363

3163

3033

4413

(a)

1632

2789 (C,)

226

210

328

26861

(04)

2"9(,,)

1702

648

2860

772

772

1647

1326

1610

6469

708

648

2988

683

411

5484

631

0

4050

(C)

8748

x Y

x

2 C1998)

z(1998)

Y z(1998)

z(19)

x

Z(1998)

2(200) Y

Y

Z C(1989)

2(1996)

X Z 201)

z(2001) CLOSED

Y

2(1990)

Y

Y

Z (1993) Z(1995)

Y

x

X 2 (1990)

Y

Y

U

Z 1992) Z(1992)

z(1997)

CLOSED -
PLANT NAME

TABLE 8.4 Nuclear Power Plant Spent Fuel Storage Dmta(a)(cont'd)

CURRENT RACK CONF MODIFIED CONF(c)

TYPE STARTUP SHUTDOWN FULL RE- FUEL INV. UXM. FILLUP ADD. ST- 1- FILLUP ADD. 3TD;

YEAR YEAR CORE LOAD CYCLE 1986 CAP. YEAR RACE REQ. CAP. YEAR RACE REQ.

(d) (e) (e),(MON.) (a) (b) (e) (f) (e)(g) (e) (h) (f) (e)(g)

----------- ------ ---------------------------------------- -------------------

INDIAN Pt 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

LACROSSE

B LASALLE CTY I

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MC-UIRE 1

MCCUIRE 2

MILLSTONE 1

MILLSTONE 2

MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2 r• OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILORIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B qUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR.BEND 1

SALEM 1

SALEM 2

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH 1

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

P 1982 1980

P* 1974 2006

P 1978 2015

P 1974 2014

B 1989 2002

B 1982 2022

B 1984 2023

B 1986 2024

B 1990 2029

P 1972 2008

P 1981 2021

P 1984 2023

B 1970 2010

P 1976 2015

P 1986 2025

B 1971 2007

B 1989 2005

9 1987 2028

P 1978 2018

P 1990 2020

P 1973 2013

P 1974 2013

P 1974 2014

B 1989 2004

P 1971 2011

P 1986 2024

P 1986 2026

P 1987 2028

B 1974 20098

B 1974 2008

B 1987 2026

B 1972 20098

P 1970 2007

P 1972 20098

P 1973 20098

P 1974 2008

B 1973 2007

B 1973 2007

P 1975 20098

P(u) 1971 2007

B 1986 2025

P 1977 2016

P 1981 2020

P 1988 1999

P 1983 2012

P 1984 2013

P 1987(j) 2031

P 1981 2021

P 1982 2022

B 1988(j) 2027

P 1987 2027

P 1989 2028

120 a - 193 68 18

193 78 18

121 87 12

72 24 12

784 220 18

764 220 18

764 224 18

784 220 18

217 73 18

193 72 15

193 72 15

580 198 24

217 68 18

193 84 18

484 120 18

582 184 24

784 278 24

157 65 18

157 85 18

177 80 16

177 60 18

177 80 18

680 128 18

204 68 24

241 85 18

241 95 18

241 85 18

784 228 18

764 220 18

748 224 18

589 192 24

121 32 12

121 32 12

121 40 12

121 40 12

724 160 18

724 .16 18

177 69 18

157 48 16

824 192 18

193 80 18

193 84 18

157 52 24

217 109 24

217 109 24

193 64 16

193 80 18

193 80 18

5680 184 18

193 52 12

193 52 12

18 758

464 980

292 1817

389 963

261 440 132 2098

0 2040

0 2040

793 1478

219 1463

186 1463

1536 2184

474 1112

0 1836

428 2287

1444 2778

0 4049

294 1737

235 0

590 1312

381 0

529 825

1392 2600

545 798

0 1329

0 1329

0 1329

1462 8814

1496 3819

0 4020

1320 2320

446 1502

408 (in)

388 1386

415 (in)

1393 3657

1428 3897

287 1080

270 544

0 3172

344 1170

174 1170

148 218

147 800

147 800

0 1238

212 1381"

136 (m)

0 2685

0 1989

0 1989

- 0

1994 493

2004 536

1999 579

1992 205

1990 9824

at 4098 " I(n) (in)

1998 4236

1996 632

2005 965

2006 989

1987 2480

1997 823

2016 S41

2004 355

1998 884

2011 1971

1999 1886 (n) (m)

1989 2102

(n) (mn) 1991 1021

1994 912

1988 8a8

2005 1117

2006 1121

2007 1121-

1997 1812

1997 1589

2009 2548

1993 1612

1995 849

(n) (m)

1993 1142

(n) (m)

2005 50S

(n) (m)

2004 226 1990 888

2007 2452

1997 1007

2001 1168

1995 2382

20098 1281

1995 2806

(n) (in)

2006 2835

2023 258

2024 258

572(186) (k)

81 (162) 1994

741( 74) 1993

344( 48) 197

840(880) (k)

(m) (k)

1144 448 1988

1180 440 1991

1038 146 1987

1081 144 1997

1031 144 1998

1792 198" (k

844 165)

1332 188 2007

1757 240 1998

2408 184 1990

3497 278 2007

1152(195 1992

(m) 1992

465 120)

20998 256 1989

594 88) (k)

819 170) 1998

819 170) 1997

819 170) 1999

2902 468) 1991

2939 440) 1991

3124 44 20083

1936 192 1988

1214 96)1990

(m) 1990

1026(120) 1988

S9)?4(480) 2002

(m) 2002

686(138) 1992

26 (98) (k)

2404 (394) 2001

690(16S) 1989

8885188) 1992

1008 270) 1989

m 1989

1989

852(128) 2000

061(240) 1989

(m) 1989

1949(388) 2000

1867(104) 2017

1867(104) 2018

ge1

992

801

301

11144

(n)

4992

5116

1070

1397

1421

2872

1291

1045

835

1252

2533

2451

(m)

2641

(m)

1381

1424

1039

1627

1881

1631

2724

2489

8444

1896

1137

(i)

1502

(m) 1463

(m)

640

956

3220

1487

1887

8172

1648

3400

(m)

3371

670

570

CLASSIFICATION

(i)

CLOSED

X

Z(1990) z (1989)

X

X

Y

X

z(1993)

Z (1994)

X

X

z(2003)

Z (1994) Y

Z (2003)

Y

X

X

X

Y

X

X

X

X

X

Z (2992)

z(1993)

Z (1994)

Y

Y

Z (1999)

Y

Y

z (199)

Z (1998)

Y

z(1997)

Y

Y

Y

Y

Y

Z (1998)

Y

Y

Z (199)

Z (2013)

Z (2014)
TABLE 8.4 Nuclear Power Plant Spent Fuel Storage Date(m)(contbd)

PLANT NAME

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

a SusquEHANNA 1

B SUSQUEHANNA 2

THREE MILE ISL

TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOGTLE 1

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION I

A ZION 2

TYPE STARTUP SHUTDOWN

YEAR YEAR

(d)

P

P

P

P

P

P

P

P

P

P

B

P

P

P

P

P

1978 2010

198l 2823

1984 2024

1972 2012

1978 2013

1985 2822

1986 2024

1974 208"

1976 2011

1972 2007

1973 2807

1987 2027

1988 2026

1972 2012

1984 2023

1985 2024

19s8(i) 2026

1999(J) 2027

1986 2026

1961 200

1973 200

1974 2088

FULL

CORE

(0)

217

217

167

167

167

764

764

177

193

167

167

193

193

388

784

217

193

193

193

78

193

193

RE- FUEL

LOAD CYCLE

() (ON.)

76

72

68

63

63

232

232

73

48

46

48

84

684

132

156

'so

as

Be

76

as

72

72

1818

18

18

18

10

18

18

12

18

18

18

18

18

12

18

18

16

18

18

18

18

INV.

1980

(C)

444

164

112

488

386

488

324

284

379

424

446

0

a

1322

128

92

0

0

52

341

674

603

CURRENT RACK CONF

1W. FILLUP ADD. SWCAP. YEAR RAGE REQ. (b) (e) (f) - ( a) (a) -

728

1078

1278

1044

1764 (y)

2840

2840

1401 (x)

1408

1404 638

1117(x)

1117(x)

2870

2658 1388

1294

(m)

1348

721

2079

(W)

1987

2881

2012

(n)

2800

(n) 2806

2804

2802

(n)

200

1999

1998

208

2001

(n)

2808

1999

1995

(n)

1182

1128

781

97

la')

7288

Cm) 76

373

384

(0)

2496

(0)

4018

1143

2891

(on)

867

1296

(o)

MODIFIED CONF (c) UWW. FILLUP ADD. STU=

CAP. YEAR RACE REQ.

(e) (h) (f) (e) (9)

272(162) (k) 1638

644(144) 1992 1668

888(138) 1999 1189

2331(159) 2006 674

(a) 2005 (in)

4268(898) 1995 868

()1995 i)

1148 1997 513

112:0 (96) 1998 61

184(144) 1995 G81

( 17) 1996 (a) 1478 (22) 2009 3251

(a) 2099 (i) 2342(284) 1993 1598

2034(312) 1994 4642

838(176) 1997 1871

514(248) 1994 3411

(in 1994 (10) 884(162) 1999 1313

493 78) 1998 284

1431 (218) 1988 1943

(in) 1988 (m)

CLASSIFICATION

(1)

xy()

Z(1995

Z 2001

Z 2001

Z 1991

Z 1991

Z(1993

Z 1994

Z 1991

Z 1991

Z 1998

Z 1998

Z 1989

Z 1990

7 1993

7 1990

Z 1990

Z (199

Y

x

x

A

B

E

d

0

1i

INDICATES COMMON POOL SHARED BY TO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFERs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

UTILITY DATA AS OF 12/31/1986 (Reference DOE/RL-87-11)

PROJECTED MAXIMUM CAPACITY USING CURRENTLY LICENSED TECHNOLOGY(| .e. HIGH DENSITY RERACKING)

BASED ON THE CONVERSION OF POOLS TO LOW DENSITY RACKS FOR THE FUEL LESS THAN 2 YEARS OLD.

P-PWR BSBWR, GuHTGR

UNIT fN NUMBER OF ASSEMBLIES

YEAR WHEN THE STORAGE SPACE RUNS OUT AT THE PLANT SITE. FULL CORE RESERVE(FCR) ASSUMED.

ADDITIONAL STORAGE REQUIRED TO THE END-OF-LIFE OF THE PLANTS. FCR ASSUMED.

NUMBERS IN () INDICATE LOW DENSITY RACKS NEEDED TO ACCOMODATE FUEL LESS THAN 2 YEARS OLD.

CLASSIFICATION OF PLANTS ACCORDING TO ADDITIONAL STORAGE NEED (AS OF 1988).

X PLANTS WHICH CURRENTLY NEED ADDITIONAL STORAGE SPACE WHEN POOLS ARE CONVERTED TO LOW DENSITY.

Y PLANTS WHICH CURRENTLY HAVE SPACE BUT WHOSE SPACE WILL RUN OUT BEFORE CONSTRUCTION OF ADDITIONAL SPACE

WHEN POOLS ARE CONVERTED TO LOW DENSITY RACKS (CONSTRUCTION TIME BASED ON THE CASK OPTION.)

Z PLANTS WHICH CURRENTLY HAVE SUFFICIENT SPACE BUT EVENTUALLY NEED CONSTRUCTION OF ADDITIONAL SPACE

WH POOLS ARE CONVERTED TO LOW DENSITY RACKS( MES IN ) INDICATE THE YEAR

WHEN CONSTRUCTION OF ADDITIONAL STORAGE SPACE SHOULD BEGIN - BASED ON THE CASK

STORAGE METHOD.)

U PLANTS WHICH HAVE SUFFICIENT SPACE UNTIL END-OF-LIFE OF THE PLANT.

STARTUP DATE BASED ON PROJECTED YEAR OF FIRST DISCHARGE.

NEED ADDITIONAL STORAGE SPACE AS OF 1996.

INCLUDED IN UNIT I

SAME AS UNIT 1

NO SPACE IN THE POOL FOR FCR+FUEL LESS THAN 2 YEARS OLD WHEN CONVERTED TO LOW-DENSITY CONFIGURATION.
TABLE 3.4 Nuclear Power Plant Spent Fuel Storage Data(a) (cont'd)

(u) SOME ROBINSON 2 PWR FUEL IS STORED AT THE BRUNSWICK (BWR) REACTOR SITE.

)IN 1986, HARRIS 1 IDENTIFIED SPACE FOR THE FUTURE STORAGE OF BWR FUEL. (HARRIS 2 IS A PWR.)

w CAN BE CONVERTED TO PWR STORAGE IF NECESSARY.

(x) THIS NUMBER IS NOT EXPLICITLY GIVEN BY THE UTILITY. MAXIMUM CAPACITY WAS DERIVED FROM

. UTILITY'S STATEMENT REGARDING THE TIME WHEN THE STORAGE SPACE RUNS OUT.

(y) INCLUDES STORAGE CAPACITY OF DRY STORAGE INSTALLATION (ISFSI).

N%
Table 3.5 Storage Options

Number Storage Option Special Condition

1 Wet-Pool

2 Drywell

3 Vault Fuel is Canned

4 Cask 10 MTU Cask

5 Silo

Table 3.6 Incremental Storage Costs Associated With Limited Low-Density

Racking in the Primary Pool (1983 Dollars)

STORAGE PER UNIT ALL PLANTS

OPTION 0UP 5%' 10% 0%" 5% 10%

POOL 2.17+7 1.67+7 1.28+7 2.34+9 1.80+9 1.38+9

DRYWELL 9.13+6 8.24+6 6.85+6 9.86+8 8.90+8 7.40+8

VAULT 2.07+7 1.67+7 1.28+7 2.24+9 1.80+9 1.38+9

CASK 1.20+7 1.22+7 1.05+7 1.30+9 1.32+9 1.13+9

SILO 1.56+7 1.22+7 9.35+6 1.68+9 1.32+9 1.01+9

*Zero % discount rate

capacity is built now

corresponds to the case where additional storage 16

Notes: 1. These costs include the cost of in-pool reracking and the

incremental costs associated with the change in additional

storage requirements resulting from the decrease in primary

pool capacity.

2. Assuming the extra storage capacity is built when required,

two discount rates are applied.

24
Table 3.7 Checklist for Identification of Affected Attributes

ATTRIBUTE QUANTIFIED UNAFFECTED

1. Public Health X

2. Occupational Exp. X

(Accidental)

3. Occupational Exp.

(Routine) X

4. Offsite Costs X

5. Onslte Costs X

6. Regulatory Efficiency X

7. Improvement in Knowledge X

8. Industry Implementation

& Operation X

9. NRC Development X(a)

10. NRC Implementation X(a)

11. NRC Operation x (a)

(a)Based on DOE/RL-87-11 (Reference 11) virtuv.lly all plants will require

additional at-reactor spent fuel storage. NRC costs for at-reactor

storage licensing actions are not affected by this alternative.

25
Table 3.8 Summary of Parameters Affecting Attributes for the Spent Fuel Pool Inventory Reduction Option

Factors Affecting Attributes Attributes Description Quantification References

Public Health A. Pool Failure Probability Seismic Structural Failure Table 3.1 Dose Reduction High - PWR 1.8 x IOr'lRy Ref. 2

* BUR 1.68 x 1loLow g 0

Failure due to Cask Drop High - PIJR 3.1 x 10-7 lRy Ref. 2 - B•R 7.76 x 10-a

Low - 0

Others . 0

B. Number of Pools Involved PWR 69 DOE/RL-87-11

BWR 39

C. Average Remaining Life- PI4R 29.8 DOE/RL-87-11 Time of Plant BWR 27.9

0m D. Radioactive Inventory Worst Case Total Inventory 30 days NUREG/CR-4982 Release After Discharge Best Estimate Last Fuel Discharge 90 Days After Discharge

E. M4eteorology Zion

F. Population Worst Case Zion (860 people/sq. mi.)

U.S. Average 340 people/sq. mi.

G. Risk Reduction 80% Sequence Frequency 801 NUREG/CR-4982

Reduction

Reduction of Considered to be insig- Occupational nificant compared to Exposure Public Health Impact -- Accidental

Reduction of No significant change Occupational expected Exposure

-- Routine
Table 3.8 Summary of Parameters Affecting Attributes for the Spent Fuel Pool Inventory Reduction Option (Cont'd)

Factors Affecting

Attributes Attributes Description Quantification References

Offsite Property A, B, C. 0, E, F, G Same as those of Public Health

Damage Ecomony Zion

Discount Rate 10%

Onsite Property Decontamination, Refur- 5 years NUREOCR-3568

Damage bishment and Replace- EPRI MP-3380

ement Power Time.

Discount Rate 10%

Reg. Efficiency Unaffected

Improvement in Unaffected

Knowledge

Industry Imple- Additional Storage High (Pool Option) DOE/RL-87-11

mentation and Option and Reracking Low (Drywell Option) EPRI NP-3365

Operation Cost.

Discount Rate 10%

NRC Development Unaffected

/Implementation/

Operation
Table 3.9 Summary of Industry -Wide Value-Impact Analysis of the Inventory

Reduction Optionta)

Dose Reduction (Person-Rem) Evaluation ($1983)

Best High (b Best High (b)

Attributes Estimate Estimateb) Estimate Estimate

Public Health 4.00 x 104 1.28 x 105 4.00 x 107 1.28 x 10O

Occupational Exposure

/Accidental - 0 - 0 -0 - 0

/Routine - 0 - 0 - -0

Offsite Property 1.42 x 106 2.22 x 106

Onsite Property 5.54 x 106 4.25 x 107

Regulatory Efficiency Unaffected

Improvement in Knowledge Unaffected

Industry Implementation

and Operation -1.38 x 109 -1.13 x 109

NRC Development, Implementation and Operation Unaffected

Net Benefit ($) -1.33 x 10 9(c)-9. 5 7 x 108

Benefit ($)/Cost ($) Ratio 0. 0 3 5 (c) 0.15

Ratio of Public Dose Reduction per Million Dollars

Cost (Person-rein/$10 6) 2 9 . 0 (c) 113.0

Cost of Implementation per

Averted Person-rem

($/Person-rem) 3 . 4 541 0a(c) 8.83x10 4

(a)Based upon a U.S. pool population of 108.

(b)High estimate is based on the 'Worst Case' source term release and Zion

site population (see Table 3.2). (c)Based on 1988 dollars, the Best Estimate Net Benefit, Benefit/Cost Ratio,

Public Dose Reduction per Million Dollars Cost and Cost per Averted Personrem would be -1.47x10 Dollars, 0.032, 26.4 Person-rem and 3.79x10" Dollar/

Person-rem, respectively. Cost escalation during 1983-1988 was assumed to

be 9.8% (Reference 17).

28
Table 3.10 Value-Impact Sensitivity Analysis of the Inventory Reduction Option

Public Dose

Net Reduction/ Benefit/

Parameter New Value Benefit $ Million $ Cost

Baseline Best Estimate -1.33E9 29.0 .035

Pool Failure Probability Factor of 100 Increase 3.32E9 2900 3.5

Discount Rate 5% -1.75E9 22.2 .028

Monetary Evaluation of

Health Effects $500/person-rem -1.35E9 No Change .020

$2000/person-rem -1.29E9 No Change .063

Economics of the Plant

Site W. Virginia -1.34E9 24.5 .029

29

4. IMPROVEMENT OF POOL MAKE-UP RELIABILITY

4.1 Introduction,

In the current section, the risk-control efficacy of Standard Review

Plan (SRP) requirements upon pool make-up capability is characterized within a

value/impact framework. The approach taken is one of evaluating first the

risk-reduction profile of requirements exceeding those of the SRP. Second for

older plants comparable to the SRP requirements, the risk-reduction potential

for similar requirements is also assessed.

The methods used to provide cooling for the removal of decay heat from

stored assemblies in a spent fuel pool vary from plant to plant. Spent fuel

assemblies are cooled and covered with water during all storage conditions.

If circulation of the pool cooling water is disrupted, e.g., due to station blackout, pump failure, pipe rupture, etc., the water temperature of the

pool would steadily increase until boiling occurred.

Thermal -hydraulic analyses of the consequences of partial or complete

loss of pool cooling capability are a routine part of the safety analysis

reports required for licensing. Generally, these analyses address several

scenarios ranging from likely to extremely unlikely conditions. Even under

pessimistic assumptions the water level in the pool would drop only a few

inches per hour. Thus, there 'is considerable time available to restore normal

cooling or to implement one of several alternative backup options for cooling.

The NRC Standard Review Plan13 provides guidance and defines the acceptance criteria for spent fuel pool cooling systems and is used by the NRC

staff to determine whether a specific design' complies with the Commission's

Rules and Regulations.

The SRP requires conformance with General Design Criteria 2, 4, 5, 44,

45, 46, 61 and 63 along with several specific criteria relating to operating

temperatures and structural classification. Although these requirements are

very general the SRP requlires, as a minimum, redundant cooling systems as well

as redundant makeup systems. Thus, four failures must occur before the spent

fuel pool can be uncovered. A station blackout could cause these multiple

failures, but the likelihood of recovering from a station blackout before the

spent fuel is uncovered (at least 24 hours) is extremely high.

4.2 Quantification

Four *generic" fuel pool cooling and makeup systems have been examined to

illustrate the possible range of failure frequencies for these systems. The

failure estimates are also "generic" in nature and may tend to overestimate

the actual failure rates. A detailed systems analysis of a specific cooling

system (including recovery actions) is likely to result in a somewhat lower

failure' rate considering the time frame (days) for recovery. The four representative systems are outlined below.

31
System A - Minimum cooling and makeup system required by the SRP: 13 One full

capacity cooling train with redundant activecomponents (i.e., redundant valves and pumps). One Category I makeup system and one

backup pump or system (not required to be Category I) which can be

aligned to a Category .1 water supply.

System B - Minimum cooling and makeup system with credit for makeup from fire

system (Note that some plants may identify the fire system as the

backup in System A).

System C -Typical older system comparable to current SRP requirements: One

cooling train with backup active components (but backup components

are required to supplement cooling about 30% of time"1 ); One safety

grade makeup train and one non-safety grade makeup system.

.System D - Typical older system (System C) with third makeup train available

(e.g., fire system).

Simplified failure estimates are listed in Table 4.1 for these four representative systems. Note that systems A and B are not intended to represent

actual systems. Rather, they are representative of the minimum requirements

in the current SRP. Systems C and D are based on a previous analysis' and

represent older plants.

The failure rates and system failure frequencies are based on failure

rate data from the Reactor Safety Study'1 with methods similar to the Prioritization Study. 15 Specifically:

° An 0.1 per reactor year frequency for the initiating event is based on

the Reactor Safety Study estimates for failure of one spent fuel pool

cooling train.

° The conditional failure probability of 0.05 (for the second train of

Type A and B) represents a relatively high commnon mode failure proba- bility given previously in the Prioritization Study. s

° The conditional failure probability of 0.3 (for the second train of

Type C and 0) represents the assumption that both cooling pumps are

necessary 30% of the time. Thus a failure of one pump represents a

failure of the system.

° Train 1 of the makeup system is assumed to be independent of the cooling system and is assigned a low common cause contribution. Note that

the likelihood of the prolonged (greater than 24 hours) station blackout event is assumed to. be low (<10-6 per reactor year). Otherwise

station blackout could provide a common cause failure of all pumps.

a Train 2 of the makeup system is assumed to have a high common cause

contribution (-5%) since it is likely to have several active components in common with the first train of makeup.

32
*The 5% conditional failure probability of the fire system is arbitrary

and can only be construed as engineering Judgement. The likelihood of

successful cooling with the fire system after all else has failed will

depend greatly-upon plant specific equipment and emergency procedures.

The failure frequencies for these four systems range from 2.2 x 10-5 to

1.9 X 10-7 per year. Although a loss of cooling and subsequent heat n~ is a

very slow event (several days), previous analyses by Benjamin et al. have

shown that after the fuel is uncovered, the remaining water would block air

circulation and clad overheating would occur even for fuel which had been

cooled for 1 year. However, because of the lack of air circulation within the

spent fuel holders, the oxidation reaction would be oxygen starved and clad

melting would not occur. Thus, catastrophic failure of the spent fuel would

not be expected. Consequence estimates have been obtained previously for this

type of accident (see page 65 of liVREG/CR-4982, Cases 3 and 4). Only the

.noble gases were released in significant quantities. The consequences were

found to be minimal (about 4 person-rem). Thus the offsite health consequences of this type of accident are expected to be minimal. However, the

economic consequences of such an accident appear to be important. Since the

reactor could not operate until the spent fuel pool was available, the cost of

the replacement power, until the spent fuel pool building was decontaminated

and the equipment was repaired, could be considerable. It is estimated that

repairs and decontamination would take from one. month to a year depending upon

the degree of fuel damage and contamination. Replacement power was calculated

based. on a 1,000 t4W generic plant and a 65% capacity factor.5 The onsite

cost would then range. from 16 to 195 million dollars conditional upon a spent

fuel pool accident. Integrated over the life of the plant (taken to be 29.2

years, the industry average remaining plant lifetime), the expected cost

associated with gradual coolant loss sequences could be as high. as $125,000

per plant (assuming failure rate frequencies for a plant with system C: see

Table 4.1).

In calculating the expected averted costs-associated with improved makeup systems, the product of the resultant accident sequence frequency reduction

and the onsite costs associated with the accident, discounted at 10% over the

remaining plant lifetime is evaluated.

Two alternative systems for improvement of the fuel pool cooling system

have been assessed as potentially cost-beneficial for the four system types:

" Alternative 1 is simply another full capacity pump and associated

valves to eliminate the need for running the cooling system without a

backup pump (System C). The cost estimate for this alternative is

$50,000 (1983) based upon References 16 and 17.

" Alternative 2 is a completely independent makeup train.- We assume

this system to be similar to the primary spent fuel pool supply train.

The hardware requirements include a Category I water storage tank

(200,000 gallon capacity), pumps, controls and piping. The cost of

the independent makeup train plus overhead and maintenance costs were

estimated with the aid of References 16 and 17. The cost is estimated

at $106' (1983).

33
4.3 Results and Conclusions of Value-Impact Study

The cost/benefit characteristics of adding either of these improvements

to the four generic spent fuel pool cooling systems is summarized in Table

4.2 where a discount rate of 10% is assumed. Only improvements to one cooling

system (Type C) appears to have non-negligible economic. risk impact. The

generalized representation of the Standard Review Plan requirements indicate

that additional requirements would not result in cost/beneficial improvements.

Although the assessment was based on the 1983 dollars, minor variations of

equipment costs due to inflation between 1983 and 1988 do not significantly alter the conclusions of this study.

For those older plants (Type C) which operite the spent fuel pool cooling

system without a backup, these preliminary evaluations indicate that the addition of a full capacity pump or a redundant makeup train is not a cost-beneficial measure (see Table 4.2). However, the estimated cost of a full capacity

pump is approaching the range of averted cost. Thus such an improvement may

be justifiable on a plant-specific basis.

34
Table 4.1 Failure Frequency for Generic Spent Fuel Pool Cooling and Makeup Systems*

Total Failure

Failure Rates Per Demand Frequency

Coolinq System up SZstem Per System

System Type Description Train 1* Train 2 Train I1 Train 2 Fire System Year

A. Minimum SRP

Requirement 0.1 0.05 0.015 0.05 3.8 x 10-6

B. Minimum SRP

Requi rement

With Credit for

Fire System 0.1 0.05 0.015 0.05 0.05 1.9 x 10-7

L" C. Old Existing

Plant with Both

Cooling Pumps

Required 30% of

Tfmett 0.1 0.3 0.015 0.05 2.2 x 10-

0. Old Existing

Plant With 0

Credit for Fire

System 0.1 0.3 0.015 0.05 0.05 1.1 x 10"6

* Reference 1.

•*Ugnits of failure per system year.
Table 4.2 Value-Impact for Generic Improvements to the Spent Fuel Pool Cooling System*

Improvement Expected Averted Benefit/

System Description Improvement Cost (1983$) Cost (1983$) Cost Ratio

A. Minimum SRP 1. Additional pump 50,000 None 0.0

2. Additional train L.0E6 545 to 6640 "0.01

8. Minimum SRP 1. Additional pump 50,000 None 0.0

Requirement

With Credit 2. Additional train 1.0E6 27 to 330 0.0

for Fire

System

C. Old Existing 1. Additional pump 50,000 2500 to 30.400 .05 to 0.61 Plant With

Both Cooling 2. Additional train 1.0E6 3160 to 38,550 .003 to 0.04

Pumps Required

30% of Time

D. Old Existing 1. Additional pump 50,000 125 to 1500 .0025 to 0.03 Plant With

Credit for Fire 2. Additional train 1.0E6 159 to 1940 <.002 System

*Quantification reflects a single spent fuel pool.
5. ACCIDENT MITIGATIVE OPTIONS

5.1 Introduction

This section discusses several proposed methods that might serve to mitigate the consequences of "beyond-design-basis accidents" in commercial nuclear

power plant spent fuel storage pools. Two hypothetical accident sequences,

defined In Section 5.2, have been considered. The efficacy of three mitigating systems is evaluated for each of the two accident sequences. The objective of these preliminary evaluations is to identify which mitigating measures, if any, appear to merit more detailed analyses. A value-impact assessment for one of the mitigative measures is performed in Section 5.5.

It must be noted that the designs and structural details of spent fuel

pools are plant specific. Also, the current inventories of spent fuel vary

greatly from plant to plant. Therefore, the evaluations that follow will not

apply equally to all plants. In the event that more detailed analyses are

found to be merited, such evaluations will need to be carried out on a plantspecific basis.

5.2 Definition of Accident Sequences

Generic Safety Issue 82, "Beyond Design Basis Accidents in Spent Fuel

Pools," was the subject of a recent risk assessment' limited specifically to

accident sequences resulting in complete or partial loss of water inventory of

a spent fuel pool. Initiating events for such sequences included:

- structural failure of pool due to seismic events, missiles or cask

drop; - water inventory boil-off resulting from prolonged loss of cooling water

circulation capability; and

- partial drain down of pool due to pneumatic seal failure.

Accident sequences that were analyzed in Reference 1 ranged from catastrophic cases which involved Zircaloy fires to less severe situations in

which damage was limited to multiple cladding failures.

For purposes of this report, two sequence types have been selected to

represent a bounding case with respect to the source terms involved. Less

severe cases, such as partial loss of water inventory and loss of cooling

capability are not discussed, since the source terms released to the environment from these sequences are relatively small and thus the associated risk

reduction potential is bounded by those discussed here. The less severe

accident sequences are also relatively low frequency. For both the sequences

considered, it is assumed that radiation levels severely limit or preclude

human access to the spent fuel pool area. Also, it should be noted that most

of the accident sequences are postulated to occur simultaneously with other

plant disruptive events due to common initiating causes such as seismic

events. The sequences are characterized In the following sections. For

convenience, the accident sequences have been denoted by the symbols "Al" and

KA2." 1

37
5.2.1 Accident Sequence "Al," A Complete Loss of Pool Water Inventory Followed by a Zircaloy Fire

The accident sequence, "Al," reflects an upper bound scenario with respect to potential radiological releases. It is based on the following

assumptions: - structural failure of the pool results in a complete loss of water

inventory;

- the age and storage configuration of the spent fuel meet the criteria

for ignition of a Zircaloy fire (see Reference 1, pp. 49-62); - the Zircaloy fire propagates through all of the spent fuel assemblies

stored in the pool; - a major fraction of the U02 fuel pellets are oxidized to U30s and relocate as a bed of rubble on the bottom of the drained pool; and - the containment integrity of the building covering the spent fuel pool

is breached.*

The fire is assumed to burn and propagate through the spent fuel inventory for a period of approximately eight hours, producing localized maximum

temperatures in the range of 15000C as each fuel batch successively ignites

and the cladding Is consumed (see Reference 18 for the temperature-time profiles for several typical cases).

Theoretical analyses and expertimental data that relate to an Al type

sequence are very limited, and, in particular, no studies have been made which

can be readily adapted to characterize the bed of debris resulting from a

spent fuel Zircaloy fire. As far as a source term for sequence Al is concerned, the release data obtained from the Chernobyl accident, i.e., the fractional releases that occurred after the initial burst release, are possibly

pertinent. Such data are summarize in Section 6 of Reference 19. The Chernobyl fractional releases of specific isotopes c•iffer somewhat from the estimates made in Reference 1, Table 4.2, pg. 69. In particular, the cesium

release fractions were an order of magnitude smaller in the Chernobyl case.

For purposes of bounding the risk reduction potential of mitigative options

discussed in Section 5.3, the release fractions estimated in Reference 1 and

utilized in Section 3 of the current document will be adopted, pending further

investigation of the relevance of the Chernobyl data. The sourceterm is

obtained by convolution of the fractional releases with the. radionuclide

inventory as a function of decay time (tonnes of fuel in each discharge

batch).

5.2.2 Accident Sequence "A2," A Complete Loss of Pool Water Inventory Followed by Clad Failures but Not Zircaloy Fire

The accident "A2" sequence, is based on the following set of assumptions:

- complete loss of water inventory due to structural failure of the pool;

*Spent fuel pools are normally housed in "secondary containment" areas (as,

e.g., in BWRs), or in auxiliary buildings that provide only limited contain

ment capability; however, even limited containment, when intact, can greatly

attenuate the source term. The sequence Al assumes that the building roof

has collapsed as a result of the intense heat of the Zircaloy fire, and vig

orous convection carries the plume into the atmosphere.

38
-conditions for the ignition of a Zircaloy fire are not satisfied (see

Reference 1, Tables 3.1 through 3.5);

- the containment integrity of the building is intact;

- pool structural damage is such that water inventory cannot be restored

before extensive clad failures; and

- all assemblies with decay times of 5 years or less subsequently suffer

100% failures of the clad pressure envelope.

The fractional releases of selected radionuclides from the fuel (gap releases) are assumed to be as follows:

Noble gases: 1.00

Cesium isotopes: 0.05

5.3 Definitions of Mitigative Measures

Several measures have been proposed which might effectively mitigate the

consequences or interrupt the progress of beyond-design-basis accidents in

spent fuel pools (e.g., see Reference 1, Section 6). Design criteria for such

systems depend on the particular accident sequence against which protection is

sought. Design details would be plant specific as appropriate for the particular pool configuration. Not all measures would be applicable to all spent

fuel pools.

5.3.1 Mitigative Measure "Ml," Covering Fuel Debris With Solid Materials

Mitigative measure, "Ml,* applies only to accident sequence Al, i.e., a

catastrophic accident in which the stored fuel inventory has been reduced to a

bed of hot rubble. It consists of the a contingency plan to dump massive

amounts of various solid materials into the drained pool to cover the rubble

to a depth of several feet. It is assumed that the solid materials are not

stockpiled onsite, but could be obtained in a timely manner on an ad hoc

basis, the materials being commonly available in all parts of the country.

The types of material or potential value include sand, clay, dolomite, boron

compounds, lead, etc. "Ml" would consist of a generic contingency plan that:

- specifies the types and quantities of materials that would be used;

- conceptual studies on how the materials could be emplaced; and

- analyses on attenuation of radioactive releases and gamma-ray shielding

efficacy.

5.3.2 Mitigative Measure "M2," Water Spray Systems

Mitigative system, "M2,* consists of a water spray system located above

the pool, having sufficient- capacity to block or mitigate a given accident

sequence.

5.3.3 Mitigative Measure "M3," Building Ventilation Gas Treatment System

Mitigative system, "M3," consists of a building ventilation/filter system

designed to reduce the concentration of airborne radioactivity before

discharge to the environment.

39
5.4 Discussion of the Efficacies of Mitigative Measures for Two Accident

Sequences

This section presents qualitative evaluations of the mitigation measures

for the different accident sequences. The objective is to identify which

measures, if any, appear to merit more detailed, quantitative analysis.

5.4.1 Zircaloy Fires (Al): Mitigative Options

Al/Mi: An Al sequence initiated by a beyond-design-basis seismic event

implies serious damage in other sections of the nuclear plant, as well as

major disruption of emergency services in the surrounding region. Given a

catastrophic Zircaloy fire, the M1 measure would attenuate prolonged radioactive releases from the bed of rubble, but it appears dubious that the measures

could be implemented soon enough to prevent a major release to the environment

during the first few hours of the sequence.

The question to be evaluated here, is whether it would be cost effective

to develop a generic contingency plan as a cooperative effort among all licensees, and, if so, hgw much development effort would be merited? The contingency plan would be concerned with an extremely low frequency, but high consequence event.

The results at Chernobyl can be used as a rough gauge of the efficacy of

this measure, when carried out on a strictly ad hoc basis with apparently no

advanced planning. It is reasonable to assume-t-hat a generic M1 plan could be

prepared that, if ever needed, could be more effective than the Chernobyl experience, i.e., be implemented sooner and provide higher attenuation of radioactive releases.

It is our evaluation that M1 merits a small effort, perhaps a few manmonths of study to determine whether a more intensive planning effort would be

cost effective.

Al/M2: A seismic Category I safety-grade water spray system drawing on a

Category I reservoir of water could be effective in mitigating the consequences of a Zircaloy fire in a spent fuel pool that has lost its water inventory. Such a system built to meet seismic safety standards would have a very

high probability of surviving a seismic event. It would also act as a standby

for an accident initiated by a shipping cask drop resulting in structural

failure of the pool. A value/impact analysis for a spray system is described

in Section 5.5.

In situations where spray actuation is retarded relative to fire initiation, there is the possibility that oxidation could be aggravated by the water

source. Consideration of this scenario is beyond the scope of the current

analysis.

Al/M3: No building ventilation system could cope with an Al accident

sequence.

40
5.4.2 Clad Failure Without Zircaloy Fire (A2): Mitigative Options

A2/Ml: In the event of a structural failure which allows the pool water

inventory to drain, recovery from the accident would present difficult problems even though no Zircaloy fire occurred. Radiation levels above the pool

would be extremely high, preventing human entry. Structural repairs which

would allow the pool to be refilled with water would be difficult, is not impossible. Therefore, an M1 type measure might prove necessary for recovery.

The cost effectiveness of developing a contingency plan faces the same uncertainties as described earlier for Al/Mi. It is our evaluation that a modest

effort appears merited and could be included in the scope of the Al/Mi study.

A2/M2: (See AI/M2. The same evaluation applies here).

A2/M3: In an A2 sequence, in which the building integrity is not

breached, an M3 building ventilation and gas treatment system could reduce the

discharge of airborne particulate radioactivity. To be effective, the system

would have to be qualified to survive the A2 initiating event, and have adequate capacity to handle extremely large volumes of air. Removal of noble

gases from the circulating air would require heroic measures - a system of

cryogenic filters (e.g., liquid nitrogen cooled zeolite beds), that could be

purged into high pressure cylinders at frequent- intervals, and, of course, a

large supply of liquid nitrogen would be necessary. Investment in an effective M3 system to cope with an extremely low frequency A2 accident sequence

would not appear to be reasonable.

5.5 Value-Impact Assessment of a Post-Accident Spray System

5.5.1 Characterization of Post-Accident Spray Systems

Post-accident spray systems were discussed in Section 5.4 as a potentially significant mitigative measure for spent fuel accidents. A scoping valueimpact assessment has been performed in this section to provide some insight

into the potential cost-effectiveness of introducing spray systems. This

assessment is a rough approximation (order of magnitude) of a cost and benefit

comparison and generally follows the guidelines outlined for "First Approximation of Benefits and Costs" in NUREG/CR-3568. 5

It should be emphasized that this assessment is scoping in nature due to

the many assumptions involved and large uncertainties in data, especially with

respect to the estimation of seismic accident sequence frequencies, and decontamination factors assumed for spray systems. The benefit estimate has the

potential to be increased significantly through modification of assumptions

with regard to cask drop frequencies.

The principal risk reduction effect of spray systems is achieved by decontaminating radiological releases thus permitting greater retention of fission products in the pool and the pool building. Results of analyses of

severe reactor accidents (Draft NUREG/CR-4551, Vol. 1, in support of Draft

NUREG-1150) 2 ° indicate that containment spray systems can be significantly

effective in reducing source terms and severity of consequences of nuclear

reactor accidents.

41
In this assessment, it was assumed that the major benefit of spray

systems derives from reduction in the offsite consequences. In NUREG/CR-3673;

it was estimated that occupational exposure would be small compared to the

offsite impact of a radiological accident. The incremental contribution to

risk reduction through mitigation of the accident would then be a much smaller

and second order effect. ' Decontamination and Replacement Power Costs would

also be assumed to be minimally influenced by the use of a spray system.

5.5.2 Quantification

The effectiveness of a spray system is measured by the Decontamination

Factor (DF - The amount of release of the radioactive species to the environment without spray divided by the amount of release with spray). Decontamination factors for a fuel pool spray system are difficult to estimate without

detailed calculations. A DF for containment spray systems (for major reactor

accidents) was assigned a best estimate of 45 across radionuclide groups in

the NUREG-1150 analysis of the Surry plant. 2 0 That factor will be assumed for

the current calculations. From Table 5.1 it may be seen that a Df of 45 has

the effect of reducing offsite consequences to a small fraction of their original levels. In practical terms, therefore, a DF of 45 provides an upper

bound upon the value/impact ratio relative to spray effectiveness.

In Reference 1, seismic initiators and cask drop accidents were

identified as potentially dominant contributors to the risk for spent fuel

pool accidents. Contributions from other sequences were assessed to be

relatively small due both to lower initiator frequencies and lesser

radiological releases. For purposes. of the current scoping analysis, an

accident sequence frequency was assumed corresponding to data presented in

Table 3.1.

Preliminary construction and industry maintenance costs were based upon

References 16 and 17. Assumed hardware requirements included a Category I

water storage tank (200,000 gallon capacity) and a spray system including

pumps, spray nozzles, and associated hardware. Total costs (industry wide:

108 pools) were estimated at $1.1E+8 (1983$).

The offsite consequences were calculated using the 14ACCS code. 6

s The Zion

plant was selected as a reference plant since detailed population and land

data were available. Two calculations were performed varying source terms and

population density. The population density of 340 persons/sqt. mile used in

the "Average Case" is a U.S. average figure. The average source term

developed in NUREG/CR-4982 was utilized here. The "Norst Case" represents the

combined effect of the worst-case source term developed in NUREG/CR-4982 and a

high population density (860 persons/square mile: Zion population). The Zion

economic data and Zion meteorology were used for both calculations. The offsite property damage in MACCS is given in 1980 dollars and has been escalated

to 1983 dollars. Table 5.1 summarizes these calculations..

Results of the value/impact analysis are shown in Table 5.Z. The table

indicates a first estimate of industry-wide potential benefit of $4.2E+7 based

purely upon the dollar conversion of radiological dose to the population, and

a potential cost of $1.1E+8. The expected averted offsite economic impact is

estimated to be $6.77E+6. These figures are based upon the average case

release/population assumptions, and a 10% discount rate for monetary costs.

42
For the worst case release/population, the expected dose reduction benefit

over plant lifetime (with $1000/person-rem conversion) is $1.18E+8 and the

economic impact reduction is $5.20E+7.

5.6 Conclusions

Inspection of Table 5.2 reveals that for best estimate calculations, the

installation of pool sprays is not a cost-effective measure. High estimates

of risk-reduction (high source term and Zion demography) can be seen to result

in marginally cost-effective comparisons for this option. As a generic

industry-wide analysis based upon the U.S. population of plant sites,however,

utilization of Zion site demography for consequence evaluation results in an

overly conservative estimate of risk-reduction properties of a given plant

modification. Use of Zion demography in the 'high estimate' calculations is

intended only to provide insights into the potential site-specific risk reduction achievement of a given backfit. In-plant, pool-specific evaluations of

risk-reduction would need to be performed, however, to reach conclusions regarding the cost-effectiveness of any modification on a plant-specific basis.

As with the fuel reracking measure discussed in Section 3, the dominant sensitivity factors in the cost-benefit evaluation are the frequencies of the pool

failure sequences. A given percentage increase in the assumed freqdency of

all sequences leading to structural failure of the pool would result in an

equal percentage increase in the risk-reduction value of the pool spray option. Current assumptions regarding the frequencies of the seismic and heavy

load, drop sequences are based upon the sequence analyses of Reference 1 and

the updated seismic and load drop fragilities reported in Reference 2. The

current study may easily be used to reflect alternative assumptions regarding

sequence frequencies through straightforward numerical scaling adjustments of

the results generated.

43

6. SUMMARY AND DISCUSSION

Generic analyses of various potential modifications to nuclear power

plant spent fuel pools have been performed. Cast within the framework of

value/impact analysis methodology, the risk-reduction value and the cost

impact of these modifications were evaluated and compared. The analyses

focused upon the risk-dominant accident sequences Identified in Reference 1.

Both accident preventive and accident mitigative risk-reduction options were

assessed. These were as follows:

1. The limited low-density reracking of recently discharged fuel to decrease the likelihood of the initiation of self-sustaining clad oxidation in the event of loss of pool water inventory.

2. The addition of a full capacity pump in one pool coolant makeup train

to increase pool cooling reliability.

3. The addition of a completely independent pool coolant makeup train.

4. The installation of pool sprays to attenuate fission product releases

in the event of fuel degradation.

Best-estimate calculations of the following value/impact attributes were

performed: Public dose, offsite economic impact, onsite economic impact and

industry implementation and operation costs. Other attributes identified,

such as occupational exposure and regulatory efficiency improvement were considered either to be negligible contributors to the value/impact balance or

unaffected within the scope of the current project. A $1000/per person-rem

averted conversion factor was utilized to convert dose-reduction measures into

a monetary measure in the best estimate calculations. None of the riskreduction measures were'assessed to have a value/impact ratio greater than 1.

A series of sensitivity calculations were performed in which various

parameter inputs and modeling assumptions were varied. Factors varied included source term magnitude, site demography economics and meteorology, accident sequence frequencies, cost discount rate, ,•se/dollar conversion and the

cost of implementation to industry. The only factors with significant influence upon the balance of value against impact was found to be the frequencies

of the sequences that involve structural failure of the pool due to seismic

events and heavy load drop events. The aggregate frequency of all such

sequences is found to behave as a simple multiplier in evaluation of the

risk-reduction value of the low-density reracking and the spray installation

options. Hence to increase this aggregate frequency by a factor of 10, say,

is to increase the risk-reduction value of each of these two plant modifications by a factor of 10 also. In the case of low-density reracking, this

aggregate frequency would need to be increased by two orders of magnitude to

enter the cost-effective domain while, for spray installation, increase by a

single order of magnitude would increase the value/impact ratio above 1. It

should be noted that even then, to draw inferences regarding the costeffectiveness of a pool modification on a plant-specific basis would require

plant-specific analyses.

Given this sensitivity to the sequence frequencies, it is important to

identify the factors and assumptions that influence these frequencies. These

include seismic hazard magnitudes and pool fragilities. Reference 2 provided

47
the basis for the current quantification. Additional important assumptions

relate to the effect of implementing the resolution of Generic Issue A-36 in

the handling of heavy loads in the vicinity of the pool. These assumptions

are summarized in Table 3.1 and are based upon discussions in Reference 1.

48
7. REFERENCES

1. V.L. Sailor et al., "Severe Accidents in Spent Fuel Pools in Support of

Generic Safety Issue 82," NUREG/CR-4982 (July 1987).

2. P.G. Prassinos et al., "Seismic Failure and Cask Drop Analysis of the

Spent Fuel Pools at Two Representative Nuclear Power Plants," NUREG/CR5176 (January 1989).

3. H. George, "Control of Heavy Loads at Nuclear Power Plants," NUREG-0612

(July 1980).

4. A.S. Benjamin et al., "Spent Fuel Heatup Following Loss of Water During

Storage," NUREG/CR-0649 (March 1979).

5. S.W. Heaberlin et al., "A Handbook .for Value-Impact Assessment," NUREG/

CR-3568 (December 1983).

6. U.S. Nuclear Regulatory Commission, "Reactor Risk Reference Document,"

NOREG-1150, Appendix 0, Vol. 3, Draft for Comment (February 1987).

7. J.S. Evans et al., "Health Effects Model for Nuclear Power Plant Consequence Analysis," NUREG/CR-4214 (1985).

8. D.C. Aldrich et al., "Technical Guideline for Siting Criteria Development," NUREG/CR-2239 (1982).

9. R.P. Burke et al., "Economic Risks of Nuclear Power Reactor Accidents,"

NUREG/CR-3673 (April 1984).

10. J.S. McCartney and R.B. Cairns, "Cost. Comparisons for On-Site Spent-Fuel

Storage Options," EPRI NP-3380 (May 1984).

11. DOE Richland Operations Office, "Spent Fuel Storage Requirements 1987,"

DOE/RL-87-11, UC-85 (September 1987).

12. P. Bleimeis et al., "Review and Evaluation of Spent Fuel Pool Expansion*

Potential Hazards Consideration," SAI-84-221, WA (July 1983).

13. U.S. Nuclear Regulatory Commission, Standard Review Plan, "9.1.3 Spent

Fuel Pool Cooling and Cleanup System," NUREG/CR-0800 (July 1981).

14. U.S. Nuclear Regulatory Commission, "Reactor Safety Study: An Assessment

of Accident Risks in U.S. Commercial Nuclear Power Plants," NUREG-75/104,

WASH-1400 (October 1975).

.15. U.S. Nuclear Regulatory Commission, "A Prioritization of Generic Safety

Issues," pp. 3.82-1 through 6 (December 1983).

16. United Engineers and Constructors, Inc., "Capital Cost: Pressurized

Water Reactor Plant," NUREG-0241 (June 1977).

49
17. R.S. Means Co. Inc., Building Construction Cost Data, 1988, 46th Annual

Edition, Kingston, MA (1987).

18. N.A. Piscano et al., "The Potential for Propagation of a Self Sustaining

Zirconium Oxidation Following Loss of Water in a Spent Storage Pool,"

Draft Report (January 1984) PDR Accession No. 8505090480.

19. U.S. Nuclear Regulatory Commission, "Report on the Accident at the Chernobyl Nuclear Power Station," NUREG-1250 (January 1987).

20. A.S. Benjamin et al., "Evaluation of Severe Accident Risks and the Potential for Risk Reduction: Surry Power Station, Unit 1," Draft Report,

NUREG/CR-4551 (February 1987) PDR Accession No. 8703170262; M. L. Ernst,

et al., "Reactor Risk Reference Document," Draft Report, NUREG-1150 (February

1987) PDR Accession No. 8703100040 (Vol. 1), 8703170207 (Vol. 2), and

8703180080 (Vol. 3).

50
APPENDIX A

Additional statistics associated with Limited Low-Density Storage of

Spent Fuel.

51
TABLE Al. COST TO PROVIDE THE ADDITIONAL STORAGE CAPACITY TO COMPENSATE

FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS STORAGE OPTIONS

(1983 DOLLARS)

----------------------------------------------------------------------------------------------------------------

l I.. .LOWDEN BUILT NOW IBUIL T WHENNEEDED( 10%DISCOUN T RATE)

PLANT NAME TYPE SHUTHUDO0- RACKS .............................................................. -I ...

YEAR NEEDED .. POOL DRYWELL _VAULT .CASK I SIO I POOL .DRYWELL .VAULT I SILO

A

A

B

B

A

A

u'

B

B

A

A

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK I

BRAIDWOOD 1

BRAIDWOOD 2

BROW"S FERRY 1

BROWNS FERRY 2

BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

BYRON 1

BYRON 2

CALLAWAY 1

CALVERT CLF 1

CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON I

COUN"CHE PK 1

COMANCHE PK 2

COOK 1

COOK 2

COOPER STH

CRYSTAL RVR 8

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND GULF I

HADDAM NECK

HARRIS 1

2008

2012

2016

20286

2028

2030

2001

20286

2027

2014

2014

2017

2010

2010

2024

2028

2024

2014

2016

2026 2928 2026

2027

2030

2030

2009

2009

2008

2018

2017

2026

2026

1984

2008

2008

2010

2026

2012

2012

2015

2008

2007

2008

2022

2007

20286

120

138

138

148 188

168

40

262

(a)

684

(a)

468

378

376

264

(a) 168

192

(a)

144

144

344

198

(a)

268

(a)

232

72

120

8686

316

316

286

552

138 138 280

98

240

84

164

104

1.88.7

2.39.7

3.4687

3.64.7

4.02+7

4.02.7

8.87.8

3.74,7

9.06+8

1.08.7

1.19.7

1.23+7

1.64+7

1.64+7

8.3*36

3.11.7

1.94.7 2.$6-7

2.60+7

2.89.7

4.08+7

4.08.7

1.62.8

6.08+7

1.26.7

1.43.7

1.43+7

1.61+7

2.24+7

2.24+7

4.33+.

2.38.7

1.70.7

2.00.7

2.00+7

2.13+7

2.77.7

2.77.7

2.49+8

4.62.7

2.32.7

2.4657

2.87.7

1.02.7

1.23.7

1.03+7

7.2686

3.17.7

1.0657

1.14.7

1.38+7

6.06+6

7.09.8

8.00+8 2.16-8

2.48+7

1.94+7

2.13.7

2.69+7

9.68+8

1.63+7

1.28.7

3.638+

4.31+7

1.36+7 1.63+7

1. 97*7

7.11.8

1.20+7

1.00+7

2.13.8

3.94.7

1.99.7 1.34.7 3.04,7 1.98.7 2.14.7

2 * 55.7 1.01.7 2.24.7 1 * 26.7 1.68.7 8.89.8 0.016 1.17.7 9.04.8 8.48.6

2.66+7

1.47.7

1.80+7

1.01+7

7.14+8

7.29.8

2.24+7

1.67+7

1.63.7

1.28-7

1.00+7

1.01.7

1.07.7

1.14+7

1.28*7

1.21.7

1.66.7

6.70+8

8.89.8

7.83+6

2.28+7

1.34+7

1.64.7

9.63+8

1.03+7

1.18+7

9.49+6

9.16.6

1.09+7

3.72+7 3.17.7 6.19,7 2.3657 4.6657

3.51.7 1.48.7 3.3657 1.69+7 2.49.7

2.47+7 1.20+7 3.22*7 2.88+7 2.0657

3.10+7 3.00.7 3.73+7

1.60.7 8.09+6 1.69+7

2.11.7 1.38.7 2.6657

4.78.7 2.73+7

1.17.7 1.1687

2.61.7 1.89.7

1.62,7

1.64.7

1.93.7

7.12.8

1.08.7

9.02.6

3.10.6

3.10+7

6.62+7

6.28.7

2. 38*7

3.38.7

1.9+.7

1.87.7

8.88+6

1.33+7

3.16+7

3.09.7

1.92.7

8.74.7

1.96-7

1.94.7

9. 72.6

2.68.7

2.46+7

2.38.7

1.46.7

2.36+7

2.06*6

1.7388

7.89+8

4.61.8

1.13+6

9.89+5

4.09.6

2.81.+

1.48+8

1.28.6

7.68.6

6.62+8

1.16.8

1.01.6

5.87.6

4.92.8

1.28.6

1.09.8

5.89.8

4.02+8

3.18.7 1.88.7 4.42+7 2.76+7 3.12+7 2.30*7 1.44.7 3.02+7 2.80.7 2.14.7

9.69.6

1.39.7

3.88+7

1.18.7

1.18.7

1.42.7

1.42+7

1.87.7

3.80.7

2.10.7

2.10.7

2.61.7

1.39+7

1.38.7

2.78.7

1.82.7.

4.76+6"

5.23+8

0.61+6

1.24.7

6.73+6

6.73+8

6.10.6

3.63.8

6.29.8

1.3a97

8.47+6 6.5086

8.36.8

3.94.0

1.78a8

1.31.7

6.08+6

4.75+6

1.10.7

1.39.7

3.2687

1.48+7

1.48.7

1.28+7

6.89.8

1.29.7

3.79+7

1.78.7

1.09.7

1.84+7

8.09,8

3.33.6

3.29+7

1.04.7

4.76+5

7.62.8

0.91+8

1.90.7

9.83*8

9.883*0

8.04.6

3.75.6

7.83.6

2.20+7

1.17.7

6.18.6

1.03+7

4.64+8

9.6896

1.82.7

6.91.6

4.76+5

9.42.8

1.24+7

2.09.7

1.21.7

1.21.7

1.17+7

7.74+6

1.29+7

2.40+7

1.6687

1.*20,7

1.41.7

8.6386

6.88+8

2.26+7

1.08.7

4.76+6

8.86.6

6.79.8

3.38.7

3.28.6

3.28+8

1.32.7

1.11.7

1.76.7

2.89.7

1.10+7

9.18.8

1.79.7

1.88+7

1.07.7

1.92.7

1.7657

4.7656

4.33+6

3.12+6

1.98.7

1.77+6

1.77.6

6.79.8

4.12+6

6.98+6

1.69+7

4.96+8

3.63+8

8.38+8

8.90.8

3.27+6

1.14.7

6.88.8

4.76+6

7.84.8

5.62.6

3.49+7

3.08.8

3.08.6

1.01.7

8.83+8

1.22-7

3.61.7

8.67+6

6.99+6

1.81.7

1. 19.7

6.42.6

2.44*7

1.17+7

4.7658

6.66+8 5.87+6

3.78+7

2.31-6 2.31.6

6.98+8

4.42+8

8.19.6

2.9807

8.14.8

4.02.6

1.19.7

7.64+8

3.2386

1.*88.7

7.62+6

4.7656

6.11-6

4.40.8

2.33.7

2.43.8

2.43+8

8.21.6

6.70.8

9.93.6

2.47+7

6.98+8

6.00.6

1.20-7

9.87+6

4.63+8

1.72.7

9.62.8

4.76+6
TABLE Al. COST TO PROVIDE THE ADDITIONAL STORAGE CAPACITY TO COMPENSATE

FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS STORAGE OPTIONS

(1983 DOLLARS) (Cont'd)

--- ----------------------------------------------------------------------------------- ----- --------------

LOW DENI BUILT NOW BUILT WHEN NEEDED(... DISCOUNT RATE)

PLANT NAME TYPE SHUTDOWH RACKS I ....-...........--- I --------------- . -.. 

.... N iEEDED DRYOEL L V I .... CASK .I ..SZLO POOL RY1 ELLI VAULT ICASK SILO

--------- ---- I----- ----- I ---- IL ----- I- --- I----- -m----- I------- -- T --------

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT S

KEWAUNEE

LACROSSE

8 LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE 1

•n MILLSTONE 2

MILLSTONE 8

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA I

A NORTH ANNA 2

A OCONEE 2

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 8

PEACHBOTTOM 2

PEACHBOTTOM 8

PERRY 1

PILGRIM 1

A POINT BEACH I

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM 1

SALEM 2

2089

2012

2626

1976

1986

2006

2015

2014

2022

2022 2828

2024

2029

2668

2821

2023 2010

2016

2625 2007 2887

2026

2618 2020

2013

2013

2014

2004

2011

2024

2025

2026

20088

2008

2626

2618

2820

2614

2664

2011

2624

2887

2008

2007

2025

2088

2026

22688

8e8

(a)

464

136

152

74

48

686

446 148

144

144

196 158

168

240

184

276

195

(a) 186

(a)

120

258

88

170

170

170

4568

440

448

192

96 (a)

120

(a) • 486

(a)

138

396 884 166

188

1.8387 1.11+7 2.49+7 1.68.7

2.46,7 1.12+7 2.49.7 1.31.7

1.79.7 9.72+6

1,84.7 7.71+8

6.21+8 1.2067 9.31.6

4.4686 8.63.6 8.27.8

2.52+7

2.87+7

1.2947 1.14.7

2.73+.

2.84.7

2.95.7 2.09+7

3.19.7

3.19.7

3.31.6

3.24.7

2.78+7

1.4127 1.40+7

1.51+7

3.9127

2.17.7

1.80.7

1.18.7

1.17.6 3.66+7

8.66.7

3.66.7

2.19.7

1.88.7

2.60.7

1.1747 1.45.7

9.7?6"

1.19.7

5.85.6

1.3086

7.67.6

1.33+7

1.3867

9.77+6

1.22.7

1.25.7

2.82.6

1.14.7

1.22.7

2.68,6

3.85+6

6.77+8

1.68.7

1.01#7

9.08+6

4.19.6 3.39+8

1.37+7

1.37+7

8.87.8

6.6568

1.84-7

4.73.6

5.08+8

2.16.7

2.67.7

1.27.7

2.66+6

2.89.7

3.17+7

S. 18.7

2.18+7

2.76+7

2.02+7

6.11+6

2.86+7 2.73+7

3.59.6

5.82.6

1.27+7

4.34+7

8.83-7

2.68.7

8.*41.6

7.1776

3.11.7

3.12,7 3.0127

1.97.7

1.98.7

2.28+7

1.02.7

1.34.7

1.49.7

1.88+7

7.66+8

6.77+6 8.78*8

1.53.7

1. 52.7

1.36.7

1.49.7

1.48.7

4.84+6

1.46.7

1.81+7

1.22.6

2.906.

8.07+6

2.74.7

2.44.7

1.1287

5.114.6

5.85*8

1.58.7

1.68.7

1.68.7

1.30.7

1.28.7

1.25.7

8.14,8

8.54*8

1.89.7

2.17#7

1.15.7

4.09+8

1.4387

2.23.7

2.24+7

1.8037

2.06.7

2.09,7

3.21.6

2.88.7

2.15.7

6.84+6

7.01.6

9.77+8

2.79+7

1.72.7

1.39.7

8.43+6

4.87.8

2.32+7

2.82.7 2.32+7

1.52.7

1.49+7

1.89,7

1.09.7

1.95+7

1.86.7

1.18.7 1.68.7

1.47.6

2.76+7

2.19+7

2.64+7

1.26.7

1.15.7 3.06+6

2.91+7

5.20.8

7.68.6

1.58+7

3.14.6

2.41+7

1.14+7

1.65+7

1.51.7 6.70+5

1.48.7

1.86+7

1.24+7

1.72+7

1.62+7

8.48.8

1.64.7

1.47.7

1.03.7

7.87+8 5.07+8

6.21+8

1.1657

1.6687

1.27,7

1.28.7

8.47.8 8.01+8 -3.60.

1.34.7

2.82.6 2.68+6

6.33+6

1.74.6

1.35.7

7.81.6

8.80+8 8.0B8+

1.79.6

7.6*85

7.0386

6.45+6

8.48.6

8.09+6

3.86.6

7.23+6

8.97*8

1.99.7

1.4807

9.18.0

8.90+6

8.27#6

3.17.7

2.68.7

2.31.7

1.26+7 1.*18.7

1.87.6 2.61+7

4.84+8

4.83+8

9.04.6 2.90*8

8.89.7

1.19.7

1.77.7 1.85.7

4.088.

1.5607

1.37.7

1.25.7 1.66.7

1.52+7

8.54+8

1.34.7

12.33.7

1.47.7

1.08.7

8.29.6

5.18.8

2.14.7

2.83.7

2.82+7

1.73.7 9.365-t

8.65.6

9.06+5

1.91.7

3.76.6

2.55+8

5.6848

2.29.8

1287.7

1.34.7

6.97.6

3.69+6

1.01+7

9.24+6

1.22.7

1.14.7

6503.8

9.3386

9.87*6

8.78*6

6.17.8

1.49.7

1.1227 7 • 84.8

7.8•68

5.27.6

2.20+7

1.96.7

1.71+7

9.20+8

8.5686

1 • 68*6

1.93.7

3.79.8

3.48+6

7.54.6

2.29.8

2.12.7

6.95+6

1.19.7

8. 608

2.82+8

1.10.7 1 •01*7

9.25.8 1.20*7

1.1567

4.96+8

2.88+6

1.1.+7

7.79.8

6.4248

2.62.7

1.77.7

2.12,7 7.81+6 1.85+7

7.69+6 4.20+8 7.87+8

9.63+8 1.25.7 2.87.7

6.06*6 7.18.6 3.89+8

9.80.6 1.89.7 1.46.7

2.14+8 3.17.6 2.49.6

2.78+7

5.20.6

2.45.7

3.33.7

8.49+7

8.18+6 86.616.

5.59.6

9.81.8

1.39.7

1.57+7

1.87.7

1.28.7

2.82.7

3.1657

3.58.7

9.78.6

9.23+8

1.18,7

1.8657

1.88.7

1.73.7

9.00+8

1.63.7

2.30+7

2.82+7

2.03+7

7.77.8

7.42.8

2.a9+7

2.19.7

8.09.8

6.3626

1.39+7

1.20+7

1.41.7

1.07.7

7.15.6 2. 80*7

2.44.7

9.45.6

8.49.8

5.4386

2.86.7

1.80÷7
TABLE Al. COST TO PROVIDE THE ADDITIONAL STORAGE CAPACITY TO COMPENSATE

FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS STORAGE OPTIONS

(1983 DOLLARS) (cont'd)

----------------- ---------------------- w------------------------------------ m------- --

..LOW . DeNl' WIBUILT NOW I BUILT WHEN NEEDED(lOS DISCOUNT RATE)

PLANT NIME TPE . I .R ------- ------- --------- -------- - --- - - ----

YEA NEEDED ~ POOL IDRYWELL VUTI CASK SIL 0 POOL J DRYWELL jVUL CASW I SILO

E SAN ONOFRE I

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH I

A SEQUOYAN 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY I

A SUtRY 2

B SUSQUEHANNA I

B SUSQUEHANNA 2

THREE MILE ISL

E TROJAN

TURKEY PT 3

E TURKEY PT 4

B VOOTLT 1

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK I

YANKEE-ROWS 1

A ZION 1

A ZION 2

TOTAL

P

P

P

P

P

P

B

P

P

P

P

P

P

P

B

B

1P

P

P

P

P

P

B

B

P

P

P

P

P

P

1999

2812

2813

2031

2821

2022

2027

2027 28828

2810

2023

2024

2012

2013

2022

2024

208

2011

2007

2027 26828

2012

2023

2024

2026

2827

2026

2001

2008

2008

270

(2)

240

(a)

388

104

104

162

144

13"

169

(a)

98"

(a)

146

98

144

(a)

262

(a)

284

312

178

240

(a)

152

76

216

(a)

3.2657 1.37*7 3.73,7 2.76+7 2.63.7 2.91+7 1.65.7 3.86+7 3.10+7 2.46.7

3.00.07

5.38.7

2.4807

1.42+7

1.42.7

6.86-6

3.68+7

3.27+7

1.68.7

4.07+7

2.18-7

1.488-7

1.66+7

6.22#7

1.42.7

1.6657

3.63.7

6.82.7

3.7.*7

2.0807

3.04.7

1.31.7

2.37.7

9.11+8

6.66+6 6 • 55.8

7.07+8

1 . 12.7

1.12.7

6.19.0

1.88+7

4.78.6

88.61+8

9.33.8

2. i0.7

16.80.0

8.24.6

1.41.7

2.44+7

1.29.7

2.61+8 1.25.7

3.00.7

6.8+67

2.02.7

1*38.7

1.36.7

1.83.7

2.53+7

2.68+7

1.01.7

4.06.7

9.19+6

1.38+7

1.99.7

6.19.7

1. 38.7

1.9657

3.19.7

6.62.7

2.92.7

4.84.8

4.02.7

1.440.7

3.39+7

1.04+7

9.79+0

9.69+8

2.16+7

1.23.7

1.43.7

6.56+6

2.49.7

4.*88.8

9.34.0

1.46+7

3.02*7

8.86*6

9.97.6

1.83.7

3.47*7

1.67+7

1.28.6

2.38+7

2.21.7

3.49.7

1.61+7

1.24.7

1.22.7

9.*356

1.93+7

1.97+7

1.06.7

2.73.7

1.07.7

1.24+7

1.68-7

S. 26#7

1.26.7

1.38.7

2.37&7

3.64.7

2.18.7

7.4.6+

2.83.7

9.67,6

3.80.7

8.01.8

1.71+6

1.060.

2.66.8

2.06+7

1.07.7

4.79+8

1.93.7

1.10.7

7.66+8

1.12.7

1.40.7

1.21.7 1.07.7

I.38.7

2.61+7

1.13.7

2.04.7

2.84*7

6.36+6

2.21+7

4.2386

1.06.8

1.00.8

2.32+8

9.6086

6.13.6

2.21.6

1.16+7

4.11+8

3.62+6

6.76÷88

8.01+6

6.41+8

8.46+8

7.18.0

1.62.7

6.6.86

8.04.6

1.76.7

1.08.7

3.98.7

7.79*6

1.60+8

1.408+

7.08.6

1.88,7

9.65.8

3.42,6

2.44.7

8.7".8

8.20+8

1.56*7

1.73.7

9.64.6

1.32.7

1.40,7

3.29+7

1.08+7

1.02.7

3.48+7

7.81.8

4.16.7

6.87.0

1.21+8

1 . 14.6

6.16+8

1.37.7

7.17.6

2.49+0

2.06+7

4.43.6

4.41+8

7.78+.

1.60+7

6.68*6

9.856.

1.03+7

2.81.7

7.98.6

6.00+6

2.84.7

7.74.6 2.70+7

6.87.6

1.29.8

1.22.8

4.36.8

1.39+7

7.28.6

2.90+.

1.67.7

4.95*8

8.16.6

1.18.7

7.68.8

9.4608

1.03.7

2.24.7

7.93.8

8.08.8

2.40.7

------------------------------------------------------------------ ~-e

2.34.9 9.88.8 2.24.9 1.30.9 1.68.9 1.38.9 7.40+8 1.38.9 1.13.9 1.01+9

A. INDICATES COMMON POOL SHARED BY TWO REACTORS t CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

B INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

E INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULLCORE RESERVE

(a) INCLUDED IN UNIT I
TABLE A2. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - POOL STORAGE OPTION(19983 DOLLARS).

PLANT HAVE TYPE LOW RACKS DEN -------------- BEFORE CONVERSION RERACKING -- AFTER

iNEEDED OX G 11% Ie'x I I -I - - - - I - -- - --- I- - - - -I- - - -

CONVERSION I INCREMMTAL COST 

5A I if" I -ex -' 5% 1 0

A

A

B

A

B"

A

A

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK 1

BRAIDWOOD 1

BRAIDWOOD 2

BROWNS FERRY 1

BROWNS FERRY 2

BROWNS FERRY 8

BRUNSWICK 1

BRUNSWICK 2

BYRON I

BYRON 2

CALLAWAY 1

CALVERT CLF 1

CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

COMANCHE PK 1

COMANCHE PK 2

COOK 1

COOK 2

COOPER SI

CRYSTAL RVR 8

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

OINNA

GRAND GULF 1

HADDAM NECK

HARRIS I

136

188

140 188

188

46

262

(a)

684

(a)

468

878

378

284

(a)

18l

192

(1)

144 144

344 198

(,)

256

(a)

232

72

120

95

85

318 818

258

552

138

136

980

240

84

588

104

104

7.27*7

7.60.7

9.09+7

8.40.7 1.11-8

1.11.6

5.91.7

1.99.8

8.27.7

8.68,7

9.48.7

9.0.+7

1.99.8

9.83.7

1.19.8

91.96.0

9.93+*7

1.093.8

7.92.7

7.04.7

7.4.+7

1.37+8

7.72.7

7.7247

6.96,0

8.82.7 6.38+*7

7.04.7

1.43+8

6.91.7

5.4687

8.75.7

7.04*7 0.00+0

5.91.7

1.28.28

8.82.7 0.0&08

0.080+1

3.49.7 3.07*7

3.92.7

2.00.7

2.55-7

2.32.7

3.18-.7

7.81,7

2.94.7

5.4a.7

5.02.7

8. 88*7

2.71+7

8.04*7

0.00+0

2.69+7

1.87.7

3.48.7

3.25.7

2.290*7

8.07+7

1.73.7

.73.+7

3.03+*7

2.3.*7

2.95.7

5.24,7

1.88.7

1.59.7 8.69.7

3.78.7

2.49+7

4.61.7

8.18.7

1.77.7

1.34.7

1.88-7

5.85.8

8.72.8 B.65+68

1.77.7

8.51.7

1.18,.7

1.19.7

8.48+7

3.06+7

4.24.*7

8.68,8

3.44.7

0.00+0

0.00+00

7.73+8

3.83+8

1.61.7

1.69+7

7.41+6

8.02.7

4.82.6

4.82+8

1.42.7

1.14.7

1.81.7

2.29.7

6.19+8

4.88.6

1.71.7

2.12+7

1.18+7

1.92.7

1. 57.7

5.42+5

5.54.+

8.21,5

8.47+5

7.84.5

7.84.6 8.68.*4

1.0936

1 32.+8

9.02- 6

7.69.5

7.52+5

1.* 7.68

7.13.6

7. 16.5

8.42+5

5.94.5

8.9685

8.78+5

1 . 12.6

4.9+.5

3.84*5

5.48+5

3.89+5

3.89.5

a. 12.5

6.12.5

6.3056

1.08.6 8.13+5

8. 13.5

7.3&.5

8 • 19.5

2.82+5

1.04.8

4.19.5

4.75+5

9.098.*7 9.83.*7

1.25#8 1.20+8

1.5608

1.5098

6.59.97 2.35+8

1.01.8

1.1098

1.09.8

1.07.8

2.35.8

1.31.8

1.438.

5.46*7

6.23.7

1.22.8

1.35.8

1.16.28

7.95,7

8.40.7

1.768*

8.e8+7

8.88.7

8.18.7

7.72.7 8.88.7

1.*89,.8

7.95,7

1.12.8

8.40.7

7.27.7

1.49.8

8.40+7

5.7087

5'72+7 7.67.7

3. 88*7 4.79*7

4.33+7

8.98.7

1.11.8

4.18-7

4.982+7

8.89.7

8.61,7

1.17,8

5.01.7

8.28.7

8.•39.6

7.35+6

3.92.7

2.98.7

8.19.7

4.24.7

3.28.7

9.78.7 2.37+7

2.37.7

4.52,7

3.97.7 4.93+*7

0.5+.7

3.49.7

3.07.7

5.8097

6.67.7

3.83,7

8.80.7

5.88.7

4.03.7

3.74.7

4.89.7

1.49.7

1.83.7

1.61*7

2.4087 8.69#*7

1.87.7

2.38*7

4.59.7

4.53+*7

7.28+7

2.29.7

5.4487

1.41+8

1.14.6

1.49+7

7.46.8

2.43.7 2.•39+7

8.35+7

7.21.6

7.21.6

2.8.#7

2.19.7

399.7

5.07+7

1.65.7

1.34.7

3.42.7

3.98.7

2.14.7

3.7387

3.27,7

1.88.7

2.39+7

8.48.7

3.84.7

4.02.7

4.92*7

.87.86

3.74+7

1.99.7

2.55.7

1.47.7

3.72+7

3.61.7

2.47.7

6.$2.7

5.28.7

2.38.7

3.88+7

3.18.7

9.59.6

1.39.7

3.88.7

1.18.7

1.18.7

1.42.7

1.42.7

1.87+7 3.89+7

2.1067

2.10.7

2.61+7

1.39.7

1.38.7

2.78+7

1.82.7

2.34.7

2.71.7

3.21.7

1.95.7

2.3067

2.99.7

8.08+6

8.58.7

1.85.7

1.87.7

1.81.7

1.67.7

8.4867

2.37.7

2.31-.7

8.79+8

7.94.8

1.46.7

1.17.7

2.82.7

1.04.7

1.0997

8.78,7

8.79.6

8.79M8

1.65+.7

1.40+7

2.03.*7

8.42.7

1.76.7

1.54.7

2.18.7

1.84.7

1.88+7

2.39.7

1.92.7

2.32.7

2.45.7

2.87.7

1.02.*7

1.28.7

1.03.7

7.28+6

3.17.7

8.09+8

1.29+7

1.21.7

1.65.7

8. 1#7

1. S0+7

2.11-7

2.05#6 1.7376

7.89*8

4.51.6

2.89.7

8.8686

8.79+6

3.88.7

3.28.6

3.28,6

1.82.7

1.11.7

1.75.7

2.89.7

1.16.7

9.18.6

1.79.7

1.89.7

1.07.7

1.92.7

1.75.7
TABLE A2. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - POOL STORAGE OPTION(1983 DOLLARS)(cont*d)

I LOW DEN BEFORE CONVERSIO I AFTER CONVERSION INCREMENTAL COST

PLANT NAME TYPE I RACKS ---I -- -- -- RERACKINGI- m --- !------ .... I .... w --- IOE. NEEDED ED... I ...... . .6. lo.x ox a lox

B HATCH I

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE 1

c,• MILLSTONE 2

MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE I

A OCONEE 2

OCONEE a

OYSTER CRi I

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM a

PERRY 1

PILGRIM I

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM 1

SALEM 2

688

(a)

484

1t8

162

74

48

889

(a)

448

440

148

144

144

198

168

168

240

184

276

196

(a)

16

(a)

120

268

68

179

170

170

465

440

448

19298 (a)

120 (a)

4"8 (,,)

138

384 189

188

7.27*7 2.98+7 1.28.7 1.14+6 8.99,7 4.24+7 2.13+7 1.83.7 1.40.7

9.78.7 9.22+6 1.21.8 3.89+7 1.40+7 2.48.7 1.40.7

9.0.0"

9.0.00

7.27.7

7.04,7

7.96+7

8.82*7

2.19.8

1.3658

1.41.8

7.27.7

8.6657

8.88+7

1.02+8

8.83+7 6.69+7

6.23+7

8.69+7

7.96+7

1.12.8

2.49.7 7.19+4

8.83+7

2.81.7

3.17.7

4.07.7

1.69.8

6.38.7

4.72*7

3.49+7 2.60+7

2.43.7

8.37+7

3.84+7

1.23,7

1.85*7

3.27*7

1.78.7

4.21.7

2.14.7

8.14.8

1.37,7 2.62+7

8.69+7

2.66+7

1.94+7 1.7757

8.11.6

7.48+8

4.44.7

1.69+7

2.62+6

8.91.8

1.77.7

4. *86

1.78-7

6.01+6

8.77.6

2.84.6

8.6884

1.2748

8.93*6

8.73+6

6.26.6

8.42.6

6.42+6

4.06+6

8.13+6

7.4656

4.89.6

3.80+6

6.71.6

8.91-6

8.73+7

9.84+7

9.31.7 7.96+7

2.16+8

1.83+8

1.7078 9.31+7

1.17+8

1.29.8 1.06+8

1. 18.8

9.28+7 8.69+7

7.96+7

9.40+7

1.6-98

6.71.7

4.69,7

4.68.7 6.68+7

1.98,8

8.23.7

7.28.7 6.61#7

4.51+7

4.34,7

6.48*7

8.80+7

2.49*7

2.97.7

4.91.7

2.4097

7.28.7

4.63.7

2.41.7

2.62+7

4.09+7

0.82+7

6.22+7

4.04.7

4.26+7

2.01+7

1.84.7

4.43+7

4.64+7

8.98+8

1.46.7

3.23.7

8.93+8

4.98.7

1. 62-7

2.87+7

1.39.7

1.14+7

2.73.6

2.84.7

2.95+7

2.09+7

3.19.7

3.19.7

9.31+8

3.24+7

2.76.7

1.41.7

1.40.7

1.61.7

3.91.7

1.94.7 2.36+7

1.44.7 2.60-7 2.70*6

2.96.7

2.8657

2.67*7

2.07*7

1.97.7 1.30+8

3.22.7

1.24.7

1.16.7

1.87+7

8.94.6

3.18.7

9.72.8

7.71+.

1.96#7

1.68.7

1.18+7 1.68-7

1.47.8

2.76.7

2.19"7

2.64.7

1.28+7

1.16-7

3.0655

2.91+7

6.2068

7.68.8

1.68+7

3.14.8

2.41.7

1.14.7

1.66.7

1.61.7

6.70+6

1.48.7

1.3657

1.24.7

1.72.7

1.62+7

8.48+8

1.64-7

1.47.7

2.07.7

3.89+8

2.03+7

7.77.8

7.42+.

2.6897

2.19+7

1.31.8 7.47+7 4.84.7 8.91.6 1.6128 8.9097 6.90+7 2.17+1 1.61.7

1.64.8

8.82*7

9.78*7

9.36*7

9.38.7

9.38.7

7.64*7

7.64.7

8.98+7

7.96*7 7.27+7

6.68*7

3.6887

6.97.7

2.64*7

2.61+7

2.39+7

3.26.7

3.2657

2.13.7

4.24.7

3.68+7

3.28.7

2.09.7 4.08#7

4.98+7

7.89.8

8.91.8

1.6597

6.6+84

2.43.7

1.94.7

6.42.6

6.11.6 2.70+6

6.74+6

8.74+6

0.74+6

9.02.5

8.73.6

8.93.6

3.97+6

3.64.6

1.22.8

7.96*7

9.86+7

1.29.8

1.29.8

1.29.8

9.14.7

8.83#7

1.14.8

9.68.7

8.88.7

7.10.7 6.18+7

8.01.7

4.93+7

4.70.7

4.47.7

6.22.7

6.06+7

3.33#7

6.78.7

6.21.7

4.78*7

3.64.7

4.11.7

2.2657

2.06+7

1.87.7

3.22+7

3.12.7

1.13.7

4.93.7

3.38+7

1.8+.7

1.18.7

1.17.8

2.68*97 2.19.7

2.46,7 1.17.7

1.45.7

1.8657

1.63.7

8.79+6

2.*387

2.28+7

2. 16#7

2.0687

1.8097

1.29,7

1.68.7

1.69.7

8.68.7 4.31.7 2.48.7

5.69.7 1.70+7 8.68.6

4.31.6 1.62.8 8.44+7 4.48+7 2.12+7 2.17.7

9.21+5 6.6887 2.19.7 8.8658 7.89+8 5.78+8

6.48+7

8.40+7 9.16.7

9.49.7

9.86+7

1.92.7 6.08+7

2.3657

3.91+7

3.38*7

7.12.8

3.27.7

8.85+6

1.79,7

1.28.7

8.19.6

4.98.6

7.61+6

7.11.6

7.4656

8. 18.7

8.88.7 1.16-8

1.27,8

1.33.8

4.62+7

6.73.7

3.65,7

8. 92.7

8.19.7

2.68.7

4.01+7

1.36.7

4.41.7

3.40+7

2.7187 6.2088

2.45+7

3.33+7

3.49,7

2.66.7

7.1.80

1.3887 3.68.7

2.90.7
TABLE A2. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - POOL STORAGE OPTION(1983 DOLLARS)(cont•d)

--- - --- --- --- -- --- -- ----------- - --- - ------------------------------ - ---------- m - -----

PLANT NAIME

TYPE RACKS---------

-OI DEN.]- I BEF

CONVERSION AFTER CONVERSION I INCREMENTAL COST

-IFwr(ine---------------------IKRCAMI----------------

kex I 5% ---- 1 ox Iex I 5% '1 lox

m•

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 8

SEABROOK 1

A SEQUOYAH 1

A SEqUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSQUEHANNA 1

1 SUSQUIEHANNA 2

cin THREE MILE ISL

"-J TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOCTLE 1

B VOCTLE 2

VT YANKEE I

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

P

P

P

P

P

P

B

P

P

P

P

P

P

P

ip

P

P

P

P

P

B

P

P

P

P

276

128

240

(a)

s88

104

164

162

144

136

159

(a)

896

(a)

148

96

144

(a)

252

(a)

264

312

178

240

(a)

152

78

218

(.)

8.77.7 3.7?.7 2.0897

1 • 11-8

1.6688

6.46.7

5.46+7

1.02.8

9.74.7

8.18.7

4.65.7

1.49.8

5.0067

6.14.7 6.68.7

1.33+8

7.59*7

1.23.8

9.2647 1.610+8

8.4+.7

5.66.7

2.54.?

6.66.?

2.860+7

7.81.6

7.25*6

6.37.7 3.20+7

2.08+7

1.11+7

6.18+7

1.82+7 2.16+7

2.19.7

8.47.7

3.67+7

4.46+7

2.6507

4.82+7

2.11+7

2.28.7

4.23.7

8.85+6

3.2647

7.79.6

1.17+6

1.08.6

4.44+7

1.26,7

6.84+6

2.87*6

2.0867

5.93+6 6.84.*6 7.64.86

8.85.8

1.065+7

1.34+7

1.89+7

7.61.8

1.8067

5.88+8

1.68.7

2.23+7

9.54+6

6.74+6

1.11.08

7.38.8

-6.51.6

6.46+6

5.82.6

6.26.5 6.65.5

7.63.5

1.31.86

6.54.5

4.37,5

6.3996

1.11.6

6.39.5

6.986.

1.68.*6

6.77.5

1.86.5

9.54,5

9.92+7 6.8657 4.90+7 3.25+7 3.25.7

1.41#8

2.09+8

1.23+8

8.82.7

6.82.7

1.108+

1.32.8

1.14.8

8.14+7

1.88+8

7.04.7

7.60.7

7.27.7

1.84+8

8.86.7

1.39.8

1.27+8

2.065+8

1.20+8

7.64*7

1.16.8

4.25.7

1.09+8

3.95.7

1.20#7

1.14.7

6.78.7

5.91.7

3.94.7

2.01+7

7.89+7

3.25+7

3.21+7

3.86+7

6.02+7

4.48+7

6.8047

4.88.7

8.5647

4.16.7

4.8.+7

7.23+7

1.88.7

8.89+?

1.61.7

2.12.8

4.66.7

3.21.7

1.8067

6.98.8

3.8067

1 • 69+7

1.48.7

1 . 94+7

2.34.7

2.49*?

2.89.?

2.06.7

4.31+7

1.66+7

3.1.+?

4.97+7

S.M*7

6.38.7

2.46+7

1.42.7

1.42+7

8.85.8

3.53.7

3.27+7

1.8867

4.67+7

2.1047

1.40+7

1.8567

5.22+7

1.42.7

1.85+7

3.63#7

5.62*7

3.70+7

2.0667

3.64+7

1.77+7

4.48*7

1.42.7

4.94-8

4.73.6

4.85.6

2.78+7

1.93+7

9.6886

2.84.7

1.70.7

1.16+7 1.64.7

2.88.7

1.47.7

1.46.?

2.25*7

3.83.7

2.066?

2.32+7

3.1-,7

2.91+7

9.87.6

8.01.6 1.71.,8

1.6"

2.05+6

2.68.7

1.7.+7

4.79.8

1.93.7

1.10-7

7.65+6

1.12.7

1.46.7

1.21+7 1.67.7

1.38.7

2.61.7

1.13.7

2.04+7

2.84+7

--------------------------------- m -------------- m-m-m ---- m --- M ------ m --------------------- m8.51.9 3.27.9 1.52+9 8.5•67 16.78+9 5.01+9 2.84+9 2.34+9 1.8649 1.38.9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORSs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFERt CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1
TABLE A2.. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - POOL OPTION

(1983 DOLLARS)

---------------------------------------------------------------------------------- m ------------- m ----------- -m ------

ADD. YEAR

SIHUTDOVI STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADD'L TIME

(ASSEM- STOR. (MON.) ------- ------ --------- BLIES) NEEDED ---... ..-

COST -I- S

CONSTRUCTION I 0s - --------- -- - ---- ----- - I TOTAL

,;T I 5fix l 8 I ox I 6% 11 x I I a I11o

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK 1

A BRAIDWOOD 1

A BRAIDWOOD 2

B. BROWHS FERRY 1

B BROWNS FERRY 2

BROWIS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

A BYRON 1

A BYRON 2 cn CALLAWAY 1

cO a CALVERT CLF 1

B CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

B COMANCHE PK 1

B COMANCHE PK 2

A COOK 1

A COOK 2

COOPER STN

CRYSTAL RVR 3

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 8

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND GULF 1

HADDAM NECK

HARRIS I

208

2012

2016

2028 2628

20d

201

2286

2027

2814

2014

2017 2618

2810

2024

2286

2024

2014

2016

2026

2028

2027

2030

2030

.2009

200

2008

2018

2017

2025

2025

1984

2068

2008

2010

2026

2012

2012

2016

2008

2007

2800

2022

207

2028

377

665 883

858

1900 1000

"827

(a)

3228

241

2401

2281

3827

(a)

1129

2213

(a)

0

a

2672

2067

(a) 1241

(a)

1238

432

2490

517

517

0

1016

893

g98

5356

298

140

2248

413

219

4392

319

0

1998

1999

1998

2009

209

2011

1985

1900

2082

1998

1991

1994

200S

1992

2025

2826

2088

2016

1998

1997

200 1995

2011

2011

1os8

2000

1998

1997

2008

20"

1997

1994

20"

1998

1997

2028

68

68

so68

53

63

68

72

59

67

67

68

72

6762

8

0

57

64

68

68

58

584

68

68

so

58

64

5858

58

58

68

82

58so

4.66*7

4.6657

4.65.7

4.6657

5.60*7 6.00.7 6.69#7

4.6557

8.68.7

5.11.7

4.74,7

4.72*7

4.62+7

8.6687

4.90+7 6.69+7

0.00.0

0.w+0

4.82+7 6.64+7

6.08+1

4.55,7

4.6657

8.70.7 4.66+7 4.56+7

4.66+7 4.66+7

4.6657

6.93,7

4.6657

4.81.7

4.66+7

4.66+7

6.48.7

4.6657

0.00+0

2.42.7

2.09.7

2.42.7

1 . 28,7

1.67.7

1.43.7

2.64.7 4.64+7

2.02.7

1.97.7 3.98+7

8.13,7

5.00+7

1.60+7

3.60.7

0.00.0

6.0670

1.57,7

1.67+7

1.23.7

2.44+7

2. N8.7

1.66.7

3.73*7 1 • 16.7

1 . 16.7

2.19.7 1 • 99.7

2.09+7

3.•0.7

1.48.7

1 . 3657

2.8387

2.6687

1.99.7

2.88.7

2.3+7

0.900

1.32+7

9.91.8

1.32.7

8.82+6

4 . 70+8 3.88+6

1.45.7

2.48.7

8.38*0

8.63+8

2.42.7

2.16,7

6.02.6

2.37+7

0.+00.

9.0".

6.38+8

2.77.6

1.21+7

1 * 20,7

6.6"•

2.18+7

3.18.8

3.18+8

1.09+7

9.01.6

9.91+6

1.68.7

6.09.0

4.20.8

1.21+7

1.68.7

9.01.6

1.31.7

1.20+7

0.0+6

2.72.7

2.96.7

4.6857

8.8657

6.47+7

6.47*7

1.38.7

1.18+8

3.16.7

3.82*7

4.74,7

4.3887

1.13.8

4.73.7

0.32.7

0.60.0

0.00.6

6.11.7

4.49,7

2.88.7

2.49+7

2.49.7

7.62*7

8.17.7

8.17.7

2.27+7

1.01+7

2.49+7

8.36.7

1.38.7

9.87.8

4.14.7

2.49.7

1.38÷7

8. 79*7

2.27.7

G.0+6

9.7658

7.19.8

9.79-8

8.0886

8.41.8

3.07+7

9.24.8

1.07.7

2.10*7

1 . 89+7

3.38.7

1.03-7

2.44.7

0.00.0

1.02.7

6.44*8

1.04.7

9.61.8

6.44.8

2.34.7

6.72*8

6.72+4

8.42+8

8.39+8

8.62*8

2.24.7

3.76+8

2.37+8

1.38,7

6.92+8 1.10.7

8.84.8

0.00.0

4.47.6 8.6+8*

6.69+8

1.63.8

2.02.8 2.82-6 1.67.8

8.1658

1.03*7

2 .93.8

3.38.6

1.94.7

1.*24,7

2.58+6

1.07+7

0.080.

2.38.8

4.04.8

3.88+8

1.81.8

8.92.8

1.18-8 I • 16.8

1 • 16.8

3.*33.6

2.4398

3.20+6

7.4808

8.• 1+6 68• 3,5

4.97+8

6.16.8

1.95.8

8.08+8

3.87.8

0.0-.0

7.27.7

7.5W+7

9.08.7

8.40*7

1.11.8

1 . 11.8

6.91.7

1.99+8

0.00+0

8.27+7

0.60.0

8.68.7

9.48.7

0.00.0

9.00+7

0.00.0

1.99•8

0.+00. 9.63,7

1419.8 1.19-8

0.0".

0.00.0

0.00#0

9.93.7

1.+8.8

0.00.0

7.92*7

0.00+0

7.04,7

7.94.7

1.37+8

7.72*7

7.72.7

0.00.0

6.82.7

8.36.7

7.04*7

1.43+8

6.91.7

6.48*7

8.76+7

7.84+7

0."00,

6.91+7

1 . 23+8

8.02+

0.00+0

3.49.7 3.07.7

8.92-7

2.00,7

2.66.7

2.32.7

3.18.7

7.61.7

2.94.7

3.04*7

6.48.7

6.02.7

*8.88.7

2.71.7

6.84.7

0.00+.

0.00.0

2.69.7

1.87.7

3.48+7

3.26+7

2.20*7

6.07*7

1.73.7

1.73#7

3.03.7

2.83*7

2.9567

6.24+7

1.88-7

1.69+7

3.69*7

8.78+7

2.49.7

4.51.7

8.18.7

1.77,7

1.34.7

1.88.7

6.5*38

6.72.8

6.66+8

1.77+7

3.61*7

1.13,7

1.19-7

3.48.7

3.0+.7

4.24.7

8.68+8

3.44.7

0.00.0

0.0"

7.73+8

3.83+8

1.6197

7.41-8

8.02.7

4.32.8

4.32+8

1.42.7

1.14+7

1.31.7

2.29.7

8.19+6

4.8+8

1.71.7

2.12.7

1.10+7

1.92.7

1.67.7
TABLE Aft. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - POOL OPTION

(1983 DOLLARS) (con'd)

e----------------------------------------------- -- ------ ------ m - ------- - m m--w ------ ----------

ADD. YEAR

SHUTDOWN STORAGE WHEN I

PLANT NAME YEAR REQ'D ADD'L I

(ASSEM- STOR.

BLIES) NEEDED -- - - - -- -e--------------

CONS. I

TIME

(MON.-)I

COST *- - --- -ltli - -- ell I---------ee e---- q--eee-ee~

CONSTRUCTION .% 10... OSM I TOTAL n •ilillil I I liiliM ...... iilii ........

-I 5%-,- I lox -I -.- -,- I lo-. x

ww

e---------~e~eeeee

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT I

INDIAN PT 2

INDIAN PT 8

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

UCGUIRE 1

MCOUIRE 2

MILLSTONE 1

t MILLSTONE 2

MILLSTONE 8

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA I

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHOOTTOM 8

PERRY 1

PILGRIM 1

A POINT BEACH I

A POINT BEACH 2

A PRAIRIE ISL I

A PRAIRIE ISL 2

B QUAD CITIES 2

B QUAD CITIES 2

RANCHO SECO I

ROBINSON 2

RYR BEND 1

SALEM 1

SALEM 2

2022

2028

1978

2008

2014

2002

2022

2023

2024

2029

2008

2021

2028

2010

2015

2025

2007

2005

2028

2018

2020

2013

2018

2014

2004

2611

2024

2025

2026

2008

2008

2028

2068

2067

2009

2008

2608

2007

2007

2008

2007

2025

2618

2020

2874 (,)

2820

0

0

493

588

679

205

9824

(a)

4098

4236

832

g96

989

2480

828

641

355

884

1971

1868

(m)

21021

912

885

1117

1121

1121

1812

1689

2648

1512

849

(a)

1142

(a)

508

(a)

228

2452

1007

1163

2000

2007

1994

1999

1992

1990

1995

1998

1998

2005

200$

1997

2018

2004

1998

2011

1999

1999

1991

1994 1988

2006

2008

2007

1997

1997

2009

1993

1995

1993

2005

2e64

1990

2007

1997

2001

B5

58

88

58

56

58

76

61

81

58

57

57

57

58

56

58

58

68

84

57

56

58

57

57

57

58

58

57

58

58

58

58

58

56

57

57

58

4.99.7 2.17,? 9.88.6

4.9687 1.54.7 5.04+8

2.29#7 7.88+6

4.80+7 9.40+8

4.654?

4.55.7

4.*55.7?

4.* 55.7

9.02+7

5.89.7

5.42*7

4.56*7

4.74*7

4.77*?

4.72.7

4.55,7 4.55,7 4.65+7

4.55.7

4.65+7

4.56.7

5.87.7

2.86.?

1.68.7

2.09.7

2.94+7

8.41.7

83.09+7

2.81+7

2.42+7

1.82.7

1.55.7

3.74.7

2.8307

9. 10.

1.83+7

2.42+7

1.18.7

2.80+7

1.60.7

8.16.8

9.91.6 1.93*7

4.63+7

1.72*7 1.38.7

1.32.7

5.82+8

5.838. 3.10O+7

1.20+7

1.98+6

8.15.8

1.82.7

3.18.8

1.23.7

2.72+7

2.49+7

3.40+7

2.27.7

1.29+8

8.11.7

8.72+7

2.72+7

3.81.7

4.09+7

5.46.7

4.08+7

2.04.7

8.80+8

2.04#7

3.46.7

5.51.7

1.17.7

0.78+8

1.08+7

1. 18.7

4.53,?

2.88,7 2.11.7

1.07.7

8.82+6

8.82+8

2.8687

1.34.7

3.22+6

2.22.8

8.54+6

8.00.8

1.81+7

2.90.8 7.27+7

0.0&0.

2.16+8 9.76.7

8.00+0

0.0m.

5.41+. 7.27+7

1.99+8 7.04+7

8.75+6 7.95.7

5.91+8 8.82.7

1.97.7 2.19.8

0.0&0

8.35.6 1.35.8

8.38+8 1.41.8

4.47+6 7.27.7

2.29+8 8.55.7

2.156+ 8. 6?7

1.44+7 1.02+8

4.89+8 8.83.7

5.62+5 6.69+7

7.62.5 5.23+7

8.78+8 8.59+7

1.20+8 7.95.7

5.26+8 1.12.8

0.00*0

1.51+7 1.31+8

0.00+0

1.01.7 1.04+8

4.88+6 8.82.7

1.25.7 9.76+7

2.48+8 9.8+,7

2.25+6 9.88.7

2.05+6 9.38.7

3.88+8 7.04+7

3.88+8 7.04+7

1.84.8 8.98+7

8.85+8 7.95.7

4.92+8 7.27.7

0.00.0

8.77.8 8.0887

0.00+@

4.83+6 6.00+7

0.*0+0

9.71+5 6.48+7

9.38.8 8.40+7

2.00+8 9.10+7

5.34+8 9.40+7

3.84+8 9.85.7

2.98+7

2.49#7

.88.37

2.31*7

8.17.7

4.07.7

1.09.8

5.36.*7

4.72.7

3.49+7

2.50+7

2.43.7 8.87.7

8.84.7

1.23.7 1.85.7

3.27.7

1.7.+7

4.21.7

7.47+7

5.56.? 3.6087

5.9707

2.84.7

2.51.7

2.39+7

3.25+7

8.25+7

2.13+7

4.24+7

3.66.7

4.81.7

1.70+7

1.92.7

5.0687

2.35.7

8.91.7

3.3867

1.28+7

7.19+8

2.14+7

8.14.6

1.87.7 2.92#7

8.60+7

2.58+7

1.94.7

1.77.7

8.11.8

7.48.8

4.44.7

1.69+7

2.52+8

8.91+8

1.76+7

4.88.8

1.76+7

4.84.7

8.26.7

2.09+7

4.08+7

8.38+68

7.80.8

8.91.8

1.*59+7

1.59.7

5.68+6

2.48+7

1.94.7

2.46.7

8.0+88

7.12+6

8.27+7

8.85+8

1.79+7

1.28+7

5.91.7 4.41.7 8.3837 7.14.7 3.08.7

4.89.7

4. 557

4.55+7

4.78.?

4.79,7

4.79.7

4.55+7

4.55,7

4.82+7

4.56+7

4.55+7

3.27#7

2.8847

3.57+7

1.84.7

1.6.+7

1.48+7 2.30+7

2.8307

1.36.7

2.4.+7 2.54+7

2.29+7 1.00+7

2.83.7

5.88.6

.*85+8

4.86+8

1.20+7

1.20.7

4.04+8

1.7867

1.46+7

5.01.7

2.27.7

5.21.7

4.58+7

4.69,7

4.59+7

2.49+7

2.49.7

4.14.7

3.40.7

2.72.7

2.23+7

1.02+7

2.40.7

9.98.6

9.50+6

9.05+8

9.51+6

9.51+6

7.72+6

1.44+7

1.12+7

4.62+7 2.84.7

4.55+7 1.58+7

1.78+7 8.46+7 1.47.7

5.06+8 4.58+6 1.44+6

4.55+?

4.77.7

4.80.7

5.06+7

1.63+7

3.24+7

1.48+7

2.43+7

2.08.7

8.15+8

2.34+7

4.865+ 1.28+7

8.99+8

9.07+a

8.99+7

4.33+7

4.80+7

4.86+7

2.88+6

1.82.7

8.71+6

1.48+7

1.28+7
- i..,, ',,..

TABLE A2*. COST FOR ADDITIONAL SPENT FUEL. STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - POOL OPTION

(1983 DOLLARS) (cont'd)

---------------------------------------------------------------------------------------------------------------------- ADD. YEAR

SHUTDOWN STORAGE WNHE I CONS.

PLANT NAME YEAR REQ'D ADD'L I TIME

(ASSEM- STOR. I (MON.)

BLIES) NEEDED

-----------------.---------------- ------------- COST

CONSTRUCTION I 08M TOTAL -- - - -- - -- - -- -- - - -- - - - - - -i-- -m- -- - - - -

1 56 1 le~i I oi I 6x I I8 ; I 01G I5 IlOS

------------ ---------------

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH 1

A SEQUOYAN 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSQUEHANNA 1

B SUSQUEHANNA 2

THREE MILE ISL

oý TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOGTLE 1

B VOGTLE 2

VT YANKEE 2

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2012

2013

2031

2021

2022

2027

2027

2028

2010

2023

2824

2012

2018

2022

2024

1 2•08

2011

2007

2007

2027

2028

2012

2023

2024

2026

2027

2026

2001

2"08

2008

2882

1261

2880

(a) 2835

268

268

1182

1126

761

97

(a)

7288

75

373

884

(a)

2495

(a)

1088

4018

1143

2891

36

1296

(a)

1996 63 6.62.7 3.13.7 1.79+7 1.1657 6.70.6 2.92+6

2008

1996

28"0

2023

2024 1987

2001

2012

20"

200

204

2"02

206

1999

1998

2006

201

2"8

1999

1995

s9

68

6756

56

6756

56

68

89

6866

68

67

s6

81

67

68

68

68

69

6.5097

7.04*7

4.86.7 4.65+7

4.66+7

4.72+7

4.84+7

4.66+7

4.66+7

7.41+7

4.56*7

4.66+7

4.66+7

8.81+7

4.65+7 4.365..7

4.62471

7.66+7

4.66+7

4.66+7

6.12.7

1.69+7

3.92+7

1.68+7 1.47*5

8.18+8

3.74+7

1.93.7

1.3657

1.11.7

8.23.7

1.48.7

1.63?7

1.88.7

2.16+7

2.09.7 .68-7

2.93.7

1.36.7

2.89.7

2.8657

4.760#

2.24.7

6.42.6

1.01+8

9.16+6

3.600.7

8.36-7 4 0.866 4.2988

2.87.6

1.47.7

6.09.8

6.16+6

7.46+8

7.39+6

9.91.6

1.28.7 6.28+6

1.27.7

4.20+8

9.91+6

1.6897

6.03.7

8.66.7

6.1657

9.07.6

9.07+8

6.4657

6.10,7

3.8637

0.0800

7.47+7

4.6536

1.69.7

1.13+7

6.65.7

2.96+7

4.88+7

7.91.7

3.86+7

4.63.6

3.43#7

1.04.7

2.63.7

1.02.7

1.14+6

1.09.6

2.63.7

1.27.7 7.26+8

0.00.0

1.95.7

1.37+6

4.71.8

3.88.8

1.32.7

9.76+6

1.88.7

9.25.6

1.80+7

7.66*8

1.93.8

1.3887

2.16+6

9.69.6

2.37.8

1.69*6

1.44.6

1.44+7

3.6688

1.84.6

0.06*0

6.589.

4.39+6

1.49+6

1.40.6

3.08~6

3.6+8-

6.04.6

2.23+6

6.32#6

1.68.6

8.686. 6.98+8

8.77+7

0.080.

0.00+0

1.11+8

1.68.8

0.00.0

1.00.8

6.48+7

6.4867

1.02+8

9.74,7 8.18.7

4.66+7

1.49+8

0.00+0

6.00+7

6.14+7

5.68.7

0.0+00

1.33.8

0.00+0

7.6507

1.23+8

9.20.7

1.50+8

0.00.0

8.40+7

6.00+7

8.66*7

0.0010

8 .61+9

3.70+7 2.08+7

2.64+7 8.66+7

2.*607

7.61+6

7.26+8

8.37+7

3.20+7

2.08.7

1.11.7

5.18.7

1.62+7

2.10+7

2.19+7

3.47+7

3.07.7

4.48.7

2.68-07

4.82+7

2.11.7

2.28+7

4.23#7

8.86+8

3.20+7

7.79+8 1 • 17.6

1.1086

4.44+7

1.20.7

2.87+6

2.08+7

S .653.

7.6848

8.86.+

1.6.67

1.34.7

1.88+7

7.61.8

1.80.7

6.88.8

1.0887

2.23+7

-- - - - - n - - - - - - - - - - - - - - - - - - - - - - - m--m ----- mwe -- - --

4.73.9 2.14.9 1.10.9 3.78.9 1.13.9 4.18.0 3.27+9 1.62+9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS, CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY WE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFERs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT I
TABLE A2b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION-POOL OPTION

(1903 DOLLARS)

---------------------------------------------- ----------- - - -------------------------- -

ADD. YEAR C OS T ISHUTDOWN ISTORAGEI WHEN ICONS. - ----------

PLANT NAME YEAR REQ"D ADD'L TIME CONSTRUCTION -o 0 8M - TOTAL

(ASSEM- STOR. (MON.)------------ - - - - ------ ------- - -

BLIES) NEEDED 0% I5 10% ex 56% lox% e% 6x lox%

ARK N0CLEAR 1 208 737 (b) 58 4.55#7 3.57.7 2.83.7 4.53+7 2.21.7 1.20-7 9.08.7 5.78*7 4.03.7

ARK NUCLEAR 2 2012 973 1989 56 4.58.7 8.42*7 2.59#7 5.25.7 2.30.7 1.15.7 9.8837 5.72.7 3.74,7

BEAVER VALLEY 1 2018 1267 (b) 59 5.11+7 4.00.7 3.17+7 7.37+7 3.07.7 1.52.7 1.25+8 7.07+7 4.89.7

BEAVER VALLEY 2 2028 1298 2000 59 5.12+7 2.2387 1.01.7 8.8897 1.a5+7 4.78.6 1.20.0 3.88.7 1.49.7

BELLEFONTE 1 2028 2404 2000 866 .3857 2.77.7 1.28+7 8.87+7 2.01.7 6.70.6 1.60.8 4.78+7 1.03.7

BELLEFONTE 2 2030 2404 2002 66 8.35.7 2.51*7 1.04*7 8.87.7 1.827' 4.71.6 1.50.8 4.33.7 1.51.7

BIG ROCK 1 2001 175 1992 58 4.55.7 2.94+7 1.93+7 2.04+7 1.04+7 5.54.6 6.59.7 3.98*7 2.48.7

A BRAIDWOOD 1 2026 4383 1998 77 8.90.7 8.33.7 4.57.7 1.48,8 4.78.7 2.01+7 2.35+8 1.11.0 6.5087

A BRAIDWOOD 2 2027 (a) 1990

B BROWNS FERRY 1 2014 4594 1999 62 5.55.7 2.87+7 1.83.7 4.58*7 1.49.7 5.38.6 1.01.8 4.16+7 1.87+7

B BROWNS FERRY 2 2014 (a) 1998

BROWNS FERRY 3 2017 3363 1995 59 5.16.7 2.87+7 1.84+7 5.06+7 1.95+7 7.44+6 1.10.8 4.82.7 2.88.7

BRUNSWICK 1 2010 3153 (b) 59 5.09+7 3.99*7 3.18+7 5.78.7 2.70+7 1.43.7 1.09.8 8.89+7 4.59.7

BRUNSWICK 2 2010 3033 (b) 68 5.04.7 3.95+7 3.1387 5.68.7 2.8687 1.40.7 1.07.8 8.81.7 4.53+7

A BYRON 1 2024 4413 (b) 77 8.87.7 6.4987 4.9087 1.46+8 5.25.7 2.43.7 2.35.8 1.17.0 7.23.7

A BYRON 2 2026 (a) (b)

O• CALLAWAY 1 2024 1833 1998 61 5.33.7 2.62+7 1.54.7 7.74.7 2.19*7 7.48+8 1.31.8 5.01.7 2.29+7

-' B CALVERT CLF 1 2014 2789 (b) 86 6.30*7 4.81.7 3.73+7 8.01.7 3.47.7 1.75.7 1.43.8 8.28.7 5.48,7

B CALVERT CLF 2 2018 (a) M

CATAWBA 1 2025 226 2021 68 4.55.7 7.13.8 1.22.8 9.87.8 1.26,8 1.92+5 5.48.7 8.39.6 1.41.6

CATAWBA 2 2026 210 2023 68 4.55.7 8.47.6 1,01.8 6.80,8 8.77+5 1.25.5 5.23.7 7.35.8 1.14.6

CLINTON 1 2027 3260 2000 59 5.12.7 2.23.7 1.01.7 7.12.7 1.89+7 4.82.6 1.22.8 3.92.7 1.49.7

B COMANCHEPK 1 2030 2881 2010 08 8.99*7 1.87.7 6.3.8• 6.55+7 1.09.7 2.13+8 1.35.8 2.98.7 7.486#

B COMANCHE PK 2 2030 (a) 2010

A COOK 1 2009 2009 1991 83 6.73.7 3.89+7 2.68*7 5.2687 2.31#7 1.12.7 1.10.8 6.19.7 3.80.7

A COOK 2 2009 (a) 1991

COOPER STN 2008 1702 1993 58 4.56.7 2.80.7 1.78.7 3.40.7 1.44+7 8.65.6 7.95.7 4.24+7 2.43.7

CRYSTAL RVR 3 2016 048 1999 58 4.6557 2.09.7 9.91.6 3.85+7 1.17.7 3.98,8 8.40+7 3.26#7 1.39+7

DAVIS-BESSE 1 2017 2850 1998 69 7.57+7 5.70.7 4.35.7 9.9987 4.08+7 2.00+7 1.78+8 9.78+7 8.35+7

DIABLO CANYON 1 2025 772 2006 68 4.55.7 1.48.7 6.09.6 4.31+7 8.92+6 2.1226 8.8867 2.37.7 7.21,8

DIABLO CANYON 2 2026 772 2008 56 4.55+7 1.48.7 5.09+8 4.31.7 8.92.6 2.1226 8.8867 2.37.7 7.21.8

DRESDEN 1 1984

DRESDEN 2 2008 1847 1992 56 4.55.7 2.94*7 1.93.7 3.83+7 1.58+7 7.52+6 8.18+7 4.52+7 2.68.7

DRESDEN 3 2006 1325 1994 56 4.55.7 2.6867 1.80.7 3.17.7 1.31.7 5.85+8 7.72.7 3.97+7 2.19.7

DUANE ARNOLD 2010 1610 1991 68 4.55,7 3.08+7 2.12.7 4.3147 1.85.7 8.84.6 8.8687 4.93+7 3.00.7

ENRICO FERMI 2 2026 8459 1990 87 6.77.7 4.81+7 3.4897 1.1208 3.74.7 1.59.7 1.80.8 8.55.7 5.07+7

FARLEY 1 2012 708 1997 58 4.55.7 2.30.7 1.20.7 3.40.7 1.19.7 4.64.8 7.95+7 3.49.7 1.85.7

FARLEY 2 2012 548 1999 56 4.55.7 2.09.7 9.91.8 2.95+7 9.76+6 3.60+6 7.50+7 3.07*7 1.34.7

FITZPATRICK 2015 2966 1991 58 5.02.7 3.40.7 2.34.7 6.17.7 2.40.7 1.08.7 1.12+8 5.80.7 3.42.7

FORT CALHOUN 2008 683 (b) 56 4.55.7 3.57.7 2.83+7 3.85+7 2.00.7 1.1237 8.40.7 6.57+7 3.96+7

FT ST VRAIN 2007

GINNA 2008 411 1994 58 4.55+7 2.8667 1.80+7 2.72.7 1.17.7 5.41.8 7.27.7 3.83.7 2.14.7

GRAND GULF 1 2022 6484 1992 84 5.96.7 3.04.7 2.53.7 8.97+7 2.98+7 1.20.7 1.49.8 8.80.7 3.73+7

HADDAM NECK 2007 631 1990 58 4.55.7 3.24.7 2.34+7 3.85+7 1.82.7 9.33+6 8.40+7 5.06.7 3.27+7

HARRIS 1 2028 a 2026 0 0.00.0 0.00.0 0.00+0 0.00,0 0.00,0 0.00,0
TABLE A2b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION-POOL OPTION

(1983 DOLLARS) (cont'd)

-------------------------------------------------------------------------------------------------------- - ---- - - -

PLANT NAME

o HATCH 1

* HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

LACROSSE

6 LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

ACGUIRE 2

MILLSTONE 1 o• MILLSTONE 2 ~~ MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE

OYSTER CRK 1

PALISADES

PALO VERDE I

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUA CITIES 1

CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR SEND I

SALEM I

SALEM 2

2009

2012

2028

1976

1980

208

2015

2014

2002

2822

2023

2024

2029

2008

2021

2023

2010

2016

2026

2007

2006

2028

2018

2020

2013

2013

2014

204

2811

2824

2026

2028

2008

2008

20286

2008

2007

2087

2008

2008

2"07

2007

2008

2007

2026

2018

2020

4060 1998 61 6.37.7 2.86,7 1.68.7 3.82.7 1.39.7 6.74-8 8.99.7 4.24+7 2.13.7

SI 2001 00 6.28+7 2.19+7 9.86" 8.85.7 1.81*7 4.46+8 1.21+8 3.80*7 1.46+7

901

992

801

11144

(a)

4992

6118

1070

1397

1421

2872

1291

1046

836

1262

2633

2451

(a)

2841

(a)

1381

1424

1039

1827

1631 1631

2724

2469

3444 1898

1137

(a)

1602

(a)

640 958

3220

1487

1687

(b)

1994

1993

1987

1988

1991

1987

1997

1998

4200

1998

1990

2007

1992

1992

1989

(b)

1998

1997 1998

1991

1991

2003

1988

1990

1990

1988

1988

2002

2002

1992

(b)

2601

1989

1992

68

67

68

68

79

63

64

68

60

680

68

68

68

67

57

69

68

57

67

68

69

5860

68

69

81

4.80.7

4 . 78.7

4 66557

4 . 6657

8.02.7

6.765.7

6. 80.7

4.66.7

6.21.7

6.22.7

4.94.7

4 . 97+7 4.08+`7 4.66+7

4.6657

4 . 80.7

6.70+7

3.81.7

2.79.7 2.280+7

3.62.7

6.81.7

4.43+7

3.92+7

3.62.7

2.0837 2.61+7

3.87*7

3.89.7

1.61.7

2.19.7

3.24+7

1.49.7

4.32+7

2.86.7

1.68.7

1'.78.7

2.91*7

4.2867

3.48.7

2.70.7

2.91.7

1.37.7

1.26.7

3.08*7

4 4.93+06 .6937

1.09.7

2.34.7

4.87.6

2.84.7

4.08+7

3.23.7 2.67+*7

2.8657

1.6227

1.38.7

1.2867

2.29.7

2.22.7

7.72.6

2.83.*7

2.41.7

4.13.7

6.08+7

4.78+7

3.40.7

1. 36*.8

1.06.8

1.12.8

4.78.7

6.47.7

6.77+7 6.62+*7

6.84.*7

4.42+7

2.04+7

3.40+7

4.6807

8.30+7

8.17.7

8.99.+7

3.40•7

6.28*27

7.81.7

7.62.7

7.62+7

4.23+7

4.07.7

6.18.7 4.63+7

3.99+7

2.10.7

1.80.7

1 . 78.7

1.94.7

6.03,7

3.80+7

3.8+.7

2.39.7

1.88.7

1 . 83+7

2 . 69.7

2.91.7

8.91+6 7.76.8

1.67.7

9.7.+6

2.98+7

3.61+7

1.76.7

2.42.7

2.16.7

2.06.7

1.90.7

1.83+7

1.37.7

2.21,7

1.88.7

1.17.7

7.38+8 7.686+

1.18+7

2.38.7

1.78.7

1.34.7

1.34.7

8.38+6

6.88+6

1.37+7

1.46.7

2.06+8

3.12.8 8.8.66

2.08+6

1.24.7

8.73+7

9.84.7

9.31.7 7.964,7

2.16-+8

7 9.78

1.83+8

1.70.8

9.31.7

1.17.8

1.20+8

1.05.8

1.18.8

9.28.7 6.69`*7

7.96+7

9.4+4.7

12.0.8

6.71.7 4.69*7

4.68*7 6.68+7

1.08+8

8.23*7

7.28*7

6.01.7 4.61+7

4.34.7

6 • 48.7

8.*80.7

2.40*7

2.97+7

4.91*7

2.40.7

7.28+7

4.03.7

2.41.7

2.62.7

4.09.7

6.62+7

6.22.7

4.04.7 4.26#7

2.01.7

1.84.7

4.43.7

4.64,7

0.98.8

1.40+7

3.23*7

6.93.86

4.08.7

6.97#7 6.29.7 1.84.7 1.61.8 8.90.7 6.90.7

6.20.7

4.5657

4.69.7

6.24+7 6.26+*7

6.26+7

4.91.7

4.76.7

6.19.7

4.66+7 4.09+7

4.07*7

3.40+7

3.69*7

2.78+7

2.6657

2.62*7

3.32+7

3.22.7

1.98.7

3.67+7

3.33+7

1.63.7 9.783+8

1.28*7

7.39.8

8.87+8

6.08+6

9.32.8

8.97+8 2.66*6

1.20.7

9.67+6

1.22.8

7.9657 9.8667

1.29.8

1.29.8

1. 29.8

9.14*7

8.83+7 1.14+8

9.0887

8. 88.7

7.18+7

6.16+7

.01.*7

4.93.7

4 . 70.7

4.47.7

5.22+7

6.05.7

3.33+7 6.78.7

6.21.7

4.78.7

3.64.7

4.11+7

2.26.7

2.05+7

1.87.7

3.22.7

3.1227

1.13.7

4.03.7

3.38.7

6.02.7 8.93.7 3.12.7

4.5657 1.80.7 7.4658

6.14.7 2.61.7 1.386.7

1.13.7 8.688 1.40.6

1.02.8 6.44*7 4.48.7

6.68.7 2.19.7 8.65+0

4.66+*7 4.55.7

6.13+7

6.27+7

6.41+7

2.94.7

3.68+7

2.13.7

3.93+7

3.49.&7

1.9937

2.883.7

9.22.6

2.98*7

2.29.7

3.63.7

4.32.7

8.34.7

7.89+7

7.68.7

1.68*7

2.1657

1.62.7

2.99.o7

2.70.7

7.62+6

1.18.7

4.27.8

1.43.7

1.11.7

8.18.7

8.88+7

1.1658

1.27.8

1.383+

4.62.7

6.73+7

3.66+7

6.92.7

6.19.7

2.68.7

4.01.7

1.36-7

4.41-7

3.40.7
TABLE Abt. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIURATION-POOL OPTION

(1988 DOLLARS) (cont'd)

--------- --------- ------ ---- r-------------- m---------- ---

ADO. YEAR I COST

SHUTDOWN STORAGE WHEN CONS.I

PLANT NAME YEAR REQD AOL II TIME CONSTRUCTION 0 a M TOTAL

(ASSEM- STOR. (MON.) - - ---- --- ------ m--- m---

LIES)NEEDEDm 1 5% lox a% I 5% -1 loIx e1 I Ilox

eeeeeeee I ------------...---- 

.0kmc~j

E SAN ONOFRE I

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAN 1

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE I

ST LUCIE 2

SUMMER 1

A SURRY 2

A SURRY 2

B SUSQUEHANNA I

8 SUSQUEHANNA 2

THREE OSJ MILE 

TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOCTLE I

0 VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2912

2018 2031

2022

2027

2927 2928

2018

2023

2024 2912

2012

2022 2924

2182

2911

2997

2997

2027

2928

2912

2023

2924

2025

2027

2292

2991

2098

2098

3172

18499

(a) 8871

579

670

1838

1558

1189

674

(a) 8ase

(1)

618

661

816

(a) 8251

(0) 1698

4842

1871

3411

(a)

284

1943

(a)

1989

1989

1989

2006

1989

1989

2090

201?

2018

(b)

1992

1909

2005

2005

1995

1995

1997

1998

1995

1905

2006

2009

1993

1994

1997

1994

1994

1999

1920

1988

1988

87

61

72

69

568

56

59

59

58

56

72

56

56

58

71

56

62

69

73

69

56

68

8.72*7 5.01.7 3.79+7 3.20+7 1.84+7 1.11.7

5.39,7

8.68*7

5.1547

4.56*7 4.55.7

5.15.7

5.14.7

5.004?

4.* 55+7

4.* 55,7 4.65+7

8.38*7

4.65+?

5.57.7

5.27*7

8.68*7

5.14.7

4.5567

6.68+7

2.86.7

8.44.7

2.25+7 8.67.6

8.286.

4.04*7

3.28*7

2.29.7

1.56.7

4.89.7

2.80*7

2.19.7

2.54.7

8.86*7

2.89+7

3.26+7

2.86.7

5.9?77

2.36+7

3.24+7

4.39+7

1.87.7

4.85+7

1.02.7

1.78.6

1.62.86

2.16.7

1.89+7

5.6.+6

2.75*7

1.22.7

1.0997

1.45+7

1.88.7

1.76.7

1.95+7 I * 96.7

1.30.7 8.84.7

1.12.7

2.84+7

3.48.7

8.87*7

1.22.8

7.18+7

2.27+7

2.27+7 6.*85,7

8.12+7

8.89*7

1.69+7

1.02.8

2.49.7

2.95.7

2.72.7

9.99.7

4.31.7

8.32.7

7.89.7

1.18-8

8.89.7

2.49+7

5-81.7

1.00+7

4.48*7

1.79.7

8.383.

3.17.6

2.74+7

2.68.7

1.0657

4.48+6

8.0997

9.61.8

1.82+7 1.12.7

2.88+7

1.68+7

2.54.7

2.92.7

3.47*7

1.75.7

1.84+7

2.84+7

6.25+6

2.04.7

4.86*6

5.45.5

4.96.5

1.45-7

1.85+7

5.05.8 1.88-8

1.11.7

3.88+8

3.86*8

4.92.8

6.784.6

7.81.6

9.48+6

8.85+8

1.27+7

6.29M6

7.*556

1.54+7

1.41.8

2.09+8

1.23.8

8.82#7 8.82*7 6.*82.7

1.19.8

1.32.8

1. 14.6

8.14.7

1.88.8

7.04.7

7.59.7

7.27+7

1.84+8

8.86.7 1.89.8

1.27.8

2.95,8

1.22.8 7.94,7

1.16.6

4.26-7 1.8998

8.95+7

1.2•.7

1. 14.7

6.78.7

5.91+7

8.94.7

2.01.7

7.89.7

3.25.7

8.21.7

3.68+7

8.02.7

4.48.7

4.6887

8.54+7

4. 10*7

4.5887

7.2387

1.69.7

8.89+7

1.51.7

2.83#6

2.12.6

4.66*7

3.21.7

1.66+7

8.96+6

3.86+7

1.59.7

1.48.7

1.94+7

2.34.7

2.49+7

2.89.7

2.08.7

4.31+7

1.85.7

3.16.7

4.97+7

9.92.7 8.85.7 4.99.7

-- ......... ----------------------------------------------------------------------------------------- ilililliI•IilimI•II

5.18.9 8.94.9 1.98.9 5.85.9 1.97+9 8.568+ 19.78.9 5.61.9 2.84+9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORSs CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1.

()NEED ADDITIONAL SPACE AS OF 1986.
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - DRYWELL STORAGE OPTION(1983 DOLLARS).

I LOW DENI BEFORE CONVERSION

PLANT NAME TYPE RACKS ------------------- N EEDEDI OX 1 6% 1 10%i -- - -- - - - - - - I -- - - - - - - - - -I.

IAFTER

RERACKINO -------- t

CONVERSION INCREMENTAL COST

5% 1 10% ex 1 5% 1 10%

I-------- ------------------------- --

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BI1 ROCK 1

A BRAIDWOOD 1

A BRAIDWOOD 2

B BRO•NS FERRY 1

B BROWNS FERRY 2

BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

A BYRON 1

A BYRON 2

CALLAWAY 1

B CALVERT CLF 1

8 CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

B COMANCHE PK 1

B COMANCHE PK 2

A COOK 1

A COOK 2

COOPER STN

CRYSTAL RVR 3

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND GULF 1

HADDAM NECK

HARRIS 1

120 138

is@

148

168 168

40

262

(a)

684

(a) 468

378

376

284 (a)

168

192

(a)

144

144

344

198

(a) 268

(a)

282

72

120

8a85

818

316

256

552

188

380

90

240

84

636

104

104

2.04.7

2.26*7

3.10+7

2.97.7

4.94+7

4.94+7

1.89.7

8.84+7

1.04.7

9.81+6

1.49.7

7.77+6

1.27+7

1.1657

1.83+7

3.82.7

S * 1.6

4.62+0

7.74+6

2.22.8

8.686+

2.96+6

S.8*+8

1.92+7

6.42,6

6.64.6

0.21.6

6.47+6

7.84.6

7.84+6

0.68.4

1.03.8

2.89#7

3.26+7

4.22.7

4.14.7

0.41+7

8.41.7

1.96.7

1.17.0

2.08.7

2.18.7

2.82*7

1.67+7

2.37.7

2.1687

1.2387

6.6.+7

1.66.7 1..64+7

2.07.7

8.62+6

9.94+8

8.22.6

7.96+6

4.3907

9.06+8

1.08.7

1.19+7

1.23+7

1.64+7

1.64+7

8.38+6

3.11+7

1.08.7

1.23.7

1.39+7

8.66.6

1.18+7

1.08-7

2.01+6

2.84.7

1.05.7

1.14+7

1.36.7

6.06+8

7.09.6

8.00.8

2.18.8

2.48+7

3.47+7 1.32+7 6.27.8

8.12.7

8.26+7

0.00*0

3.1387

0.00+0

8.84+7

1.22.7 6.03.8

2.11.7 1.44.7

1.94.7 1.27+7

4.21.7 2.33+7

1.32.8 4.67.7 2.09.7 9.98.8

9.02*6 4.04.7 2.02.7 1.08.7

7.69.6 3.90.7 2.73.7 2.0837

7.62*6 3.78+7 2.65+7 1.98.7

1.07.6 1.17+8 7.26+7 6.22+7

7.13.6 4.84.7 2.18.7 1.10#7

7.18.5 6.23+7 4.21.7 3.10.7

1.34.7 9.09.6 6.01.6

1.01.7 8.89.8 8.70+6

7.14+8 7.01.8 8.89.6

7.29+6 7.81.8 7.83+6

3.17.7 3.15.7 3.00+7

1.48+7 1.18.7 8.09.8

1.20-7 1.35+7 1.38.7

3.43+7 1.07+7 8.66+6

6.10+7 2.93+7 1.81.7

0.00+0

0.00+0

3.40.7

6.01.7

0.00•0

0.00+0

1.00+7

9.88.6

0.00+0

0.00+0

3.24+8

2.14.8

6.42.6

6.94.6

6.9686

8.7*76

1.83.7 1.81-7

4.20.7

8.26+7

2.84.6

2.66+8

1.67.7

1.62.7

4.83.6 3.96+6

4.07+8

1.90.7

1.87.7

8.68.6

1.83+7

3.48+8

3.14.8

0.43+8

6.20+8

1.1388

9.89+6

4.81.6 2.01-6

3.33+7 1.64.7 7.48+8 1.12.6 6.0817 3.16-7 2.07-7 1.6887 1.72+7 1.44.7

2.16+7

2.01+7

6.22+7

2.28.7

2.28+7

0.00*.

1.99.7

1.94.7

2.01+7

8.01+7

1.89+7

1.83.7

3.08+7

2.01-7

0.00.0

1.89+7

4.97+7 1.90+7

0.06"0

0.00to

1.06.7

8.83.8

3.08.7

5.63#8 6.68.0

6.63.0

9.28÷8

8.28+8

8.88.8

2.67.7

6.06*8

S.37*8

1.43+7

1.14.7

8.10.8

2.89.7

9.72+8

6.33.6

2.*338

1.68.7

1.48.8

1.46.8

4.61.8

3.88+8

4.13.8

1. 24.7

2.0868

1.87.8

7.14.6

6.84+8

3.63.6

9.765.

4.98+8

4.90*6

3.84+6

6.48.6

3.89+6

3.89.6

0.12+6

6.12.6 6.30+6

1.08.8

8.18.6

6.18.6 7.30,6

3.19+6

2.82.6

1.04.6

4.19.6

4.76*6

2.62*7

2.0837

7.41+7

2.91.7

2.91+7

2.64.7

2.24+7

2.69.7

7.29+7

2.67*7

2.32.7

3.84+7

2.38+7

2.04*7

8.18.7

2.45,7

1.62.7

1.12.7

4.88.7

8.89"8

8.69.8

1.64+7

1.24.7

1.61.7

4.14+7

1.28+7

1.02,7

2.29.7

1.73+7

1.14.7

8.33.7

1.63.7

9.18.6

6.11.8

3.67.7

2.84.8

2.84+6

9.69+6

7.19.6

1.08.7

2.72.7

8.39.6

4.88+6

1.48+7

1.92.7

6.67+0

2.01.7

1.12+7

6.23.8

0.61+8

1.24+7

6.78+8

6.73.8

8.10-6

3.63+6

6.29+8

1.89.7

8.47+6

6.60+8

8.36*8

3.94+8

1.78.8

1.31+7

6.06+6

6.19.8

4.93+8

1.88.7

a. 66*6

3. 66*6

8.72*6

4.7686

7.7"6

1.68+7

7.32+6

6.40.6

9.28.8

6.29.8

3.67.8

1.34.7

8.97+8

4.*338

3.12.0

1.96.7

1.77*8

1.77.6

6.79*6

4.12.8

6.98+8

1.59.7 4.96+8

8.63.8 8.98+8

6.980

3. 27.8

1.14.7

8.88.0
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - DRYWELL STORAGE OPTION(1983 DOLLARS)(cont*'d)

PLANT-- NAM TP RAK---- m---- m-----mm-----m---------RAC--N----- m-w - - -- Im-w -mm --- --w

ILOW DEN 1 BEFORE CONVERSION IAFTER CONVERSION _I_ INCR!C ENTAL COST INEEDEDJOX 1 5% 1 20% el oxI Ilol ox ox lox

-- m I m -I ----- m-w-- -- mw---- - - ---- -- I --- - -.

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

.LACROSSE

B LASALLE CTy I

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE 1

o• MILLSTONE 2

ut MILLSTONE a

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE I

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND I

SALEM 1

SALEM 2

688

(a)

464

1S

162

74

48

666

(a)

448

446

146

144

144

198

156

18

246

184

278

195

(a)

188

(a) 126

256

68

176

170

170

456

446

448

192

98

(a)

126

(a)

486

(a) 138

ISO4 96

884 166

1688

9.11+7 1.83+7 6.8896 1.14.6 4.11+7 2.67+7

9.22+5 4.54.7 1.64.7

1.16+7 1.11+7 8.59.6

8.85.8 1.12+7 7.86+6 3.51+7

6.00.0

2.16.7

2.24+7

2.22+7

1.99.7

1.08.8

5.08+7

5.29+7

2.20+7

3.12+7 3.28+7

3 .37+7 2.80+7

2.18+7

1.81+7

1.98+7

2.79+7

5.605+7

9.99+8 3.11.6

1.21+7

7.74+6

9.59.6

1.24+7

8.80.7

2.3887

2.11+7

1.12+7 9.96+8

9.65+6

2.47+7

1.31.7

4.28+8

8.44+6

1.01+7

8.70+6

2.11+7

7 • 08.8

2.84.6

4.89+6

7.99.8

4.17.7

1.28+7

9.64.6

5.95+6

3.44.6

3.17.6

1.93+7

8.49+6

9.01+6

2.42+8

5.4388

1.78+6

9.*49.6

8.01.5

6.77.5

2.84+5

6.68+4

1.27.8

8.98+5

8.78+5

5.25+5

8.4246

8.42+5

4.05+5

8.13+5

7.45+5

4.89+5

8.86+6

5.71+5

8.91+5

3.08.7 8.86.7

2.79+7

2.12.7

1.16+8

8.30+7- 6.6.+7

3.12.7

4.27.7

4.88+7

3.61+7

3.87+7 3.33+7

1.96+7

2.23+7

3.31+7

8.54+7

2.22.7

1.77+7

1.54+7

1.84+7

7.21.7

8.92+7

3.44+7

2.33+7 1.92;+7

1.84+7

2.65+7

2.62+7

9.51+8

9.18+6

1.49.7

9.38.8

3.83+7

1.8.+7 1.66.7

9.18+6

1.51.7

5.20+7

2.83+7

2.16+7

1.83+7

9.28+6

8.53+6

1.88+7

1.93+7

2.97+6

4.49+6 1.04+7

2.92+6

2.21+7

9.75.6

1.19+7

5.85+6 1.386+

7.87+6

1.33+7 1.3887

9.77+8

1.22+7

1.25+7

2.82+6

1.14+7

1.22+7

2.03+68

3.05+6

5.77+6

1.63+7

1.67+7

1.0.+7

8.12+6

4.08.6

1.04.7

1.83+7

1.42.7

1.26+7

9.70+8 9.35+8

9.75+6

1.37+7

8.99+8

S. 17.6

3 .25+6

1.81+7

8.21.8

4.48.8

1.83+7

7.87+6

5.67+8

5.21-6

1.15+7

1.66+7

1.27+7

1.28+7

8.47+6 8.01+6

1.34+7

2.82+6

2.56+8 5.83+8

1.74+6

1.35.7

7.81+6

8.668+

8.0+66

1.79+6

7.85+6

7.83+8

6.45+6

8.468+

8.09+6 3.856+

7.23,6

6.97+8

9.80+6

2.14+8

8.05+6

5S. 36.6

3.93+86

1.39,7

1.26+7

5.71.7 8.78+7 2.83.7 8.01+5 6.84.7 4.52+7 3.33+7 1.01+7 8.74.6

3.50.7 1.99.?

2.94*7

3.28+7

3.29+7

3.29+7

2.56.7

2.41+7

3.24+7

2.44+7

2.56+7

2.10+7

1.13+7

2.05+7

1.03+7

9.81+8

9.34+8

1.24.7

1.17+7

8.48+8

1.41+7

1.36.7

.*37.7

8.8128

1.63+7

3.51+6

3.19.6

2.91+6

8.32.6

5.97+6

2.41+6

8.56+8

7.69+6

5.42+5

5.11.5 2.70+5

8.74.6

8.74+5

6.74+6

9.02+5

8.73+5

8.93+5

a.97+6

3.84+5

4.35+7 2.38+7

3.26+7

4.69+7

4.59+7

4.59.7

3.35+7

3.18+7

4.19+7

2.88+7

3.11+7

2.9-o7

1.87+7

2.27+7

2.07+7

1.98+7

1.88+7

2.10+7

2.00+7

1.39+7

2.05+7

2.0667

2.18.7

1.22.7

1.89.7

1.0567

9.65,8

1.89,7 1.39+7

1.32+7

6.17+6

1.54+7

1.42+7

9.09*6

4.19+8 3.99+6 1.398+7

1.37+7

1.37+7

8.87+8

8.65+8

1.04+7

4.73+8

5.85+6

9.08+6

5.89+6

2.40.6 1.11.7

1.07+7 1.62.7

9.50+6

9.18+6

8.34.6

8.78.8

7.22+6

2.98+7 1.72+7 1.04+7

1.78+7 6.08+6 2.18.8

4.31+5 3.66+7 2.81+7

9.21+5 2.11+7 8.28.8

1.96+7 7.81+6 9.28.6

3.39+6 4.26+6 3.14+6

1.83+7

2.56+7

3.24+7 3.31+7

3.58*7

8.52+6

1.89+7

9.24+8

1.58+7

1.36+7

2.44+6

1.17+7

2.88+6

7.58+6

6.69.6

8.19+5

4.00+5

7.81+5

7.11+5

7.45+5

2.59+7

3.07+7

4.0.+7

4.62+7

5.07+7

1.56+7

2.21+7

1.49+7

2.96+7

2.79.7

9.87+6

1.88+7

6.03+8

2.08+7

1.89+7

8.18+6

5.69.8

9.01+8

1.39+7

1.57+7

9.72.6

5.64+6

8.47+8 1.60+7

1.50+7
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - DRYWELL STORAGE OPTION(1983 DOLLARS)(contbd)

-------------------------------------------------------------------------------------------------------- LOW DENI BEFORE

PLANT NAME TYPE RACKS ------

I .. NEEDEDi as

CONVERSION I------I

B

IRW..--NG I--

AFTER

5S I lox I .I 0%

CONVERSION INCREMENTAL COST

---- --- ---- ---

------- I ---------I---------

E SAN ONOFRE I

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK I

A SEQUOYAH 1

A SEQUOYAN 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSQUEHANNA 1

B SUSQUEHANNA 2

THREE MILE ISL

TROJAN

on E 7URKEY PT3 0% E TURKEY PT 4

B VOOTLE 1

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

P

P

P

P

P

P

B

P

P

P

P

P

P

P

B

P

p

P

P

P

P

P

P

P

P

276

128

240

(a)

388

104

104

162

144

138

159

(a)

89" (a)

148

98

144

(a)

262

(a)

204

312

178

240

(a)1

152

78

218

(a)

4.03+7 2.23*7 1.26.7 9.5866 6.30+7 3.82+7 2.82+7 1.37+7 1.89.7 1.86.7

a.*94.7

8 .77.7

3.44+7

1.83+7

1.83+7

3.38+7

3.28+7

2.*78+7

1.73+7

8.76+7

1.78.7

1.*91+7

1.80.7

8.09.7

2.07+7

4.75+7

3.*28.7

0.63.7

2.*97.7

1.* 78.

3.* 4+7

1.0347

3.26.7

1.01.7

2.68.8

2.46*0

2.47+7

1.22+7

7.69+8

4.19.0

2.80+7

6.784.6 8.78.8

7.27.8

1.78.7

9.01+6

1.99.7

9.86+8

2.41+7

8.17.6

8.12+8

1.08+7

3.03+8

1.73.7

8.20+.

3.99,6

3.83.6

1.93.7 4.96+0

2.31.0

1.09,8

1.11.7

1.99+8

2.60+8

2.98.6

6.74.0

4.18.8

9.24.0

3.22+8

9.74+8

2.44+6

3.88+8

1.04.7

6.74,6 1.568.

7.38*6 6.61.6

6.46+6

6.62*6

6.26+5

6.56*6

7.03.5

1.31.8

8.64+6

4.37+6 6.39+6

1.11.8

6.63+6

1.59.6

8.90+6

6.77+6

1.80.6

9.64+6

6.19.7

9.03+7

4.28.7

2.44+7

2.43.7

4.03*7

4.32.7

3.64+7

2.18.7

8.4657

2.19.7 2.62+7

2.73*7

0.08+7

2.87.7

6.61.7

4.02.7 8.98*7

4.20.7

2.01,7

6.13+7

1.88.7

6.62+7

1.61+7

4.62+8

4.28.8

2.82+7

2.32.7

1.66.7 7.9386

4.52+7

1.07.7

1.18.7

1.48+7

3.01+7

1.61.7

2.72+7

2.08+7

4.34+7

1.67+7 1.8+.7

1.64*7

7.84.0

3.83.7

6.77.8

9.08.6

8.22.6 2.10+7

1.41.7 6.683+8

2.88.8

2.13+7

6.44+0

6.69+8

8.10.8

1.28.7

9.52.8

1.61+7

9.70+0

2.39.7

7.37*0

9.71.8

2.72+7

1.31.7

2.37+7

9.11+0

8.88+8

8.66+8

7.07+8

1.12+7

1.12+7

6.19.6

1.88+7

4.7086

8.61+8

9.33+8

2.10.7

8.60+8

8.24+8

1.41+7

2.44+7

1.29.7

2.61+8

1.689.7

9.02+8

2.38+7

8.72+8

2.49+8

2.37.8

4.02.8

1.16+7 8.87.8

3.84+6

1.6.+7

6.67+6 5.2578

7.93+8

1.24-7

8.69+6

7.98.8

1.09.7

2.03+7

9.18.6

6.89.8

1.86.7

6.38+8

2.21-7

4.23.8

1.00.8

1.00.0

2.32.0

9.68.0

6.13+8

2.21.6

1.10+7

4.11.8

3.62*8

6.76.8

8.01.8

6.41+8

8.46+8

7.18.6

1.62+7

8.04+8

1.78.7

--- ------------------------------ m ----------- m-mmm--mm ---- m --- m ----------------------- m

3.15.9 1.34.9 8.85.8 8.6557 4.07.9 2.18+9 1.34.9 9.8+8 0.90+.8 7.48.6

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS s CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT I
TABLE As&. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - DRYWELL OPTION

(1993 DOLLARS)

I ADD. YEAR COST

SHUTDOWN STORAGE WHEN CONS - .... "i - i 

PLANT NAME YEAR REQ'D ADD'L TIME CONSTRUCTION "0 S MI TOTAL

(ASSEM- STOR. (MON.)I----------- -------------- -" ----- - ----- IBLIES) NEEDED e I% 15x lox% ex 15x lox I o% 6x lo --------------------------------------------- -------- ------ ------ ----------

ARK NUCLEAR 1 2008 $77 1990 47 1.73+7 9.1568 5.00.6 3.10.0 1.21.8 5.10.5 2.04.7 1.04.7 5.g1.6

ARK NUCLEAR 2 2012 g5a 1999 47 1.68.7 8.69.6 4.0868 3.67.8 1.22.8 4.37.6 2.2567 9.81+8 4.52+6

BEAVER VALLEY 1 2018 858 1996 47 2.3687 1.25.7 8.83+6 7.3686 2.4386 9.08.5 3.10.7 1.49+7 7.74+8

BEAVER'VALLEY 2 2028 858 2009 47 2.35+7 8.61.+ 1.97+8 8.28+6 1.16.8 2.47+5 2.97+7 7.77.8 2.22+6

BELLEFONTE 1 2028 1900 2009 46 3.74.7 1.05+7 3.14+6 1.20.7 2.1256 4.48+5 4.94.7 1.27.7 3.58.6

BELLEFONTE 2 2030 1900 2011 48 3.74.7 9.6358 2.69.8 1.20+7 1.96*8 3.88.5 4.94+7 1.15*7 2.96.8

BIG ROCK 1 2001 95 1995 47 1.7387 9.8128 5.50+8 1.55.8 7.30+5 3.68+5 1.89.7 1.03.7 5.8086

A BRAIDWOOD 1 2028 3627 1996 49 5.89.7 3.02+7 1.65+7 2.95.7 8.0128 2.68+8 8.64+7 8.82+7 1.92+7

A BRAIDWOOD 2 2027 (a) 0.00+

B BROWNS FERRY 1 2014 32268 202 48 2.90.7 1.15+7 4.74+8 5.67•8 1.68.6 5.27+6 3.47+7 1.82+7 5.27.8

B BROWNS FERRY 2 2014 (a) 0.0010

BROWNS FERRY 3 2017 2441 2001 47 2.49+7 1.04.7 4.48.6 8.30.8 1.77+8 6.54.5 3.12+7 1.22.7 5.0.+6

BRUNSWICK 1 2010 2401 1990 47 2.48+7 1.78.7 1.27+7 7.82+8 8.46+6 1.71+8 3.26.7 2.1127 1.44+7

0.0600

BRUNSWICK 2 2010 2281 1991 47 2.4127 1.63+7 1.12+7 7.17+6 8.09+8 1.47+6 8.2137 1.94+7 .1.27+7

0.*00.0

A BYRON 1 2024 3627 1994 49 5.69+7 3.33+7 2.00.7 2.9657 8.83+8 3.25+68 8.84+7 4.21.7 2.33+7

A BYRON 2 2028 (a) 0.00+0

o" CALLAWAY 1 2024 1129 2005 47 2.83+7 8.99+6 3.23.8 7.99+8 1.74+6 4.82*5 3.4387 1.07.7 3.618.

B CALVERT CLF 1 2014 2213 1992 48 3.72.7 2.40+7 1.58-7 1.38+7 5.33+6 2.34.6 5.10+7 2.93+7 1.81.7

B CALVERT CLF 2 2018 (a) 0.00,0

CATAWBA 1 2025 0 2025 0 0.00+0 0.00+0 0.00+0 0.00.0 0.00+0 0.000 0.00*0 0.00.0 0.00.

CATAWBA 2 2026 0 2026 0 0.00+0 0.00+0 0.00.0 0.00+0 0.00+0 0.00+0 0.00.0 0.00.0 0.00.0

CLINTON 1 2027 2572 2006 47 2.6557 8.32+8 2.8568 8.52.8 1.69.8 3.92#5 3.40+7 1.00.7 3.24.6

B COMANCHE PK 1 2030 2087 2015 48 3.99+7 8.38+86 1.89+8 1.02*7 1.48.8 2.4655 5.01+7 9.86+8 2.14.8

B COMANCHE PK 2 2030. (a) 0.00•0

A COOK 1 2009 1241 1999 48 2.88+7 1.86+7 8.77,8 6.04+6 1.88+8 7.12+5 3.33.7 1.54.7 7.48.8

A COOK 2 2009 (a) 0.00.,.

COOPER STN 2008 1228 1997 47 1.84+7 9.32+6 4.88+6 3.0656 1.1826 4.74*6 2.15.7 1.66.7 5.83.6

CRYSTAL RVR 3 2016 482 2005 47 1.73.7 5.90.8 2.12.8 2.84.6 7.39.5 2.06.6 2.01.7 8.3.68 2.38.8

DAVIS-BESSE 1 2017 2490 1995 48 4.61,7 2.6127 1.44.7 1.71+7 5.89+6 2.17.8 8.22.7 3.08+7 1.88+7

DIABLO CANYON 1 2025 617 2011 47 1.88.7 4.81.6 1.31•6 S.97.6 7.17+5 1.45+5 2.28+7 5.586 1.468+6

DIABLO CANYON 2 2025 517 2611 47 1.88+7 4.81.8 1.31+8 3.97+8 7.17+5 1.45+5 2.28+7 5.5386 1.46+6

DRESDEN 1 1984 0 0. 00+0

DRESDEN 2 2008 1016 1998 47 1.73.7 8.30.6 4.13+. 2.58.6 9.59+6 3.80.6 1.99+7 9.268+ 4.51+6

DRESDEN 3 2008 893 2000 47 1.73+7 7.63+8 3.41+8 2.07•8 7.28,6 2.7386 1.94.7 8.28.6 8.88,8

DUANE ARNOLD 2010 998 1999 47 1.73+7 7.90+8 3.78+8 2.84.8 9.83.5 3.86+5 2.01.7 8.88+8 4.16-8

ENRICO FERMI 2 2025 5355 1997 48 4.07+7 2.05+7 1.07+7 1.94.7 5.22+8 1.70.6 8.01.7 2.57+7 1.24.7

FARLEY 1 2012 298 2008 47 1.73+7 5.82.6 1.93.8 1.55+6 4.27.5 1.26+5 1.89+7 8.05+6 2.08,6

FARLEY 2 2012 140 2008 47 1.73.7 6.10+8 1.59+8 1.08+8 2.70.5 7.55+4 1.83,7 5.87+8 1.87+8

FITZPATRICK 2015 2248 1997 47 2.40+7 1.21.7 8.33+8 6.77+6 2.22.8 8.13.5 3.08.7 1.43+7 7.14.8

FORT CALHOUN 2008 418 1994 47 1.7387 1.01+7 6.05+6 2.84+8 1.25.8 5.885+ 2.01+7 1.14.7 8.84.8

FT ST VRAIN 2007 0.0+.0

GINNA 2006 219 2600 47 1.78+7 7.5368 3.41+8 1.55+8 5.72*6 2.22.5 1.89+7 8.10.8 3.8.+6

GRAND GULF 1 2022 4392 1998 48 3.54.7 1.70+7 8.47.6 1.43+7 3.94+8 1.28+8 4.97.7 2.09.7 9.75.8

HADDAM NECK 2007 319 1997 47 1.73.7 8.7126 4.54+8 2.58+6 1.01+. 4.18+5 1.99.7 9.72.8 4.98+6

HARRIS 1 2028 0 2028 0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0

0.00+0
TABLE Age. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - DRYWELL OPTION

(1983 DOLLARS) (contd)

--------------------------------------------------

PLANT NAME

ADD. YEAR I

SHUTDOWN STORAGE WHEN I CONS.

YEAR REQ'D ADDbL I TIME

(ASSEM- STOR. I (MON.)

BLIES) NEEDED

CONSTRUCTION I 0 $ M TOTAL

0% I6x lo I Iss I1lo% osx I Is 1 jx

I COST-- 

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT a

KEWAUNEE

'LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE I

ay MILLSTONE 2 0o MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL I

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM I

SALEM .2

2009

2012

2026

1976

1980

2008

2016

2014

2002

2022

2023

2024

2029

2008

2021

2023

2010

2016

2026

2007

2006

2028

2018

2020

2013

2013

2014

2004

2011

2024

2026

2028

2008

2008

2028

2008

2007

2008

2008

2008

2007

2007

2008

2007

2026

2018

2020

2874

(a) 2820

202

0

493 568

679

205

9824

(a)

4096

4238

682 985

989

2480

823

641

366

884

1971

1866

(a)

2102

(I)

1021

912

836

1117

1121

1121

1812

1689

2648

1512

849

(a)

1142

(a)

603

(a)

228

688

2452

1007

1163

2000

1994 2004

1999

1992

1990

1996

1998

1996

2006

2006

1987

1997

2018

2004

1998

2011

1999

1989

1991

1994

1988

2006

200

20807

1997

1997

2009

1993

1996

1993

2006

20•4

1999

2007

1997

2001

48

48

47

47

47

47

49

48

48

47

47

47

47

47

47

47

47

47

48

48

47

47

47

47

47

.47

47

47

47

47

47

47

47

47

47

47

47

48

2.72.7

2.69+7

1.83,7

1.92+7

1.81.7

1.73.7

8.97+7

3.41.7

3.48*7

1.86+7

2.49+7

2.62.7

2.47.7

2.19+7

1.92.7

1.73+7

1.73+7

2.28+7

3.82+7

1.19.7

8.36+8

1.07+7 6 . 88.

8.30+8

1.11+7

4.96+7

1.90+.7

1.87+7

9.88+8

8.50+6

8.19.8

2.04,7

1.11+7

3.86.8

6.19+6

9.165.

6.77+8

1.7657

2.74+8

6.42+6

2.69.8

3.94+6

7.32.8

3.68.7

1.09.7

8.32+6

6.4048

3.08.8

2.81+6

1.89+7

6.78.6

8.29.6

2.33+8

6.00.6

1.67+8

8.31+8

3.9*+6

8.22.6

3.30+6

3.18.6

4.08+8 2.68+8

3.86.7

1.6687

1.81+7

8.28.8

8.77.8

8.98.4

8.0688

2.82*8

7.7656

2.32+8

6.26.8

1.23+7

1.38.8

1.82.6

1.48.6

8.62.6

1.29.+

1.29+8

1.36+7

4.81+6

4.37+6

1.32.8

1.4658

1.46.4

4.33+8

1.99.4

4.28+6

2.62.6

9.73.6

9.28.6

3.68+8

4.98.6 3.11.7

0.00.0

3.87+6 3.61.7

0.00.0

0.00*0

8.67.6 2.18.7

2.64.6 2.24+7

4.60+6 2.22+7

6.73+6 1.99+7

6.88+8 1.08.8

0.00.0

1.70+8 6.08+7

1.32+6 6.29+7

6.64*6 2.20+7

3.77+6 3.12+7

3.6756 3.20.7

2.37+8 3.37,7

7.27.6 2.80+7

7.21.4 2.18+7

8.88+4 1.81.7

4.31+6 1.98.7

1.8656 2.79.7

1.18.8 6.05.7

0.00+0

3.6508 6.71.7

0.00+0

1.89.8 3.6507

6.6865 1.99.7

1.84+8 2.94.7

4.11.6 3.28+7

3.7456 3.29.7

3.40.6 3.29+7

6.74+5 2.6657

6.38.6 2.41.7

2.73+5 3.24+7

8.86.6 2.44+7

7.18.6 2.6.-7

0.00.0

1.11.0 2.98+7

6.60,4 1.78.7

0.*00.0

1.11.6 1.83.7

1.27.8 2.58-7

3.32+6 3.24.7

8.8756 3.31+7

8.64+5 3.68+7

1.33.7

9.98.4

1.21.7

7.74.6

9.69+6

1.24.7

6.30•7

2.3887

2.11.7

1.12+7

9.96.8

9.85+6

2.47*7

1.31.7

4.28.8

8.44.4

1.01.7

8.70.6

2.11.7

3.73.7

2.10.7

1.137

2.0857

1.03.7

9.81.6

9.34.8

1.24.7

1.17-7

8.48.4

1.41.7

1.38.7

1.72.7

6.08.8

0.52.6

1.69+7

9.24.6

1.6367 1.98-7

6.88+6

3.11.8

7.08+8

2.84.8

4.39.6

7.99.6

4.17.7

1.28.7

9.64+8

5.96+8

3.44+8

3.17.8

1.93.7

8.49*8

9.01.5

2.42.6

6.43+6

1.7606

9.49+6

2.83.7

1.37.7

6.81.6

1.63.7

3.51.6

3.19.8

2.91.8

8.32*8

5.97+8

2.41.8

8.6*8+

7.69+6

1.04+7

2.18.8

2.44*8

1.17.7

2.88.8

7.68+8

6.69+8

4.06+7 3.02.7 2.28+7 1.6867 7.10.6

2.6687

1.73+7

2.17.7

2.62+7 2.63+7

2.63+7

2.18+7

2.08.7

2.6657

1.99+7

2.16+7

1.73.7

1.01.7

1.*70+7

8.83+8

8.23+8

7.84.8

1.10.7

1.04.7

7.19+8

1.22+7

1.20.7

1.20.7

8.0668

1.3+,7

3.1*8

2.82.8

2.67,6 6.76+8

6.43+6

2.14.6 7.67.6 7.87.8

9.38+8

2.68.6

7.87+8

7.60.8

7.01+6

7.81.8

3.89+6

3.48.8

6.90.8

4.63+6

3.97+8

3.72+8

1.17.0 3.62+8

1.66+8

1.68.8

1.658.

1.41.8

1.32.6

1.29.8

1.92+6

1.63+8

2.41+7 1.48+7

1.73.7 5.90+8

9.28.6 6.68.6 2.41.6

2.12.8 6.18+6 1.64.6

1.73+7

2.03.7

2.62.7

2.64+7 2.74.7

8.19.8

1.44+7

7.80.8

1.28+7

1.14+7

2.33.8

1.04.7

2.66.6

8.89.8

4.9386

1. 03.8

5.256+

7.17.8

7.86.8

8.39+8

3.29.6

2.47+6

1.44.6

2.48+8

2.22.6
TABLE Aft. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - DRYWELL OPTION

(1963 DOLLARS) (cont'd)

------------------------------------ ------- mm -------- m --- w ----- m ------ m ----------------- m ---

ADD. I YEAR

SHUTDOWN STORAGE WHEN CONS.-

PLANT NAME YEAR REQ'D IADD'L TIME CONSTRUCTI.

(ASSEM- ISTOR. (MON.) -------

IES) NEEDED .... ---- ---- ---- -- -- -

-I

H

------I1o% I -T - - --- ---- --

0% 15% lax e 1 r,% I l. . .

01

'C

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 8

SEABROOK 1

.A SEQUOYAH 1

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE .1

ST LUCIE 2

SUMMER 1

A SURRY I

A SURRY 2

B SUSQUEHANNA 1

B SUSQUEHANNA 2

THREE MILE ISL I

TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOOTLE 1

B VOCTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD S

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2012

2013

2031

2021

2022

2027

2027

2028

2010

2023

2024

2012

2013

2022

2024

2008

2011

2007

2007

2027

2028

2012

2023

2024

2025

2027

2025

2001

2008

2008

2362

1261

2890

2831

258

258

1182

1128

781

97

(a)

7289

373

384

(a)

2491

(a)

lose

4018

1143

2691

857

36

1295

(a)

1996 48 3.77.7 2.10.7 1.20.7 2.6558

200 1995

2008

2023

2024

1987

2001

2009

2012

2000

2006

2004

2002

2006

1999

1998

2008

2001

2008

1999

1995

48

48

47

47

47

47

47

47

47

49

47

47

47

48

47

48

47

48

47

47

48

2.87.7

4.87.7

2.58.7

1.73.7

1.73*7

2.48.7

2.42.7

2.23+7

1.73+7

4.86+7

1.73+7

1.73+7

1.73.7

4.47+7

1.73.7

3.35,7

2.55.7

4.89.7

2.35.7

1.73.7

2.92+7

0.48.6

2.60.7

8.41.6

2.45.8

2.33+6

2.04*7

1.01+7

4.19+6

2.12.7

5.62.6

8.19+6

6.83+6

1.46.7

7.90+.

1.61,7

9. 31.8

1.95.7

8.95+6

7.90.6

1.63.7

2.65.6

1.49.7

2.088"

3.81.5

3.47*5

1.09+7

4.85+8

2.06.6

1.09+6

9.61.6

1.93.8

2.33.8

2.82.6

6.00.6

3.76+6

8.03.6

2. 85.6

8.43.6

2.17.8

3.76+6

9.*306

1.07.7

2.10+7

8.63.6

1.03,8

1.03.8 8.08+6

8.36.6

5.51+8

0.00,0

1.84.7

5.1,5

1.81+8

1.29.8

1.62,7

3.36.6

1.40.7

7.29.8

1.94,7

6.24+6

8.19.8

1.88.8

8.45*6

1.71.8

1.30*5

1.24.5

4.33.8

2.08.8

1.10.6

0.00.0

4.82*6

1.5685

5.36.5

4.42*5

8.21*8

1.11,6

3.79.6 1.94+0

4.88.6

1.22.6

2.20*5

2.49.8

3.83.5

2.35.8

3.97.5

1.81.4

1.64.4

2.37.6

5.99+5

2.49.5

0.00*0

1.46+6

5.00+4

1.70+5 1.60.6

7.43+5

3.99+5

1.21+6

3.71.6

1.31+6

2.72+5

9.75+4

1.08+6

1.26.6 6.44+5 4.03.7

0.00.0

0.00.0

3.94.7

8.77.7

0.00.0

3.44.7

1.83.7

1.83.7 3 * 38.7

3.26.7

2.78*7

1.73.7 0.00.0

6.70.7

0.*00.0

1.78.7

1.91.7 I • 88.7

0.00,0

8.09,7

08.00+6

2.07,7

4.75+7

3.28.7

6.00+6 8.63.

2 . 97+7

1.78.7 3 . 64.7

0.00+0

3.15.9

1.03.7

3.25.7

1.01.7

2.58.6

2.45.6

2.47.7

1.22.7

7.69.8

4.19.8

2.60.7

5.78.6

6.73+8

7.27.6

1.78+7

9.01.6

1.99.7

9.85+6

2.41,7

8.17+6

8.12.6

1.88.7

3.03.6

1.73.7

8.28.8

3.99.5 3.63.5

1.93.7

4.95.8

2.31.6

1.09•6

1.11.7

1.98.6

2.50+6

2.98.8

5.74*6

4.18.6

9.24.6

3.22+6

9.74+8

2.44*6

3.8086

1.04*7

2.2387 1.28.7

------------ -----------------------------------------------------------------

2.45+9 1.13.9 5.89.8 6.99.8 2.08.8 7.65+7 1.34+9 8.85.8

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1
TABLE Agb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - DRYWELL OPTION

(1983 DOLLARS)

--------------------------------------------------------------------------------------------------------------

ADD. YEAR COS 5T

SHUTDOO N STORAGE WHEN CONS. I ........- I .......................

PLAiT NAME YEAR REQ8D ADD'L TIME CONSTRUCTION I TOTAL

SLIES) NEEDED % 16x 1 tx % s 1 6% ex % 10K --------------------------------------- m-----m---- ------ mm--- ----------------

ARK NUCLEAR 1 2008 737 (b) 47 2.21+7 1.73.7 1.37.7 8.81.6 3.32*8 1.8.8 2.89.7 2.06#7 1.66.7

ARK NUCLEAR 2 2012 973 1989 47 2.39.7 1.78.7 1.8567 8.68.8 3.70.8 1.87.8 3.25.7 2.1607 1.54.7

BEAVER VALLEY 1 2010 1287 (b) 48 2.90+7 2.27+7 1.8007 1.32.7 6.66.8 2.72+8 4.22+7 2.82.7 2.07.7

BEAVER VALLEY 2 2026 1298 280 48 2.91+7 1.27.7 6.76.8 1.23.7 2.98+8 8.6806 4.14.7 1.57.7 0.82.8

BELLEFONTE 1 2028 2404 2880 48 4.33*7 1.89.7 8.57.8 2.08*7 4.83.8 1.37.0 8.41.7 2.37.7 9.94.8

BELLEFONTE 2 2930 2404 2602 48 4.33.7 1.72.7 7.09.8 2.08.7 4.3880 1.13.8 8.41+7 2.10.7 8.22+8

BIG ROCK 1 29081 176 1992 47 1.73+7 1.11+7 7.32.8 2.32+6 1.18.8 0.31.6 1.98+7 1.23.7 7.9568

A BRAIDWOOD 1 2028 4383 1990 49 7.18+7 6.10.7 3.6887 4.47.7 1.48+7 8.17+8 1.17+8 0.68.7 4.30.7

A BRAIDWOOD 2 2027 (a) 1999

B BROVKS FERRY 1 2014 4594 1998 48 3.88.7 1.77.7 8.0800 9.92.8 3.23+8 1.18.0 4.67.7 2.60+7 9.9688

B BROWNS FERRY 2 2014 (a) 1998

BROAIS FERRY 3 2017 3353 1995 48 2.97.7 1.68.7 9.47.8 1.07+7 3.68.8 1.386.8 4.04.7 2.02.7 1.08.7

BRUNSWICK 1 2910 3153 (b) 48 2.07.7 2.26.7 1.78.7 1.03.7 4.81.8 2.64.8 3.90.7 2.73.7 2.03+7

BRUNSWICK 2 2010 3033 (b) 48 2.79+7 2.18.7 1.73+7 9.91+0 4.86.8 2.46+8 8.78.7 2.8657 1.98.7

A BYRON 1 2024 4413 (b) 49 7.20.7 6.84.7 4.47+7 4.6507 1.82.7 7.5088 1.17.8 7.2607 6.22.7

A BYRON 2 2028 (a)

o CALLAWAY 1 2024 1633 1998 48 3.30.7 1.76.7 9.68.8 1.54+7 4.33+8 1.48+6 4.84.7 2.18.7 1.10.7

B CALVERT CLIF 1 2014 2789 (b) 48 4.31.7 3.38.7 2.88.7 1.92.7 8.82.8 4.20.6 .23.7 4.21.7 3.18.7

8 CALVERT CLF 2 2018 (a) ()

CATAWBA 1 2026 228 2921 47 1.73.7 2.70+8 4.81+6 1.08.8 1.43.6 2.19+4 1.83.7 2.64+8 4.83*5

CATAWBA 2 2028 210 2023 47 1.73.7 2.4658 3.81.5 7.76.6 9.99.4 1.42.4 1.81.7 2.55.8 3.95.5

CLINTON 1 2027 3289 200 48 2.92+7 1.27.7 5.77.8 1.28.7 8.04.8 8.88+6 4.20.7 1.57.7 8.84.8

B COMANCHE PK 1 2030 2681 2910 48 4.85.7 1.25.7 3.66.6 1.6007 2.88.8 6.21.5 8.26.7 1.62+7 4.07.8

B COMANCH PK 2 2030k (a) 2010

A COOK 1 2009 2009 1991 48 3.89.7 2.63.7 1.82.7 1.19.7 6.23+8 2.65+. 5.08.7 3.16+7 2.07.7

A COOK 2 2009 (a) 1991

COOPER 5TN 2908 1702 1993 47 2.13+7 1.321.7 8.22.6 4.89.8 2.08.8 9.57+5 2.82.7 1.62+7 9.18.8

CRYSTAL RVR 3 2918 648 1999 47 2.09+7 9.68*8 4.55*8 5.42*6 1.65.68 6.676 2.83.7 1.12+7 5.11.8

DAVIS-BWSSE 1 2017 2850 1988 49 4.94+7 3.87.7 3.07.7 2.47+7 1.01*7 4.98.8 7.41.7 4.88.7 3.67+7

DIABLO CANYON 1 2026 772 200 47 2.2657 7.32*8 2.61.8 8.01.0 1.37.8 3.2656 2.91.7 8.89+8 2.84.6

DIABLO CANYON 2 2026 772 208 47 2.26.7 7.32+0 2.61.8 8.618 1.37.8 3.2656 2.91.7 8.69.8 2.84.8

DRESDEN 1 1984

DRESDEN 2 208 1647 1992 47 2.04+7 1.32+7 8.6088 4.97.8 2.1*78 1.03+0 2.64.7 1.54.7 9.89+8

DRESDEN 3 2008 1325 1994 47 1.85.7 1.08,7 8.47+8 3.89.8 1.81.8 7.17+6 2.24.7 1.24.7 7.19+8

DUANE ARNOLD 2010 1510 1991 47 2.01.7 1.38.7 9.38.8 6.89.8 2.60+8 1.19+6 2.69+7 1.81.7 1.08.7

ENRICO FERMI 2 2026 8469 1990 48 4.65+7 3.2387 2.33+7 2.74+7 9.12+8 3.88.8 7.29.7 4.14.7 2.72.7

FARLEY 1 2012 708 1997 47 2.17.7 1.10.7 5.72.8 6.01.8 1.75.68 8.685 2.87+7 1.28.7 8.39+8

FARLEY 2 2012 648 1999 -47 1.94+7 8.90.8 4.23.8 8.82+8 1.28+8 4.54.6 2.32+7 1.02.7 4.88.8

FITZPATRICK 2015 2968 1991 48 2.77.7 1.87+7 1.29+7 1.07+7 4.17.8 1.87t8 3.84.7 2.29.7 1.48.7

FORT CALHOUN 2098 883 (b) 47 1.89.7 1.48+7 1.18.7 4.84.8 2 62+0 1.42.8 2.3807 1.73.7 1.32*7

FT ST VRAIN 2007

QINNA 2008 411 1994 47 1.73.7 1.01.7 8.0586 3.10+6 1.34.8 8.17.6 2.04+7 1.14.7 8.67.8

GRAND GULF 1 2022 6484 1992 48 4.09+7 2.84+7 1.78.7 2.09.7 8.91.8 2.79.0 8.10+7 3.33+7 2.01.7

HADDAM NECK 2007 831 1999 47 1.96.7 1.39.7 1.09.7 5.02+8 2.37+0 1.22.8 2.4657 1.83+7 1.12.7

HARRIS 1 2028 0 2028 0 0.00.0 0.00.9 0.00+0 0.00.0 0.090+ 0.00.0
TABLE Afb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - DRYWELL OPTION

(1983 DOLLARS) (cont'd)

------------------------ - ------------------------------------------------------------------------ ---

ADD. YEAR

SHUTDOWN STORAGE WHEN CONS. - ... ..----------

PLANT NAME YEAR REQ'D ADO'L TIME CONSTRUCTII

(ASSEM- STOR. (MON.)

BLIES) NEEDED e! I5

C 0 ST

.. .. . I --- I . ... . ..

0 S M --I TOT•A I 6• I

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT I

INDIAN PT 2

INDIAN PT 8

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCOUIRE 2

MILLSTONE 1 • .j MILLSTONE 2

:-' MILLSTONE 3

MONTICELLO

HNIE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 8

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE S

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH I

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B qUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM 1

SALEM 2

2009

2612

20286

1976

1986

2008

2016

2014

2002

2022

2023

2024

2029

2068

2021

2023

2010

2015

20285

2007

2005

2026

2018

2020

2013

2013

2014

2004

2011

2024

2025

2026

2008

2009

2628

2008

2007

2008

2008

2008

2607

2e87

2008

2007

2025

2016

2026

4050

901

992

8s1

301

11144

(a)

4992

5116

1070

1397

1421

2872

1291

1046

835

1252

2538

2451

(a)

2641

(a)

1381

1424

1039

1627

1631

1831

2724

2469

3444

189e

1137

(a)

1502

1488 (m)

640

958

8220

1487

1667

1998

1998

2001

(b)

1994

1998

1987

1998 1991

1987

1997

1998

2007

1998

1990

2007

1992

1992

2 bb

bI

1989

(b)

1996

1997

1998

1991

1991

2003

1988

1990

1990

1988

1968

2002

2002

1992

(b)

2001

1989

1992

48

48

4?

47

4?

47

48

48

47

48

48

48

48

47

47

47

47

48

48

48

4?

4?

48

48

46

47

47

40

47

47

48

47

47

47

48

48

48

3.38.7 1.79+7 9.79+8 7.33+8 2.81+8

3.21.7 1.83+7 5.78+8 1.83.7 8.12#6

1.168. 4.11.7 2.0*77 1.10.7

8.69*5 4.84.7 1.84.7

2.40.7

2.52.7

2.10.7

1.7387 7.15+7

8.91,7*

3.95.7

2.35+7

3.06.7

3.16.7

2.87.7

2.70+7

2.59.7

1.78.7 1.*82,7

2.54.7

4.52.7

1.88.7

1.47.7

1.29.7

1.42.7 5.60.7

8.06.7

2.67.7

1.94.7

1.5567

1.49+.7

2.09.7

2.12.7

8.62.6

1.29.7

7.87+6

2.91.7

1.49+7

6.83+8

8.11+6

1.18*7

4.44.7

2.43.7 1.04+7

1.81.7

8.07+8

7.42+6

1.85.7 1.88.7

2.63+8 4.13+6

9. 32+8

2.68+6

1.91.7

6.75+8

8.38.8

8.7568

3.87+8

4.3147

2.39.7

2.6557

7.71+6

1.21.7

1.28.7

9.39.6

1.17.7

7.41.8 2.22+8

4.1998

7.65.6

2.82+7

8.44*.

2.99.8

-2.55+8

2.20.6

1.61.7

8.8666

7.87.8

3.87.6

8.51+6

3.46+8

4.46.8

4.98.6

1.49.8

8.83+5

2.01#8

1.61.6

7.20+6

1.91.8

1.21+8

1.87+6

1.34+8

7.6*68

3.98+8

2.17.6

1.19.6

1.11.8 2.33+6

2.49#8 3.43.6

3.4805

1.06.8

8.42.5

3.02+8

3.09+7 8.86,7 $.38#7

2.78+7

2.12.7 1.16-8

8.30+7

6.60+7

3.12-7

4.27+7

4.38+7

3.81+7 1.87*7

3.$337 1.96.7

2.23+7

4.31.7

8.64.7

2.22.7 1.7?7-

1.54.7

1.84.7

7.21*7

3.92.7

8 * 44.7

2.8387

1.90.7

1.84+7 2.53+7

2.82.7

9.51.8

9.18.6

1.49.7

9.68.7 S.$9.7

4.84.7 3.84.7 2.88+7 2.0&?7 8.84.8 4.51+8 8.64.7 4.52.7

6.6568

1.68.7

1.00.7

9.18.6

1.31.7

5.20.7

2.83.7

2.16.7

1.83.7

9.268+

8.9*68

1.88+7

1.93.7

2.97.6

4.49+6

1.04.7

2.92.6

2.21.7

3.33*7

2,18-7

1:22-7

.1.89+7

1.05#7

9.556+ 8.19.7

1.39+7

1.32.7

5.17.6

1.5487

1.4297

1.98.7

3.3916

9.87+6 1.65.7

8.03+6 2.42.7

1.89.7

8.05.7

1.92÷7

2.39#7

8.14.7

3.14.7

3.14.7

2.6837

2.51.7

3.04.7

2.20+7

2.45.7

2.39+7

1.44+7 1.87.7

1.66.7

1.59.7

1.51.7

1.78.7

1.14+7

1.72.7

1.74+7

1.89.7

1.09+7

1.48.7

9.09.6

8.28,6

7.*586

1.2387

1.17.7

4.51.6

1.36.7

1.26.7

1.38.7

4.38+8

8.59*8

1.46.7

1.45.7

1.45+7

7.16.6

6.74.8

1.15+?

6.76.8

6.68+8

5.64+6

2.25.6

3.95.6

4.09.8

8.91+6

3.72+8

3.21+6

3.0836

2.53+8

3.30+8

3.09+8

2.8598 1.26+6

2.06+8

1.46.8

1.27#8

1.18-6

1.88.6

1.48.6 8.58-5

1.79.6

1.59.6

4.3557

2.36*7

3.25.7

4.59+7

4.89*7

4.89*7

3.35+7

3.18.7

4.19.7

2. 88+7

3.11.7

2.98.7

1.87+7

2.27.7

2.07+7 1.98-7

I • 88.7

2.21.7

2.06.7

2.8957

2.08.7

2.77.7 2.17.7 1-72+7 8.94.6

1.98.7 7.77+6 3.2148 1.49-6

4.38.8 2.36.6 8.86*7 2.81.7

5.89.5 1.84.5 2.11.7 8.28"8

2.1887

2.37+7

2.92.7

3.19.7

3.45.7

1.34.7

1.86.7

1.22+7

2.38.7

2.28.7

8.82.6

1.47.7

5.26.8

1.80.7

1.46.7

5.07+6 7.6478

1.14+7

1.4387

1.62+7

2.22#6

3.51.8

2.73+6

5.78+8

5.56.6

1.0568

1.93+8

7.7125

2.76+6

2.28+6

2.59.7 8.67.7

4.68.7

4.62+7

5.07+7

1 56+,7

2.21+7

1 249+7

2.98.7

2.79+7
TABLE A3b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - DRYWELL OPTION

(1983 DOLLARS) (cont'd)

ADD. YEAR C 0 S T

SHUTDOWN STORAGE WHEN CONS. - ------------ ------- -------

PLANT NAME YEAR REQD ADDI'L TIME CONSTRUCTION O TOTAL

(ASSEM- STOR. (MON.) ---

BLIES) NEEDED 0%x5 1 % I 0 ~ 5 1 % l K % 1 6

----------------------------------------- ------- ------- ------ ------ --------- ---

E SAN ONOFRE 1 1999 3172 1989 48 4.62+7 3.37+7 2.66.7 7.78.6 4.4946 2.70.6 6.30.7 8.02+7 2.82+7

E SAN OHOFRE 2 2012 (a) 1989

E SAN ONOFRE 3 2013 1989

SEABROOK 1 2031 1646 2000 48 3.42.7 1.49+7 6.77+0 1.77.7 3.89.6 1.07+8 6.19+7 1.88-7 7.84.6

A SEQUOYAH 1 2021 3400 1989 49 6.82.7 4.34+7 3.29+7 3.21+7 1.18-7 5.40+8 9.03.7 5.62+7 3.83.7

A SEQUOYAN 2 2022 (a) 1989

SHORE"lA 2027 3371 200 48 2.97+7 1.30+7 6.88+6 1.31#7 3.10+6 8.88.5 4.28.7 1.61+7 6.77+8

SOUTH TEXAS 1 2027 670 2017 47 2.12+7 4.04+8 8.30+5 3.24+6 4.77.5 7.80+4 2.44+7 4.52.6 9.08+6

SOUTH TEXAS 2 2028 670 2018 47 2.11.7 3.83+6 7.61+6 3.23+6 4.62*6 7.08+4 2.43+7 4.28.6 8.22*6

ST LUCIE 1 2010 1638 (b) 48 2.96.7 2.32+7 1.84.7 1.07.7 6.00+8 2.64+6 4.03+7 2.82+7 2.10+7

ST LUCIE'2 2023 1668 1992 48 2.87.7 1.86+7 1.22+7 1.46+7 4.69+8 1.88+6 4.32+7 2.32+7 1.41+7

SUMMER 1 2024 1169 1999 48 2.74.7 1.28+7 6.96+8 1.10+7 2.86+5 8.72+5 3.84+7 1.66+7 6.83+0

A SURRY 1 2012 674 2005 47 1.97,7 6.74+6 2.42+6 2.09+6 5.91.6 1.79+6 2.18.7 7.3.+6 2.80+6

A SURRY 2 2013 (a) 2005

6 SUSQUEHANNA 1 2022 8680 1996 49 6.77+7 3.21+7 1.84.7 2.68+7 8.11+6 2.93+6 8.46+7 4.02+7 2.13+7

8 SUSQUEHANNA 2 2024 Ia) 1996

THREE MILE ISL 1 208 13 1997 47 1.88.7 9.60.8 4.96+8 3.12+6 1.19.8 4.86+6 2.19+7 1.07+7 6.44.6

TROJAN 2011 661 1998 47 2.10.7 1.01.7 5.04.6 4.18+6 1.46.6 6.47.6 2.62.7 1.16+7 6.69.6

E TURKEY PT 3 2007 818 1996 47 2.30.7 1.28+7 7.32+6 4.28.6 1.76+8 7.76+6 2.73.7 1.46+7 8.1068

E TURKEY PT 4 2087 (a) 1995

B VOOTLE 1 2027 3261 200 49 6.61.7 2.40+7 1.09+7 2.67+7 6.088+6 1.74.6 8.0887 3.01+7 1.26+7

B VOOTLE 2 2028 Ia) 2000

VT YANKEE 1 2012 1696 1993 47 2.07.7 1.27.7 8.00#0 6.01.6 2.35.8 1.02+6 2.67.7 1.61+7 9.02#6

WASH NUCLEAR 2 2023 4642 1994 48 3.70+7 2.17+7 1.30+7 1.81.7 6.63+6 2.0656 6.61.7 2.72+7 1.61+7

WATERFORD 3 2024 1671 1997 48 3.19+7 1.61+7 8.41+6 1.43.7 3.91+6 1.29+0 4.62+7 2.0*7 9.70.6

A WATTS BAR 1 2025 3411 1994 49 6.84.? ,ý42+7 2.06+7 3.12.7 9.18.6 3.36+6 8.96+7 4.34+7 2.39+7

A WATTS BAR 2 2027 (a) 1994

WOLF CREEK 1 2026 1313 1999 48 2.9657 1.35,7 6.41+8 1.26+7 3.17.0 9.69+5 4.20+7 1.87+7 7.37,6

YANKEE-ROWE 1 2001 264 1990 47 1.73,7 1.23.7 8.86+8 2.84+8 1.62+6 8.61+5 2.01+7 1.38+7 9.71+6

A ZION 1 2008 1943 1988 48 3.83+7 3.00+7 2.38+7 1.30.7 6.36*6 3.44+8 6.13+7 3.64.7 2.72+7

A ZION 2 2"08 (a) 1988 ------------------------------------------------------------------------ ---------------- ----------------------------

TOTAL 2.93+9 1.77.9 1.17+9 1.14.9 3.92+8 1.89+8 4.07.9 2.16+9 1.34.9

AB

E

INDICATES COMMON POOL SHARED 13Y TWO REACTORSt CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE IND)ICATES POOLS CONNECTED BY TRANSFER" CANAL: CAPACITIES AND INVENI"ORIES ARE COMBZINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUJIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INZCLUDED IN UNIT 1.

NEED ADDITIONAL SPACE AS OF 198".
TABLE A4. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - VAULT STORAGE OPTION(1983 DOLLARS).

---------------- LOW---DEN BEFORE----CONVERSION--- ----- I--- AFTER----CONVERSION---- --- I LOW DIN1 BEFORE CONVERSIO! AFTER CONVERSION

PLANT NAME TYPE RACKS I----------------- RERACKING

NEEDEDI1 OX 15 lox

INCREMENTAL COST

ex I 5% I 1e%

A

AB

B

A

A

(AB

B

B

B

A

A

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK I

BRAIDWOOD 1

BRAIDWOOD 2

BROWNS FERRY 1

BROWNS FERRY 2

BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

BYRON 1

BYRON 2

CALLAWAY 1

CALVERT CLF 1

CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

COMANCHE PK 1

COMANCHE PK 2

COOK 1

COOK 2

COOPER STH

CRYSTAL RYR 3

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND GULF 1

HADDAM NECK

HARRIS 1

120

138

188

148

168

168

40

252

(a)

684

(a) 456

378

378

284

(a)

188

192

(a)

144

144

344

198

(a)

2582 (a),

232

72

120 1es B5

85

318

318

258

552

136 138

386

240854

538

184

104

104

3.5607

3.94,7

6.89.7

5.82+7

1.04+8

1.04.8

3.19.7

2.01+8

1.77.7

1.71+7

2.8907

1.45+7

2.65+7

2.41.7

1.75.7

8.79+7

9.36.8

7.82.8

1.44.7

4.12.8

7.44.6

8.18+6

9.9088

4.39,7

5.42+5 5.54,5

8.21.5

6.47+5

7.34,5

7.34+5

8.56.4

1.03.8

5.39,7

8.23.7

8.62.7

8.38.7

1.44+8

1.44+8

3.35,7

2.81+8

3.79,7

4.08.7

5.69.7

3.11.7

5.28.7

4.7947

2.10+7

1.39.8

2.83.7

2.88+7

4.06+7

1.30+7

2.20.7

1.82+7

1.3657

8.59,7

1.94.7

2.35.7

2.89.7

2.80.7

4.08+7

4.08+7

1.82.6

8.08.7

2.07.7

2.41.7

2.85.7

1.72.7

2.70+7 2.46+7

3.58.8

6.20+7

8.86.7 2,57.7 1.03.7 1.32.8 9.78.7 4.35+7 2.07.7

5.99.7

8.3307

0.00+0

5.97#7

0.00+0

2.01+8

8.71.7

1.0808

0.00,0

0.00.0

8.84+7

1.08.8

2.30.7 9.51.8

4.02.7 2.72*7

3.8.+7 2.37.7

9.89+7 5.31.7

2.07.7 7.01.8

8.18.7 3.76,7

9.02+5 8.14+7 3.99+7 2.14+7

7.59.5 7.79+7 5.38+7 3.98+7

7.52+5 7.52+7 5.19+7 3.84.7

1.07.8 2.82+8 1.43,8 8.93+7

7.13.5 9.99+7 4.44+7 2.22+7

7.16+5 1.39+8 8.94+7 8.24+7

3.04.7 1.91.7 1.17.7

2.24+7 1.78.7 1.28+7

1.57.7 1.44.7 1.34.7

1.63.7 1.81.7 1.54+7

8.19+7 4.a9+7 3.73+7

3.35.7 2.44+7 1.59.7

3.22.7 2.88+7 2.5657

1.94.7

2.13,7

2.89+7 9.6a+8

1.53.7

1.2987

3.83+6

4.31#7

0.00,0

0.00+0

1.93.7

2.1207

0.00.0

0.00+0

8.17.8

4.6556

6.42.6

5.94+5

8.9685

8.78+6

3.09.7

3.04.7

0.49.7

1.44.8

4.88+8

4.20.8

3.12.7

3.47+7

8.14.6 8.84+5

1.31.7

9.29.8

3.16+7

3.09.7

1.92.7

3.74.7

5.44+8

4.88,8

1.27.7

1.46+7

1.46+6 1.2+6*

7.58.8

5.62.8

8.52.7 3.00,7 1.45.7 1.12.6 1.08.8 8.89.7 4.36.7 4.42.7

3.74+7

3.45.7

1.42+8

4.01.7

4.01.7

0.00.0

3.40+7

3.29+7

3.45+7

1.31.8

3.19+7

3.09+7

5.88+7

3.45,7

0.00.0

3.19.7

1.04.8

3.40+7

0.*00.0

0.00.0

1.92*7 1.13.7

8.9947

9.84+6

9.64.6

1.5897

1.41.7

1.52.7 5.57.7

1.02+7

9.04.8

2.71.7

1.93+7

1.37.7

4.33.7

1.65.7

9.19,8 3.95+6

3.73+7

2.52.6

2.52+8

7.85.8

8.25+6

7.*008

2.86+7

3.47+8

2.81,8

1.34.7

1.13.7

8.15.8

2.00+7

8.42+8

4.90+5

3.34+5

5.48e5

3.89+6

3.89+5

6.12.5

8.12.5

5.30.5

1.08.6

8. 13.5

8.13+5

7.30+5

3.19.5

2.32.5

1.04.8

4.19.5

4.75+5

4.79,7 4.8eO+7

1.74.8

5.45.7

5.45.7

4.59+7

3.92+7

4.69+7

1.88.8

4.91+7

4.12.7

7.65.7

4.23+7

3.60.7

1.36.8

4.39+7

2.74.7

2.03+7

1.06+8

1.8607

1.60.7

2.74+7

2.16.7

2.87.7

9.44.7

2.31.7

1.79+7

4.49+7

3.05.7

1.95.7

7.22.7

2.87.7

1.85,7

9.14.8

7.17.7

5.19+6

5.19+8

1.72.7

1.25.7

1.87+7 8.18+7

1.15+7

8.2196

2.87+7

2.29+7

1.13,7

4.34+7

1.97+7

1.10.7

1.39.7

3.26.7

1.48.7

1.48.7

1.26+7

6.89+8

1.29.7

3.79+7

1.78.7

1.09.7

1.84.7

8.09.8

3.33.6

3.29,7

1.04.7

3.79.7 3.02.7

9.73+8 7.84*6

9.29.8 5.52.6

3.70+7 3.49.7

8.80+6 3.068

6.8086 3.0686

1.22+7 1.01.7

8.12.6 6.83+6

1.41+7 1.22.7

3.98+7 3.81+7

1.35+7 8.87,6

9.48.6 5.99.8

1.85+7 1.61.7

1.15,7 1.19+7

5.97.6 5.42+8

3.00,7 2.44+7

1.26.7 1.17+7
TABLE A4. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - VAULT STORAGE OPTION(1983 DOLLARS)(cont'd)

--------------------------------------------------------------------------------------------------------------

I LOW DEN I BEFORE CONVERSION PLANT NAME TYPE RACKS I-----------------I jNEEDED! I 6X 1O% ---- - - - -I --- I ~ - - . - - I-m 

AFTER CONVERSION 1INCREMENTAL. COST

--------- - ----------- I lox - - .. 10w

'I

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE 1

MILLSTONE 2

MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 8

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

6 QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM 1

SALEM 2

588

(a)

464

130

162

74.

48

660

(a)

448

440

140

144

144

188

241

184

278

195

(a)

18a

(a)

120

268

170

170

170

468

440

448

192

(a) 120

(a)

480

(a) 138

98

384

180

188

6.01-7 2.64.7 1.18.7 1.14.6 .8.39.7 4.21+7

9.22.6 9.32.7 3.32.7

2.21.7 2.49.7 1.78.7

0.92+7 1.34+7 2.49+7 1.47.7

0.0+80

0.00.0

3.7687

3.92.7

8.6087

3.40*7

2.41+8

1.06.8

1.11+8

3.8657 6.98+7

6.18.7 8.64+7

6.18.7

3.8387

3.04.7

3.36*7

6.20.7

1.07.8

1.94.7 6.98+.

2.10.7

1.36.7

1.68.7

2.12.7

1.38.8

4.88.7

4.34+7 1.96+7

1.89.7

1.84.7

4.62.7 2.39+7

7.43.8

1.08.7

1.73.7

1.24.7

4.43.7

1.21.7

4.94.6

7.68*6

1.386.7

8.42+7

2.6657

1.97+7

1.03+7

6.47.6

6.99+6

3.48+7

1.18.7

1.67.8

4.06+0

9.20.6

3.21.6

1.99*7

6.01.6

6.77.6

2.84.6 6.68.4

1.27+8

8.98.6

8.73+6

6.26.6

8.42.6

6.42.6

4.0656

6.13+6

7.46*6

4.88+6

3. 80.6

6.7126

8.91+6

6.86.7 6.63+7

6.12.7 808.67 2.69.8

1.38+8

1.42.8

6.96+7 8.68.7

8.92.7

7.11+7

7.72.7

6.48+7

3.86+7

3.89+7

6.41.7

1.66-.

4.18.7

2.80+7

2.81.7

1.47.8

8.14+7

7.37+7

4.29.7

3.80+7

3.68.7

4.91.7

6.11.7

1.83+7

1.67+7

2.69+7

1.80.7

8,23.7

3.13.7

1.91.7

1.8657

2.24+7

9.12.7

6.64.7

4.68+7

3.28.7

1.84.7

1.89.7

3.83+7

3.73.7

6.68+6

7.80.8

1.79+7

6.64.6

6.00+7

2.16-7

2.67+7

1.27.7

2.68.6

2.89.7

8.17.7

3.18.7

2.1687

2.76.7

2.•827

6.1126

2.80.7

2.73.7

3.69+6

6.82.6

1.27.7

4.34,7

2.16.7 2.11+7

1.16.7

7.01+6

1.5607

3.36+7

3.12.7

2.89.7

1.98.7

1.90.7

3.38.6

2.79+7

1.18+7

6.36+8

9.01+6

6.12+6

3.89+7

1.20.7

8.0..6

1.98+7

1.48.7

9.18.8

8.27+6

3.17.7

2.68.7

2.81+7

1.26.7

1.16.7

1.87.8

2.01+7

4.84+8

4.03.6

9.04.6

2. 906

3.09+7

1.19+7

1.77-7

1.06.7

4.08.8

1.60.7

1.37.7

1.26+7

1.60.7

1.62.7

8.64+8

1.34+7

1.33+7

1.89.7

3. 17.8

1.41.7

1.07.7

7. 16.6

2.80+7

2.44+7

1.24.8 8.04*7 6.66+7 8.01.6 1.64.8 9.79.7 8.76.7 3.03+7 1.83+7

6. 86.7

3.40.7

6.48.7

6.3687

6.38+7

8.88.7

4.66*7

4.82+7

6.28+7

4.37.7

4.6887

4.08.7

1.91+7

8.7687

1.97.7

1.88.7

1.78.7

2.26+7

2.10.7

1.6837

2.51+7

2.47.7

2.6807

1.12.7

2.77.7

8.68+8

8.086+8 6.61#8

1.14.7

1.08+7

4.69.0

1.60+7

1.38.7

6.42.6

6.11+6

2.70+6

8.74.6

6. 74#6

0.74.6

9.02+6

8.73*6

8.93+6

3.97.6

3.64.6

8.88.7

4.19.7

8.23*7

9.40.7

9.4837

9.43.7

6.64+7

8.13+7

8.47+7

6.3697 5. 98*7

6.91+7

2.91+7

4.28.7

4.17+7

3.98.7

3.80+7

4.08.7

3.81.7

2.79+7

8.77+7

3.68+7

4.31.7

2.12.7

3.16.7

2.10+7

1.91.7

1.73+7

2.8657

2.49+7

1.02+7

2.80+7

2.68+7

2.08.7

8.41+6

7.77+6

3.11.7

3.12.7

3.12+7

1.97+7

1.98+7

2.28+7

1.02.7

1.84.7

1.91.7

1.06.7

6.40+8

2.28.7

2.17*7

2.08+7

1.90+7

1.80+7

1.26.7

1.30-7

1.46+7

6.04.7 3.2387 1.94.7

2.98.7 1.02.7 3.66+0

4.31.6 7.26.7 6.1447

9.21+6 3.68+7 1.45.7

3.79*7 1.86.7 1.91.7

6.90+8 7.87+0 6.20.0

8.09+7

4.82+7

6.26+7

0.41.7

7.07+7

1.10.7

3.02.7

1.76*7

2.93.7

2.68.7

4.11.8

2.08+7

6.48+8

1.44.7

1.08.7

6.19.6

4.00+6

7.81.6

7.11.6

7.46+6

4.70.7

6.88*7

8,19.7

9.49.7

1.08.8

2.81.7

4.16.7

2.98+7

6.98.7

6.72.7

1.76.7

3.10+7

1.18.7

4.18.7

3.4657

1.67.7

1.28+7

2.02+7

3.16.7

3.68.7

1.77+7

1.17.7

1.27.7

3.13.7

3.14+7
TABLE A4. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - VAULT STORAGE OPTION(198I DOLLARS)(cont'd)

-- -------- - -------- ----------- - ----- - ----- - ---------- - ------ ---- - ----- ---

PLANT NAME

I |LOW DENI

TYPE RACKS I.

.NEEDED ... ILO DNI'

BEFORE CON•

sexI

fERSION FAIYG. AFTER Co VERSION

~10% 110 I.....

-I- NCREMENTAL COST

I~ ex s Ilo1o •Im•N•ml•o•w•m --------------------- I--------I-------------"-----

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH 1

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSQUEHANNA I

B SUSQUEHANNA 2

THREE MILE ISL

TROJAN

E ThRKEY PT 3

E TURKEY PT 4

B VOCTLE I

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION I

A ZION 2

TOTAL

P

P

P

P

P

B

P

P

P

ip

P

P

P

P

P

P

270

(a)

240

(a)

388

104

104

152

144

138

159

(a) 890

148

98

144

(a)

252

(a)

264

812

176

240

(a)

152

78

218

(a)

8.83+7 4.81.7 2.82.7 9.58.6 1.29.8 8.49#7 8.17+7

7.91.7

1.57#8

8.78+7

3.09.7 3.019÷7

8.654*7

8.27.7

5.18+7

2.89.7

1.6.8÷

2.9"+7

8.24.7 8.*14.7

1.89.9

8.55.7

9 *82.7

8.36.7

3.2453. 1.63+8

3.65+7

2.99+7

7.00+7

2.04.7

7.46.7

1.95.7

4.358.

4.1".8

4.82.7

2.8307

1.42+7

7.00.8

0.02+7

9.89.6

1.14.7

1.2.+7"

4.01+7

I .64.7

4.08.7

5.54+7

1.63+7

2.38+7 1.a8+7

6.94+8

3.94.7

8.25+0

8.72+5

8.11.6

3.49*7

9.29+6

4.21+6

1.82+8

2.5667

3.32+8 4.28.6

5.03+6

1.29+7

7.07+6

1.87.7

6.1128

2.23+7

4.53+8

6.47+8

2.03+7

5.74+5

1.06+6

7.38÷6

5.51.5 5.46÷6

6.52.5

5.2655

8.0565

7.03.5

1.81.8

8.54.5

4.37÷5 8.39÷5

1.11+8

6.58,5

8.9065

1.08+8

8.77+5

1.86+5

9.64+6

1.09.8

2.10.9

8.6887

4.41.7 4 • 88.7

8.11.7

8. 75.7

7.06+7 8S. 82.7

1.96+8

3.94+7 4.67+7

5.07.7

1.89.8

4.88+7

1.17.8

9.48.7

2.0898

8.48.7

8.45.7

1.09+8

8.81÷7

1.29+8

9.22*7

8.1.8+

7.67.0

4.81.7 3.02.?

1.28.+7

9.22.7

1.86.7

2.0847 2.69.7

8.*97.7

2.71.7

569.87

4.04.7

9.92.7

8.31.7

2.86+7

7.49+7

1.59.7

7.92.?

1.35+?

1.88+6

1.47.8

4.14.7

2.75.7

1.88.?

4.54+8

4.88.7

9.41.6

9.99+6

1.49.7

2.90.7

1.82+7

*.12.7

1.94+7

5.41.7

1.46.7

1.45+7 5.42.7

8.00+7

5.88.7

2.02.7

1.88.7

1.36+783+7 1.68.7

2.53+7 2.66+7

1.01+7

4.05+7

9.19+6

1.38+7

1.99.7

5.19.7

1.1S+7

1.95.7

3.19,7

5.62.7

2.92+7

4.84+8

4.02÷7

1.9.*7

4.89.?

1.82.7

4.80."

4.08+0

1.04.7

2.37.7

1.86.7

6.52+.

9.59+6

9.84.6

1.5637

3.07.7

1.23.7

1.70÷7

2.23+7

4.49.7

1.85.7

1.01.7

8.91.7

1.08.7

3.99.7

7.79-6 1.50.68

1.40.6

7.08+0

1.89.7

9.65+6

3.42.8

2.44.7

8.75.6

8.20+6

1.05.7

1.73.7

9.84.6 1.32+7

1.40+7

8.29.7

1.06÷7

1.02.7

3.48.7

3.73.? 3.98.7 3.65.7

----------------- ----------------------- ----------------------------------------------------

8.25+9 2.62.9 1.3809 8.50+7 8.43+9 4.85.9 2.82+9 2.24+9 1.80+9 1.3889

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(I) INCLUDED IN UNIT I
TABLE A4a. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - VAULT OPTION

(1983 DOLLARS)

ADD. YEAR C OST SHUTDOWNISTORAGEI WHEN I CONS. ....... I..... I....... I............

YEAR REq'D ADDIL TIME CONSTRCTION I 0 8 U I TOTAL (ASSEM- STOR. (MON.) -- - - - - - - - - -- -- - - - - - - - - - - I - - - - - - - - - - - BLIES)NEEDED % I 5 1 o % I i S I 6% 110%

ARK NUCLEAR 1 2008 a77 1996 48 2.88.7 1.6537 8.34*6 0.20+8 2.43+0 1.02.6 3.60+7 1.77-7 9.3868

ARK NUCLEAR 2 2012 G65 1999 48 3.19+7 1.48+7 8.938+ 7.50,6 2.48.4 8.92+6 3.94+7 1.71.7 7.82+6

BEAVER VALLEY 1 2016 836 1998 52 4.28+7 2.27+7 1.24+7 1.81+7 5.31.0 1.98.0 6.89+7 2.80+7 1.44+7

BEAVER VALLEY 2 2028 8a8 2009 62 4.26+7 1.20+7 3.68.6 1.8307 2.64+6 6.38*6 6.82+7 1.46+7 4.12+8

BELLEFONTE 1 2028 1900 2009 68 7.07+7 2.10+7 8.43+8 2.74+7 4.90.8 1.01.6 1.04,8 2.66.7 7.44+6

BELLEFONTE 2 2030 1900 2011 68 7.67+7 1.98.7 6.32.0 2.74.7 4.46+6 8.37.6 1.04.8 2.41+7 0.16+6

BIG ROCK 1 2001 96 1996 48 2.88+7 1.680+7 9.18.8 3.10+0 1.48.4 7.17+6 a.19+7 1.75.7 9.90+8

A BRAIDWOOD 1 2028 3827 1998 87 1.28+8 8.80+7 3.72+7 7.32.7 1.99+7 6.88+6 2.01+9 8.79+7 4.39.7

A BRAIDWOOD 2 2027 (a) 0.08+0

B BROWNS FERRY 1 2014 3228 2002 58 6.67+7 2.20*7 9.10.6 1.28.7 3.78.8 1.18+8 6.86*7 2.67+7 1.03.7

B BROWNS FERRY 2 2014 (a) 0.0.+0

BROWNS FERRY 3 2017 2441 2001 64 4.60.7 1.91+7 8.28.8 1.39+7 3.92+6 1.23+6 6.99.7 2.30+7 9.61.8

BRUNSWICK 1 2010 2401 1990 64 4.67+7 3.2657 2.34+7 1.73+7 7.66+8 3.77+0 8.30+7 4.02+7 2.72+7

0.00+0

BRUNSWICK 2 2010 2281 1991 63 4.40.7 2.98+7 2.05+7 1.67.7 6.7+86 8.23.6 6.97+7 3.68+7 2.37+7

0.00+0

A BYRON 1 2024 3827 1994 87 1.28.8 7.60+7 4.60+7 7.32+7 2.19+7 8.06+6 2.01.8 9.69+7 5.31+7

A BYRON 2 2028 (a) 0.00+0

' CALLAWAY 1 2024 1129 2006 66 4.93*7 1.6887 6.06*8 1.78.7 3.87.6 9.62+6 6.71+7 2.07.7 7.01+6

B CALVERT CLF 1 2014 2213 1992 68 7.62.7 4.91+7 3.23+7 3.18+7 1.22+7 6.34+8 1.08,8 6.13.7 3.76,7

B CALVERT CLF 2 2016 (a) 0.00+0

CATAWBA 1 2025 0 2026 0 0.0080 0.00.0 0.00+0 0.00.0 0.00.0 0.00+0 0.00+0 0.00+0 0.."+0

CATAWBA 2 2026 0 2026 0 0.000 0.00.0, 0.00.0 0.00+0 9.00+0 0.00.0 0.00+0 0.00.0 0.00+0

CLINTON 1 2027 2672 200 66 4.76+7 1.66+7 6.30+. 1.89+7 3.78.8 8.70.6 6.64.7 1.93.7 8.17.8

B COMANCHE PK 1 2030 2087 2016 89 8.40.7 1.78+7 8.98.0 2.3657 3.42.8 5.8.+6 1.08.8 2.10+7 4.66+8

B COMANCHE PK 2 20830 (a) 0.00+0

A COOK 1 2009 1241 1998 67 6.39.7 2.69+7 1.29.7 1.13.7 4.11.6 1.6800 6.62+7 3.00+7 1.46+7

A COOK 2 2009 (a) 0.00.0

COOPER STN 2008 1238 1997 47 3.1227 1.58+7 8.2286 6.20.8 2.87+6 9.6655 3.74+7 1.82+7 9.19+6

CRYSTAL RVR 3 2018 432 2005 47 2.88+7 9.85+6 3.648 5.688+0 1.47+. 4.1256 3.4657 1.13+7 3.96+6

DAVIS-BESSE 1 2017 2490 1996 76 1.01+8 6.61+7 3.21+7 4.10.7 1.37+7 6.21.6 1.42+8 6.98.7 3.73+7

DIABLO CANYON 1 2026 617 2011 48 3.20+7 8.17+8 2.22+8 8.1.86 1.47+8 2.97+6 4.01+7 9.64*6 2.62+6

DIABLO CANYON 2 2026 617 2011 48 3.20.7 8.17+8 2.22+6 8.13.6 1.47.6 2.97+6 4.01.7 9.84+8 2.62+6

DRESDEN 1 1984 0 0.00+0

DRESDEN 2 2008 1016 1998 46 2.88+7 1.39+7 6.890+ 6.16+6 1.92+0 7.88+6 3.40*7 1.66+7 7.66+0

DRESDEN 3 2008 893 2000 48 2.88.7 1.26+7 6.70.8 4.13+6 1.4686 6.46+6 3.29+7 1.41.7 6.26+5

DUANE ARNOLD 2010 998 1999 48 2.86*7 1.32+7 6.27+8 6.68.6 1.97.6 7.3056 3.4657 1.62+7 7.00+6

ENRICO FERMI 2 2026 6366 1997 70 8.83+7 4.30+7 2.27+7 4.60+7 1.21+7 3.94+8 1.31+8 6.67+7 2.6807

FARLEY 1 2012 298 2000 46 2.88+7 9.38+6 3.22+6 3.10+8 8.68+5 2.61+6 3.19,7 1.02+7 3.47+8

FARLEY 2 2012 140 2088 48 2.88+7 8.60+6 2.8088 2.07.8 6.41+6 1.6156 3.09.7 9.04+8 2.81.6

FITZPATRICK 2016 2246 1997 65 4.39+7 2.22+7 1.16+7 1.49+7 4.88.0 1.78+6 6.88+7 2.71.7 1.34+7

FORT CALHOUN 2008 413 1994 48 2.88*7 1.6887 1.01.7 6.68.6 2.61+0 1.18+6 3.46+7 1.93.7 1.13+7

FT ST VRAIN 2007 0.00+0

GoNNA 2088 219 2000 48 2.88.7 1.28+7 6.70.0 3.18,6 1.14+6 4.46+6 3.19+7 1.37+7 8.16+6

GRAND GULF 1 2022 4392 1998 64 7.13.7 3.48.7 1.71.7 3.24+7 8.98+6 2.9080 1.04+8 4.33+7 2.00+7

HADDAM NECK 2007 819 1997 48 2.88*7 1.46+7 7.68+0 6.16.8 2.01+0 8.38+6 8.40.7 1.66.7 8.42+8

HARRIS 1 2028 0 2020 0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0 0.00+0

- - 0.00+0
TABLE A4a. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - VAULT OPTION

(19893 DOLLARS) (cont*d)

--------------------------------------------------------------- !------------------------------------------------

ADD. YEAR C 0 S T

SHUTDOWN STORAGE WHEN CONS. - w- "-.........-I-.....-------- .

PLANT NAME YEAR REQD ADD'L TIME CONSTRCTION I 0 a U I TOTAL

(ASSEM_ STOR. (MON.) -- ; ------ BLIES)NEEDED 1 -%1 -o, I e i 5%

eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee--- ------

B HATCH 1 2009 2874 2000 s6 5.18*. 2.24.7 1.02+7 8.80,6 A.03,8 1.11.6 6.01.7 2.54.7 1.18.7

8 HATCH 2 2012 (0) o.0o+o

HOPE CREEK 2028 2920 2007 s6 5.09.7 1.68+7 5.16.8 1.84+7 3.82+8 8.22.5 8.92#7 1.94.7 5.98.6

HUMBOLDT BAY 1978 0 -. 0*00

INDIAN PT 1 1998 a0.00.0 -

INDIAN PT 2 2006 493 1994 47 3.0997 1.81.7 1.08.7 8.70.6 2.89.6 1.3.68 3.7867 2.1207 1.21.7

INDIAN PT 3 2016 536 2004 48 3.27.7 1.17+7 4.42.8 6.54.6 1.77.8 5.22.5 3.02+7 1.3567 4.94.6

KEWAUNEE 2014 579 1999 47 3.05.7 1.40,7 6.65.8 8.2686 2.62.6 9.12.5 8.88.7 1.8667 7.68+8

LACROSSE 2002 205 1992 47 2.89.7 1.8867 1.22.7 5.1868 2.57.6 1.35+6 8.40.7 2.12.7 1.3867

B LASALLE CTY 1 2022 9824 1990 95 1.49.8 1.01.8 7.01+7 9.24.7 3.24.7 1.41+7 2.41+8 1.83.5 8.42.7

B LASALLE CTY 2 2023 (a) 0.00.0

LIMERICK 1 2024 4096 1995 63 8.81.7 3.79*7 2.17.7 3.76,7 1.09.7 3.86.6 1.06.8 4.88.7 2.56.7

LIMERICK 2 2029 4236 1998 84 6.97+7 3.38+7 1.67.7 4.10.7 9.91.8 3.00.6 1.11+8 4.34.7 1.97+7

MAINM YANKEE 2008 682 1996 47 8.1867 1.8897 9.15,6 8.88,8 2.89.6 1.1386 3.85+7 1.95.7 1.03.7

UCCUIRE 1 2021 96a 2005 54 4.59.7 1.57+7 5.84+6 1.39+7 8.21.8 8.34+5 5.98+7 1.89+7 8.47.8

MCGUIRE 2 2023 989 2006 64 4.88,7 1.52+7 5.20,8 1.60+7 3.24.6 7.90.5 8.18+7 1.84+7 5.99+6

MILLSTONE 1 2010 2480 1987 54 4.66.7 3.8667 2.96+7 1.98+7 9.68.8 5.2386 8.54.7 4.62+7 3.48,7

-, MILLSTONE 2 2015 828 1997 51 8.8987 1.96.7 1.02.7 1.30+7 4.2568 1.56+8 5.18.7 2.89.7 1.18.7

, MILLSTONE 3 2025 541 2018 46 8.29.7 6.586+ 1.42.8 5.8836 8.49*5 1.48.5 3.83+7 7.43.6 1.57.6

MONTICELLO 2007 355 2004 48 2.88+7 1.0387 3.89.8 1.55.6 5.05+5 1.74+5 3.04,7 1.0987 4.086.

NINE MILE PT 1 2005 884 1998 48 2.98.7 1.53+7 8.34.6 4.65,8 1.95.6 0.81.5 3.38+7 1.7387 9.20.8

NINE MILE PT 2 2026 1971 2011 61 4.06*7 1.04*7 2.81.6 1.14+7 2.00+6 3.99+5 5.20,7 1.24.7 8.21.6

A NORTH ANNA 1 20918 186 1999 87 7.89*7 3.81+7 1.72.7 2.81.7 8.20.8 2.70+6 1.07.8 4.43.7 1.99.7

A NORTH ANNA 2 2020 (a) 0.00.0

A OCONEE 1 2013" 2102 1989 70 8.57.7 8.39+7 4.84.7 3.84.7 1,6857 8.11.6 1.24+. 9.04.7 5.65.7

A OCONEE 2 2013 (a) 0.00.0

OCONEE 8 2014 1021 1991 65 4.77*7 8.23.7 2.22.7 2.08.7 8.26.8 3.75.6 6.85+7 4.06*7 2.8607

OYSTER CRK 1 2004 912 1994 46 2.88.7 1.68.7 1.01.7 5.16.6 2.93.6 1.11.6 3.40+7 1.9147 1.12.7

PALISADES 2011 835 1988 s0 3.84.7 8.01.7 2.38.7 1.64.7 7.52.8 3.92,6 6.48.7 3.76.7 2.77.7

PALO VERDE 1 2024 1117 2005 64 4.88,7 1.80,7 5.75.6 1.8.+7 8.6868. 9.10.5 6.36+7 1.97.7 8.8868

PALO VERDE 2 2025 1121 2006 64 4.89.7 1.63.7 5.23,8 1.69+7 3.49.8 8.30.5 6.38.7 1.88.7 6.06.6

PALO VERDE 3 2026 1121 2007 54 4.89+7 1.45,7 4.7686 1.89.7 3.33.8 7.64.5 6.38.7 1.7897 5.51.6

PEACHBOTTOM 2 2009 1812 1997 50 3.67+7 1.95+7 1.02,7 7.89.8 3.01.8 1.23+8 4.88.7 2.25.7 1.14.7

PEACHBOTTOM 3 2008 1689 1997 49 3.69.7 1.82.7 9.46*6 7.2866 2.77,+ 1.13+8 4.32+7 2.10.7 1.08*7

PERRY 1 2028 2548 2009 55 4.75*7 1.34+7 3.98.6 1.53+7 2.8686 6.06.5 6.28.7 1.63.7 4.59.6

PILGRIM 1 20098 1512 1993 40 3.43.7 2.11.7 1.32.7 9.4086 3.99+6 1.84+8 4.37+7 2.51+7 1.50+7

A POINT BEACH 1 2007 849 1995 50 3.81+7 2.12.7 1.21.7 8.4686 3.48.8 1.53+6 4.6867 2.47.7 1.3867

A POINT BEACH 2 2008 (a) 0.00.0

A PRAIRIE ISL 1 2008 1142 1993 53 4.40.7 2.70,7 1.70,7 1.24+7 6.28.6 2.43.8 5.84.7 3.2387 1.94.7

A PRAIRIE ISL 2 2008 •a) 0.00.0

B QUAO'CITIES 1 2007 A08 2005 46 2.88.7 9.8486 8.64+8 1.0386 3.28+5 1.10.5 2.98+7 1.02+7 8.5.68

B QUAD CITIES 2 2007 (a) 0.00.0

RANCHO SECO 1 2008 228 2004 46 2.86.7 1.03+7 8.89.8 2.07,8 8.67.5 2.21+5 3.09*7 1.10,7 4.11.8

ROBINSON 2 2007 688 1990 49 3.52+7 2.50.7 1.81+7 1.10,7 6.17,6 2.6.+8 4.62+7 3.02,7 2.08.7

RYR BEND I 2025 2462 2007 54 4.6867 1.44,7 4.78.6 1.59.7 3.20.8 7.34.5 6.25+7 1.76,7 5.4868

SALEM 1 2016 1007 1997 54 4.71.7 2.88,7 1.24,7 1.70.7 5.45+6 1.9768 6.41.7 2.93.7 1.44.7

SALEM 2 2020 1183 2001 57 5.19.7 2.16+7 9.33+6 1.88.7 4.9686 1.49.6 7.07.7 2.8667 1.08.7
TABLE A4a. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - VAULT OPTION

(1983 DOLLARS) (contd)

ADD. YEAR C 0 S T ISHUT)OWHISTORAG WHEN ICONSI. I .....

PLANT NAME YEAR REQ'D ADD*L TIME CONSTRCTION I 8 S u TOTAL

(ASSEM- STOR. (MON.) ----------------------- I ------------------

BLIES) NEEDED o% 61 I 1% I JI I 10 15% 11o

E SAN ONOFRE 1 1999 2382 1996 67 7.75.7 4.32.7 2.47+7 6.8360 2.88+6 1.47,6 8.33+7 4.81+7 2.62.7

E SAN ONOFRE 2 2012 (a) 0.00.0

E SAN ONOFRE 3 2013 0.00+0

SEABROOK 1 2031 1281 2008 58 6.60+7 1.82+7 5.08+0 2.41+7 4.18.6 8.81+5 7.91.7 2.04,7 6.94+8

A SEQUOYAH 1 2021 2880 1995 78 1.80.8 6.89#7 3.37.7 6.10.7 1.57.7 6.72+8 1.57.8 7.48.7 3.94*7

A SEQUOYAN 2 2022 (a) 0.00+0

SHOREHAM 2827 2036 2008 66 4.81.7 1.67.7 6.37.0 1.92+7 3.81+6 8.82+5 6.73*7 1.96,7 6.26*5

SOUTH TEXAS 1 2027 268 2023 46 2.88+7 4.09.8 6.3865 2.07.0 2.00.6 3.62+4 3.09+7 4.3656 6.72.6

-SOUTH TEXAS 2 2028 268 2824 40 2.88+7 3.90#8 6.78+6 2.07+0 2.48+6 3.29+4 3.09+7 4.16+8 6.11.6

ST LUCIE 1 2010 1182 1987 64 4.68+7 3.68*7 2.97+7 1.98.7 9.6706 6.23+8 6.64+7 4.62+7 3.49.7

ST LUCIE 2 2023 1120 2001 63 4.43.7 1.84.7 7.97.8 1.64+7 4.67*6 1.32+6 6.27+7 2.30+7 9.29+6

SUMMER 1 2024 761 2"8 61 3.98.7 1.19.7 3.67.6 1.18.7 2.37+6 6.3656 6.16+7 1.42+7 4.21+8

A SURRY 1 2012 97 2012 46 2.88+7 7.00+d 1.82.6 0.00+0 0.08+0 0.00+0 2.88+7 7.00.6 1.82.6

A SURRY 2 2013 (a) 0.00+0

B SUSQUEHANNA 1 2022 7288 2000 80 1.11+8 4.84+7 2.19.7 4.64.7 1.18.7 3.68.6 1.568+8 6.02.7 2.6657

B SUSQUEHANNA 2 2024 (a) 0.00.0

THREE MILE ISL 1 2008 76 200 46 2.88+7 9.38.8 3.22+0 1.03*8 3.13.6 1.00.5 2.98.7 9.0906 3.32*8

TROJAN 2011 373 2004 46 2.88.7 1.03+7 3.89+8 3.61.8 1.07.6 3.40+6 3.24.7 1.14,7 4.23+6

E TURKEY PT 3 2007 884 2002 46 2.8807 1.14+7 4.71.6 2.65*8 8.86*6 3.20+6 3.14+7 1.23+7 6.63+8

E TURKEY PT 4 2007 (a) 0.00+0

B VOOTLE 1 2027 2496 28" 76 9.94+7 3.24.7 1.11+7 3.87+7 7.69.8 1.78,6 1.38+8 4.01+7 1.29+7

8 VOOTLE 2 2028 (a) 0.00+0

VT YANKEE 1 2012 1088 1999 48 2.88.7 1.32.7 6.27+6 6.71.0 2.22.6 7.98+6 3.5657 1.64+7 7.07+6

WASH NUCLEAR 2 2023 4018 1998 63 6.6087 3.20.7 1.69.7 3.1687 8.67*6 2.7650 9.82+7 4.00+7 1.87+7

WATERFORD 3 2024 1143 200 66 4.74+7 1.64.7 6.29.8 1.62.7 a.42+6 8.23+6 6.38+7 1.88.7 6.11+8

A WATTS BAR 1 2026 2691 2W01 78 1.00.8 4.41.7 1.91.7 4.72.7 1.13.7 3.18.6 1.53.8 6.64.7 2.23.7

A WATTS BAR 2 2027 (a) 0.00.0

WOLF CREEK 1 2025 867 2"08 62 4.27.7 1.26.7 3.94+8 1.3487 2.67+8 6.94,5 6.63,7 1.6587 4.65*6

YANKEE-ROWE 1 2001 30 1999 48 2.88+7 1.32+7 6.27+0 1.03.0 4.40+6 1.96,6 2.98.7 1.36,7 6.47+8

A ZION 1 2008 1296 1995 68 5.61.7 3.12+7 1.79.7 1.39+7 6.60+6 2.42+6 7.00+7 3.6887 2.03+7

A ZION 2 2000 (a) 0.000.

------------- ------------------------------------------------------------------------------------

TOTAL 4.67.9 2.15.9 1.13.9 1.58.9 4.6868 1.70+8 0.25.9 2.62+9 1.38+9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS& CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1
TABLE A4b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - VAULT OPTION

(1983 DOLLARS)

---------------------------------- aaaaaaaaaaaaaaaaaaaaaaaaaaaaaaa------------------ - -

A

A

B

B

A

A

B

B

B

A

A

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BG ROCK 1

BRAIDWOOD I

BRAIDWOOD 2

BROWNS FERRY 1

BROWNS FgRRY2 BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

BYRON I

BYRON 2

CALLAWAY 1

CALVERT CLF 1

CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

COMANCHE PK 1

COMANCHE PK 2

COOK 1

COOK 2

COOPER STh

CRYSTAL RVR 3

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND GULF 1

HADDAM NECK

HARRIS 1

20•8

2012

2016

2028

2029

2030

2001

2028

2027

2014

2014

2017

2010

2010

2024

2028

2024

2014

2016

2025

2028

2027

2030

20380

2009

2009

2008

2028

2017

2025

2025

1984

20089

2008

2010

2025

2012

2012

2016

2008

2007

2006

2022

200"

2028

737

973

1267

1296

2404

2404

175

4398

3153

3033

4413

(a)

1883

2789

(a)

228

210

3280

2881

(a)

2009

(a)

1702

648

2850

772

772

1647

1325

1510

8459

7T8

548

2988

83a

411

5464

631

0

(b)

1989

(b)

2000

2002

199

1990

1998

1998

1995

(b)

(b)

1996

2021

2023

2000

2010

2016

1991

1991

1993

1999 1988

2096

2006

1992

1994

1991

1990

1997

1999

1991

(b)

1994

1992

1990

2026

51

58

S8

B8

78

78

46

98

a6

59

58

57

97

62

78

46

48

58

77

a8

o0

60

81

51

51

49

47

49

78

5s

48

57

48

48

76

48

0

3.93+7

4.8657

5.6557

6.59*7

9.49+7

9.49+7 2.88.7

1.64.8

7 * 9*7

7.50+7

5.73.7

6.49+7

5.*30+7

1.55.6+

a.92+7

9.40+7

2.88+7

2.88+7 6.60.7

1.05+8

3.75+7 8.06.7

1.18*8

4.82+7

4.02+7

8.55+7

3.13+7

8.48+7

1.02+8

3.84+7

3.33+7

6.25+7

3.28+7

2.88+7

8.70+7

3.35,7

8.00.+

8.08+7

3.24+7

4.35+7

2.44+7 4.24+7

3.75+7

1.86+7

1.04+8

3.61+7

3.19.7 4.30+7

4.16.7

1.04,8

8.46+7

8.98.7

4.5128

4.09.8

2.44.7

2.82+7

I,.49*7

2.30.7

1.88+7

8.13*7

1.31+7

1.31*7

2.29+7

1.88.7

2.86+7

7.24+7

1.94+7

1.53+7 3 .55.7

2.58+7

1.68+7

5.81+7

2.38.7

0.0+00

2.44+7

2.45+7

8.45.7 1.11.7

1.8127 1.00÷7

31.2+7

3.29.7

7.14.7

1,•89.?

1.99+7

5.25.7

7.70+5

8.88+6

1.11+7

8.02+6

3.78.7

1.46+7

7. 98+8

5.94+7

4.49+8

4.49+8

1. 50+7

1.10.7

1.62+7

5.23+7

1.01*7

7.25+6

2.46+7

2.M+7

1.01+7

3.89+7

1.72+7

0 .00+0

1.4867

1.88+7

2.97+7

2.77#7

4.99+7 4.98+7

4.865+8

1.07+8

2.28+7

2.41+7

2.80+7

2.22+7

1.07+8

3.47+7

4.93+7

2.07+6

1.55+6

2.89+7

3.90+7

2.7837

1.04.7

1.14+7

6.11+7

1.48+7

1.43+7

1.04+7

7.91+8

1.21+7

8.61+7

1.07+7

7.86.8

2.40+7

9.95+6

6.20+8

4.86.7

1.04+7

0.00,+

7.13.8

8.238+

1.24.7

8.89+6

1.14+7

1.04*7

2.37.8

3.49÷7

7.37+6

8.02+8

1.08+7

1.04.7

3.87+7

9.80+6

1.96.7

2.87.6

2.00+5

6.83+8 6.50.6

1.20.7

4.41+6

8.48+6

.2.5607

2.95+6

2.9568

4.54+8

3.27+8

5.21.6

2.20*7

8.73+8

2.61+6

9.85+68

6.17+8

2.69+6

1.81.7

4.8998

8.88+6

4.10+8

8.13+6

1.93+8

8.24+6

2.88+8

1.28+6

1.47+7

2.65+6

3.06+8

8.7*+6

1.79+7

3.34+8

9.92+8

4.38+4

2.04+4

1.95.6

1.27+6

9.81+.

2.03+6

1.18+8

1.23+7

7.01*5

7.01+6

2.18+8

1.46+6

2.48.6 9.84.8

1.438*6

9.37+5

4.20+6

2.91+6

1.23+6

8.4816

2. 51.8

5.3097

8.2B+7

8.52*7

8.38+7

1.44+8

1.44.8

3.85+7

2.81+8

9.78+7

8.14+7

7,79+7

7.52+7

2.62+8

9.99+7

1.39+8

3.09+7

8.04+7

8.49*7

1.44.8

1.08.8

4.79.7

4.80+7

1.74+8

6.45+7

6.46+7

4.59+7

3.92+7

4.69.7

1.88+8

4.91+7

4,12+7

7.85+7

4.23.7

8.50+7

1.86+8

4.89+7

3.79+7

4.08+7

5.69+7

8.11+7

5.28+7

4.79,7

2.10+7

1.69+9

4.86*7

8.99.7

6.88+7

5.19.7

1.438+

4.44+7

8.94+7

4.80+8

4.20+8

8.12+7

8.47+7

8.88.7

2.74+7

2.08+7

1.06*8

1.80+7

1.80+7

2.74+7

2.16+7

2.87.7

9.44+7

2.31+7

1.79+7

4.49+7

3.05+7

1.95+7

7.22+7

2.87+7

2.8837

2.88.7 4.08.7

1.30*7

2.20+7

1.82.7

1.3547

8.59+7

2.07+7

2.14.7

3.98+7

8.84+7

8.98.7

2.2247

6.24+7

8.14+5

8.04*5

1.31.7

9.29+8

4.38+7

1.65.7

9.14+6

7.17*7

6.19+6

5.19+8

1.72+7

1.25+7

1.87+7

6.18+7

1.15+7

8.19.8

2.87+7

2.29+7

1.18+7

4.34+7

1.97+7

0.000+ 0.0
TABLE A4b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO'LOW DENSITY RACK CONFIGURATION - VAULT OPTION

(1983 DOLLARS)(cont'd)

-------------------------- m----- ------------- m--------------- m--------- m------ -- m----

ADD. YEAR

SHUTDOWN STORAGE WHEN CONS. - -------------------- PLANT NAME YEAR REQ'O ADDIL TIME CONSTRUCTION

(ASSEU- STOR. (LMON.) ------------ m.-------. BLIES) NEEDED ox I 65 I 1x -------------------------------- -- -.-.. ------.

C OST

a 8 . TOTAL-.--- ---.

I e0 I 65 I 105 0% I 55 I 10i

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT a

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CrY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE I

MCGUIRE 2

MILLSTONE 1 co MILLSTONE 2

D MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE a OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

P.ACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM 1

SALEM 2

2009

2012

2028

1978

1980

200

2016

2014

2002

2022

2823

2024

2029

2006

2021

2023

2010

2016

2026

2007

2006

2028

2018

2020

2013

2013

2014

2004

2011

2024

2026

2020

2008

2008

2826

2080

2007

2008

2008

2008

2007

2007

2008

2007

2025

2016

2020

4860

901

992

8e1

301

11144

(a)

4992

5116

1070

1397

1421

2872

1291

1046 835

1252

2533

2461

(1)

2841 • (a)

1424

1039

1627

1631

1031

2724

2489

3444

18ss

1137

(6)

1483

(a)

640 958

3220

1487

1667

1998

1996

2001

(b)

1994

1993

1987

1988

1991

1987

1997

1998

2007

1998

1990

2087

1992

1992

1989

(b) 1998

1997

1908

1991

1991

2003

1988

1990

1990

1988

1988

2002

2002

1992

(b)

2001

1989

1992

63

61

64

60

47

182

68

69

62

80

60

58

so

66

48

47

64

78

77

60

48

63

61

81

61

66

64

60

61

63

57

48

49

53

58

61

64

8.7317 8.5727 1.9147

8.31.7 2.62,7 1.14.7

1.68+7 6.3868 2.83.8

3.01.7 7.04+6 1.98.6

88. 887 4.21.7 2.21.7

9.32.7 8.32+7 1.34+7

4.87.7 4.67+7

3.89.7

2.88.7

1.84.8

8.15.7

8.28.7

4.27.7

6.9657

8.04.7

6.01,7

6.10.7

4.83.7 2.88.7

3.08+7

4.71.7

1.01.8

3.43,7

2.73+7

2.2867

2.37+7

1.08,8

6.1867 6.80+7

3.44,7

3.01.7.

2.90.7

3.93.7

4.00.7 1.60+7

1.30.7

2.18.7

1.48.7

0.6*57

2.71.7

1.64,7

1.42+7

1.97,7

7.28+7

4.72+7

3. 88.7

2.81+7

1.67+7

1.44+7

3.11,7

3.17+7

4.90+6

6.89+8

1.57.7

4.78.8

4.27*7

1.48+7

1.88#7

1.43.7

7.76.8

1.06+8

6.49+7

6.88.7 1.88.7

2.73+7

2.88.7

2.10+7

2.62.7

1.86.7

4.8658

8.29+8

1.70,7

4.86+7

7.64.8 8.83+8

6.3658

4.41+8

3.91+7

1.98+7

1.77,7

8.46+8

7.92,6

7.80.8

9.83+8

1.11+7

8.32.8

1.77.6

4.08.8

3.35,6

.1.73+7

4.19.8

2.68.8 2.28+8

2.88+8

1.84.7

9.17+6

7.03+6

4.73.6

2.69.8

2.6*06

6.19.8 6.67*6 7.57.6

7.12.5

2.18.8

7.68+6

7.2658

6.86+7

6.63,7

6.12.7

3.68.7

2.89.8

1.38.8

1.42.8 6.96+7

8.68+7

8.92.7

7.11,7

7.72.7

6.48+7

8.89+7

6.41.7

1.60.8

4.18,7

3.39.7

2.80*7

2.81.7

1.47*8

8.14,7

7.37+7

4.29.7

3.68.7

4.91+7

6.11+7

1.83+7

1.57.7 2.69+7

1.80.7

8.23.7

1.05.8 7.64.7 5.68+7 4.88.7 2.1657 1.10.7 1.64.8 9.79+7

5.92+7

3.29.7

4.3657

6.13,7 8. 16*7

8. 16*7

4.94+7

4.64+7

6.89+7

3.90+7

4.61.7

4.64.7

2.4657

3.41.7 3.26*7

3.10.7

2. 98.7

3.34+7

3.14.7

2.22.7

3.08.7

3.20,7

3.87+7

1.88.7

2.70.7

1.78+7

1.62.7

1.47+7

2.38.7

2.1687

8.76+8

2.42+7

2.31,7

2.94.7

8.98.8

1.88.7

3.27+7

3.29+7

3.28*7

1.88.7

1.49.7

2.68.7

1.46,7

1.4657

1.27.7

4.83.8

8.86+8

9.24+8

8.82.8

0.48*6

7.17.8

6.70*6

6.71*8

7.07,6

8.82.8

8.43+8

2567.6

4.61.8

3.16.8

2.87+6

2.81.6

3.51+8

3.28.6

1.48.8

3.83+6

3.60+8

8.80+7

4.19.7

8.23.7

9.4087

9.43.7

9.43.7

6.13+7

8.47+7

6.56,7

6.98+7

S. 91.7

2.91.7

4.28+7

4.17.7

3.98*7

3.8607

4.08.7

3.81.7

2.79.7

3.77*7

3.88.7

3.13+7

1.91+7 1 • 65.7

2.24.7

9.12.7

5.84.7 4.68+7

3.28.7 1.64,7

1.69.7

3.8637

a.73+7

6.86,6 7.60.6

1.79.7 6.64+6

6.00.7

8.76.7

4.31.7

2.12.7 3.16+7

2.10.7

1.91.7

1.73.7

2.65.7

2.49,7

1.02.7

2.80+7

2.68.7

3.79,7

5 .90.8

1.78,7 3 .10,7

1.•18,7

4.18,7

3.46.7

5.2657 4.12,7 3.28+7 2.80+7 9.78.6 6.30+8 7.26+7 6.10.7

3.37+7

8.83+7

4.32.7

5.62+7

8.27+7

6.91+7

1.34.7

2.34.7

3.38+7

2. 34+7

4.68.7

4.48.7

6.62.6

1.64.7

2.68.7

1.01,7

2.64*7 2.93+7

3.08.8

1.07.7

1.64+7

2.67.7

3.22.7

3.67+7

1.*60.

4.67+8

7.88.6

0.1658 1.36+7 1.28.7

3.81.5

2.22+6

4.21.+

1.738.6

8.22.8

5.17+8

3.88+7

4.70.7

6.88.7 9.19.7

9.49,7

1.08,8

1.4657

2.81+7

4.16.7

2.98+7

5.98.7

6.72+7
TABLE A4b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - VAULT OPTION

(1983 DOLLARS) (cont'd)

ADD. YEAR COST

SHUTDOWN STORAGE WHEN CONS.------------- m---------- -

PLANT NAME YEAR REq'D ADD'L TIME CONSTRUCTION I 0 8 TMT

(ASSEII- STOR. (MION.) ---- 5Io - -e -- 5x------x NEEDEI Dl 0LS I S 10 I I IlO

---------- -------- ------- ------ ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

E SAN ONOFRE 1 1999 8172 1989 76 1.01+0 7.41+7 5.52+7 1.87+7 1.09+7 6.49.8 1.20.8 8.49.7 6.17+7

E SAN ONOFRE 2 2012 (a) 1989

E SAN ONOFRE 3 2013 1989

SEABROOK 1 2031 1845 2 800 8.6.87 2.98+7 1.36+7 4.02#7 6.82+8 2.43+6 1.09.8 3.88.7 1.59+7

A SEQUOYAH 1 2021 3400 1989 88 1.30+8 9.11+7 6.48+7 7.98+7 2.93+7 1.34+7 2.10.8 1.20+8 7.8247

A SEQUOYAH 2 2022 (a) 1989

SHOREHAM 2627 8371 200 69 5.73+7 2.50.7 1.13+7 2.95+7 8.99+8 2.00+6 8.89+7 3.20+7 1.33+7

SOUTH TEXAS 1 2027 570 2017 50 3.72+7 7.09+6 1.46+6 6.87+8 1.01#6 1.65+6 4.41.7 8.1086 1.63*6

SOUTH TEXAS 2 2028 670 2018 60 3.70+7 6.71.6 1.82.6 6.83#8 9.66+5 1.49+5 4.38+7 7.67*6 1.47+6

ST LUCIE 1 2010 1686 (b) 69 5.71+7 4.48+7 3.55+7 2.40+7 1.12+7 5.94+6 8.11.7 5.60.7 4.14.7

ST LUCIE 2 2023 1558 1992 58 5.60+7 3.55+7 2.33+7 3.25+7 1.06+7 4.22+6 8.75+7 4.61+7 2.75+7

SUMMER 1 2024 1169 1999 57 5.19+7" 2.38+7 1.13+7 2.47*7 8.38+6 1.95+8 7.86+7 3.02+7 1.83.7

A SURRY 1 2012 574 2005 48 3.39+7 1.16+7 4.17+8 4.33+6 1.22+6 8.70+6 3.82*7 1.28+7 4.54+6

A SURRY 2 2013 (a) 2005

B SUSQUEHANNA 1 2022 8680 1995 67 1.29+8 7.21+7 4.13+7 8.66+7 2.01+7 7.26+8 1.98+8 9.22+7 4.86+7

B SUSqUEHANNA 2 2024 (a) 1995

THREE MILE SL I 2008 518 1997 48 3.20+7 1.62.7 8.42+6 6.37+8 2.43.6 9.91+5 8.84+7 1.86+7 9.41+8

TROJAN 2011 861 1998 50 3.69+7 1.77+7 8.83+6 8.84+6 3.07+6 1.16+8 4.57.7 2.08.7 9.99+6

E TURKEY PT 8 2007 816 1995 52 4.14+7 2.31+7 1.32,7 9.29+6 3:82+8 1.6848 5.07+7 2.69,7 1.49+7

E TURKEY PT 4 2007 (a) 1995

B VOGTLE 1 2027 3251 2000 85 1.2658 5.48+7 2.47+7 8.39+7 1.51+7 4.32.6 1.89+8 6.97+7 2.90+7

B VOOTLE 2 2028 (a) 2000

VT YANKEE 1 2012 1596 1993 49 3.62+7 2.22+7 1.4067 1.2867 4.94,6 2.1256 4.88.7 2.71+7 1.62+7

WASH NUCLEAR 2 2028 4642 1994 68 7.57+7 4.48.7 2.65+7 4.14+7 1.26+7 4.88+6 1.17+8 5.89+7 3.12+7

WATERFORD 8 2024 1671 1997 61 6.26+7 3.16+7 1.6567 8.22+7 8.82+6 2.90+6 9.48+7 4.04+7 1.94.7

A WATTS BAR 1 2025 8411 1994 88 1.31+8 7.65.7 4.58.7 7.78.7 2.27+7 8.29+8 2.08.8 9.92.7 5.41+7

A WATTS BAR 2 2027 (a) 1994

WOLF CREEK 1 2025 1313 1999 59 5.67+7 2.680+7 1.23.7 2.81+7 7.13+6 2.16+6 8.48*7 8.31*7 1.45+7

YANKEE-ROWE 1 2001 264 1990 48 2.88+7 2.05+7 1.48+7 5.88+6 3.05+6 1.72+8 3.46.7 2.36+7 1.66.7

A ZION 1 2008 1943 1988 67 7.94+7 8.03+7 4.8387 2.98.7 1.46#7 7.88+6 1.09+8 7.49+7 5.42.7

A ZION 2 2008 (a) 1988 -------- m -------- m -------------- ----------------- mm -.-- - 2.--------------------------------

TOTAL 5.81+9 3.45+9 2.23.9 2.62+9 8.99,8 3.87.8 8.43.9 4.85+9 2.62+9

Co

As

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

iINDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDI1CATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREUENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - CASK STORAGE OPTION(1983 DOLLARS).

I ILOW DEN

PLANT NAME ITYPE IRACKSI

NEEDEDj

--------------------------------------------------------------------------------- BEFORE CONVERSION I----I AFTER CONVERSION I INCREMENTAL COST ----------- RERACKINI ------------------------ I

ex I 6% 1 lox I - I 0% I 6% 110% ex% I 6% 1 10% --------- -------- I---------I------------I----------- M

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK 1

A BRAIDWOOD I

A BRAIDWOOD 2

B BROWNS FERRY 1.

B BROWNS FERRY 2

BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

A

A

B

B

B

B

A

A

BYRON 1

BYRON 2

CALLAWAY 1

CALVERT CLF 1

CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

COMANCHE PK 1

COMANCHE PK 2

COOK 1

COOK 2

COOPER SYN

CRYSTAL RVR 3

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDENJ 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERMI 2

FARLEY I

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GIN"

GRAND GULF 1

HADDAM NECK

HARRIS 1

120 136

138

140 188

188

40

262

(a)

084

(0)

468

370

376

284

(a) 108

192

(a)

144

144

344

198

(a)

268

(a)

232

72

120

85

86

310

316

2•0

662

138

130

380

90

240

64

63.

104

104

1.99.7

2.30+7

3.68+7

3.49+7

0.76+7

0.76+7

1.91+7

1.33+8

1.04+7

1.03+7

1.83+7

9.69+8 1.87+7 1.69#7

1.8+.7

0.75+7

6.68+.

4.83+8

9.682.8

2.82+0

6.62+8

4.68+8

0.06+5

3.82+7

6.42+6 6.64+6

8.21+6

8.47+6

7.34+6

7.34.6

6.60+4 1.038+

3.18+7

4.03+7

4.94+7

8.92+7

8.92+7

1.96+7

1.6658

2.40.7

2.04.7

3.71+7

2.08+7

3.78+7

3.41#7

1.2657

1.05+.

1.87.7

1.96+7

2.89+7

9.28+0

1.88+7

1.39+7

8.12.8

7.46+7

1.26+7

1.43.7

1.43+7

1.61+7

2.24+7

2.24+7

4.38+6

2.38+7

1.42+7

1.60+7

1.94+7

1 . 19+7

1.97+7

1.79+7

1.88+6

3.89+7

4.71+7 1.86+7 7.68*6

3.64+7

a.88+7

0.090.

3.07+7

0.00+0

1.33+8

1.67+7 .68+80

2.88+7 1.89+7

2.41+7 1.64+7

7.44.7 4.38+.

1.32+8 8.64+7 3.11.7 1.63+7 1.98+7 1.39+7 9.04+8

9.02.6 6.01.7 2.72+7 1.63+7 1.2807 1.24+7 9.653+8

7.69+6 4.78+7 3.8657 2.86+? 1.00+7 1.08+7 1.03.7

7.62+6 4.80+7 3.61+7 2.74+7 1.01+7 1.17+7 1.18.7

1.07+8 1.6658 1.18.8 9.06+7 2.36+7 4.24+7 4.78+7

7.13.6 6.82+7 2.98+7 1.60+7 1.69.7 1.06+7 1.17+7

7.1806 8.77+7 8.87+7 6.21+7 2.08.7 2.48+7 2.61.7

2.38.7 1.63#7

1.97+7

7.11+8 2.20+7

1.00+7

2.13+8

3.94.7

I

4.20.7 1.40+7 4.97+0

8.76+7 4.28+7 2.77+7

0.00.0

0.00+0

4.06+7

7.42+7

0.00+0

0.090+ 1 * 26.

1.28+7 1.64+7

0.00+0

0.00+0

4.32.0

3.45+8

8.42+6

S. 94.6

8.99+6

8.70+6

1.89.7

1.88.7

4.9687

1.0•.8

2.98+6

2.67*8

2.08+7

2.02.7

6.03+6

4.14+6

9.30.8

7.39+8

1.96.7

1.94+7

9.72+8

2.88+7

3.8608

3.26+8

8.71+8

1.17+7

1.16-6

1.01+8

6.87+8

4.82+8

4.63+7 2.16+7 1.07+7 A k12+8 7.17+7 4.77+7 3.26+7 2.76+7 2.72+7 2.30+7

2.29+7

1.98+7

9.65+7

2.33+7

2.33+7

0.00+6

1 . 98+7

1.94+7

1.97+7

7.91-7

1.91+7

1.89+7

3.64+7

1.97+7

0.80+0

1.91+7

0.32.7

1.98+7

0.00.0

0.00.0

1.09+7

8.68+86

6.18+7

6.80+6

6.88+9

9.32+0

8.40+8

0.92+8

3.87.7

0.90+0 6.68+8

1.0797

1.14+7

8.32.0

2.96+7

9.79+8

6.68+8

2.37+8

2.92+7

1.68+8 1.68+8

4.680+8

3.78.8

4.18.+

1.99+7

2.12+6

1.74+6

9.20+0

8.74+8

3.70+8

1.46.7

6.06.8

4.90.6 3.34+6

6.48+6

3.89+6

3.89+6

0.12+6

8.12+6

6.30+6

1.08+8

8.13.6

8.13+6

7.30.6 8.19.5

2.32*6

1.04+8

4.19+6

4.76+6

2.91+7

2.84+7

1.13+8

3.27+7

3.27+7

2.71.7

2.2657

2.68+7

1.00.8

3.02+7

2.46,7

4.69+7

2.40.7

1 . 99+7

8.03+7

2.61+7

1.74+7

1.28+7 8. 66#7

1.03+7

1.03+7

1.70+7

1.29+7

1.74+7

8.78,7

1.49+7

1.10+7

a.01+7

1.82+7

1.14+7

4.99+7

1.73+7

1.08+7 6.90+8

6.05.7

3.48+8

3.48.8

1.10.7

7.69+8

1.18+7

4.78+7

7.86+8

6.14+8

2.04+7

1.41+7

6.76+6

3.23+7

1.23+7

7.62.6

8.91+0

1.9.+7

9.83.0

9.83+.

8.04+8 3.76+8

7.88+8

2.28+7

1.17+7

a. 18*6

1.03+7

4.64+6

9.69+6 1.82+7

6.91+8

0.90+0

6.31+8

3.44.7

4.89.8

4.89.8

8.27+0

6.07+8

9.08+0

3.00.?

9.27+0

0.02+8

1.29+7

7.*10.8

a .34+6

2.13+7

7.92+0

6.66+8

3.87+8

3 .78+7

2.31+8

2.31+.

0.98+8

4.42.8

8.19+8

2.90.7

6.14+0

4.02.8

1.19+7

7.04+6

3.2*28

1.88+7

7.02+8
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - CASK STORAGE OPTION(g983 DOLLARS)(cont'd)

-------------------------------------------------------- M ----------- M ---- mm ----------- m- --- mm --- m ----------

ILOW DEN BEFORE CONVERSION

PLANT NAME TYPEI RACKS I----- - ----

NEEDEDI 60 lox ..... -- -I I--

AFTER CONVERSION ! INCREMENTAL COST

--- I ^NAILKI4 I .----------- ---------- I ---------

I I 5% 11lo I 0x 1 6% 1 10% I----------------- - --------------------- -------

|

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE 1

oo MILLSTONE 2 MILLSTONE 3

MONTICELLO

* NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B qUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BENM 1

SALEM 1

SALEM 2

588

(a)

464

138

152

74

48

680

(a)

448

440

146

144

144

198 156

188

240

184

276 195

(-)

1S0

(m)

120

2568 68

170

170

178

468

440

448

192

96 (a)

120 (-)

480 (-)

138

98

384

180

168

4.28.7 1.85.7 8.34+6 1.14+6 5.78+7

9.22+6 5.58+7

3.04+7 1.85.7 1.63+7

2.25.7 9.61.6 1.31+7

1.30+.7 9.31.6

1.02.7 8.27.8 4.*367

8.00.0

0.00•0

2.20+7

2.36.7

2.19.7

1.98.7

1.61.8

8.10+7

8.28+7

2.26+7

3.82+7

3.91,7

3.89+7

3.09+7

2.35.7

1.88+7

1.95.7

3.24+7

8.97+7

1.31.7 4.2.68

1.26.7

8.33+8

9.78+6

1.25+7

1.03+8

3.28*7

2.91.7

1.17+7

1.27*7

1.24.7 3.09+7

1.62+7

4.84.8

6.74+6

1.02*7

8.10+8

3.14+7

7.48.8

3.11.8

4.57.8

8.14.6

7.30.7

1.85.7

1.42+7

8.36*6

4.64.6

4.21.6

2.62.7

7.77+8

9.92*5

2.636*8

5.64+6

2. 18.8

1.40.7

8.01*5 6.77.5

2.84+6 6.68.4

1.27.6

8.93+6

8.73+5

6.25.6

8.42.5

6.42.6

4.05.5 6 *13.5

7.45.5

4.89+5

3.80.5

6.71.5

8.91.5

3.63+7

3.97+7

2.93.7

2.02.7

1.57+8

7.54+7

7.71+7

3.6.57

5.24+7

6.33+7

4.33+7

4.50+7

4.09.7

1.95+7

2.20+7

3.99.7

9.81.7

2.77*7

2.25*7

1.72.7

1.82.7 1.19.8

6.63*7

4.96*7

2.83*7

2.57*7

2.49*7

3.29*7

3. 38*7

1.24.7

9.29*8

1.52.7

1.21.7

8.00.7

2.16.7

1.32.7

1.08,7

1.32.7

9.31.7

4.39+7

3.36*7

2.31.7

1.32.7

1.22.7

2.57*7

2.82+7

4.00+8

4.69.6

1.08.7

3.90.8

3.89+7

1.49.7

1.68.7

7.868

8.77+5

6.78.8

1.53+7

1.52.7

1.38.7

1.49+7

1.48.7

4.84,6

1.46.7

1.81+7

1.22+8

2.90.8

8.07+6

2.74+7

1.67+7

1.49.7

7.73*8

S.80.8

1.77+7

2.44+7

2.14.7

1.71.7

1.36.7

1.31+7 2.49+6

1.92+7

8.64.8

3.04+8

5.38+6

4.53.6

2.96+7

1.47+7

1.0987

8.29m6

5.18+6

2.14,7

2.83.7

2.02.7

1.73+7

9.36+8 8.6568

9.06.5

1.91+7

3.78*8

2.65*6

6.64.6

2.29.8

2.50+7

7.78.7 5.85.7 4.22.7 8.01.5 1.01.8 7.69+7 8.01.7 2.44.7 2.1227 1.87.7

4.11+7

1.96+7

3.12.7 3.96+7

3.98+7

3.9a+7 2.98+7

2.6987

4.0•*7

2.58.7

2.93+7

2.69+7

1.14.7

2.34.7

1.32.7

1.26.7

1.20+7

1.49.7

1.34.7

1.10+7

1.54.7

1.81+7

1.82.7

6.72+6

1.81.7

4.8688

4.2568

3.8786

7.6886

8.91.6

3.24.8

9.54.8

9.10+8

5.42+5

6.11-6

2.70.5

8.74+5

8.74.5 8.74.5

9.02+5 8.73.5

8.93.6

3.97.5

3.84.5

6.24+7

2.42.7

3.88+7

5.46*7

5.47+7

5.47+7

4.19.7 8.*88.7

6.17.7

3.15.7

3.7657

3.97+7

1.7687

2.77+7

2.80.7

2.67*7

2.154.7

2.77+7

2.57.7

1.89.7

2.3887

2.61,7

3.10.7

1.32-7

2.16.7

1.50+7

1.37.7

1.24.7

1.90#7

1.75.7

7.37+8 1.86.7

1.8687

1.e18.7

5.1128

6.86+6

1.68+7

1.58.7

1.58e7

1.30+7

1.28.7

1.25.7

6.14.6

8.54.6

1.34,7

6.80+8

4.51#6

1.64+7

1.48.7

1.41.7

1.37,7

1.32.7

8.87+8

8.84+6

1.03+7

1.34*7

6.97.6

3.89.6

1.10,7

1.01+7

9.24.6

1.22.7

1.14.7

5.03.6

9.33+8

9.87.8

3.81+7 2.17+7 1.35.7 4.31.5 4.63.7 3.48+7 2.71.7

1.8687 8.38+8 2.30+8 9.21.5 2.38.7 9.37+6 3.86.6

9.83+8 1.33,7 1.40+7

6.06.6 3.92+6 2.49+6

1.89.7

2.70.7

3.92.7

3.99+7

4.46*7.

6.78,8

1.8+.7

1.18,7

1.98+7

1.81.7

2.54+6

1.32+7

3.83.6

1.01+7

7.74.8

8.19.6

4.00+5

7.81.6

7.11.6

7.45.5

2.80.7

3.58.7

4.94+7

5.67.7

6O.1*7

1.7867

2.72.7

1.99,7

4.02.7

3.85.7

1.14.7

2.13,7

8.49+6 3.00+7

2.60+7

9.710+6

9.23.8

1.10+7

1.65+7

1.*0.7

1.14.7

8.98.6

8.88.8

2.13.7

2.11,7

9.45+8

8.49+6

6.43.6

2.06.7

1.80.7
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - CASK STORAGE OPTION(1983 DOLLARS)(cont'd)

---------------------------------------------------------------------------------------------------------------

PLOW DEN, I EI

PLANT NAME TYPE RACKS __!----------RION------ RERACKINO--------- TE-CNE!!-------

I --- I--- ---- --- I --- -- --- -- -- ---- - - -

INCREUENTAL COST

a% SI 5 lox0

2.7657 3.27.7 3.16+7

1.40.7 1.28.7 7.818

3.39*7 4.23.7 4.16.7

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH I

A SEQUOYAH 2

SHOREiHA•

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE I

ST LUCIE 2

SUMMER 1

A SURRY I

A SURRY 2 a SUSQUEHANNA I

B SUSQUEHANNA 2

THREE MILE ISL

9 TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOOTLE 1

B VOOTLE'2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION I

A ZION 2

P

P

P

P

P

P

B

P

P

P

P

IP

P

B

B

iP

P

P

P

P

P

P

P

p

270

128

240

104

104

162

144

138

159 (a)

(a)

146

96

144

(a)

252

(a)

284

312

178

240

(a)

162

78

218

(a)

8.68+7 3.86+7

4.80+7 1.3887

1.03.8 6.64+7

4.1227

1.89+7

1.89+7

3.90+7

3.76+7

3.17+7

1.84.7

1.30.7

2.686.

2.66+6

3.09.7

1.60.7

9.16-8

4.48+6

1.09+8 4.6127

2.09+7

4.26+6

3.12.7

4.40+8

4.16+6

3.78+6

2.62+7

6.38+6

2.82.6

1.16.6

2.06.7

2.08+6

2.67+6

3.10+6

1.01.7

4.20+6

1.36+7

4.82.6

1.77+7

3.11-6

4.06.6

1.49+7

7.3806

6.61+6

5.46+6

6.62,6

6.25+5

7.056+

7.08+5

6.08+7

2.81.7

2.79*7

4.99+7

4.92.7

4.66+7

2.43.7

2.14.7 5. 29*8

6.80*6

3.81+7

3.03+7

2.06.7

8.23.8

9.64+6

1.07+8

9.73,5

2.98.7

1.96.7

9.38+8

2.94.6

1.04+7 9.79+8

9.59.6

1.15.7

1.23.7

1.43.7

6.568+

9.1658 3.1.8*

3.0086

7.71.6

1.68+7

1.15.7

4.4658

6.67*6 1.21+8

1.14+a

6.16+6

1.37*7

7.17+6

2.49+6

9.68*6 9.23+7 6.84.7 6.16+7

6.74+6 6.16.7 2.6587 1.16.7

1.06.6 1.36.8 9.66+7 7.17.7

1.31+6 1.33.8 7.14+7 4.02.7 2.49.7 2.68.7 2.08+7

1.88.7

1.93+7

1.90+7

6.07+6

6.87+0

7.61+6

6.64.6

4.37.6

6.39+6

2.29.7

2.82+7

3.29+7

1.14.7

1.33+7

1.80.7

6.88+6

8.54.6

1.02.7

4.8688

9.34.6

1.4657

5.93+6 8.91.8

1.12.7

4.43.8 4.41.8

7.78.8

9.31.7 2.98.7 1.11.6 1.28.8 6.38+7 2.40+7 3.82.7 2.63.7 1.60.7

2.00.7 5.9*+7

4.01.7

1.03+8

3.50+7

1.88.7

4.77+7

8.98.6

2.7657

1.28+7

4.16+7

1.01.7

2.6636 2.83+7

6.6586

6.39+6

6.98+6

1.8+8.

6.77.6

1.88+6

9.64.6

2.83-7

0.83+7

6.67.7 1.38.8

6.01+7

1.97+7

7.04.7

1.68+7

3.88+7

2.72.7

7.69+7

2.22+7

1.38+7

6.41+7

1.03.7

2.27*7

1.40.7

4.47+7

1.04.7

9.87.6

4.24.7

8.85+6

9.97*8

1.63.7

a.47+7

1.67+7

1.28+6

2.38.7

8.3386

1.17+7

1.6217

3.6657

1.27+7

6.46+8

2.88+7

6.68+8 9.86+8

1.03+7

2.01+7

7.96.8

6.00.6

2.84.7

--- ------------------- ----------------------------------------------------------------------------

TOTAL 3.98+9 1.79.9 9.37+8 6.6507 6.17.9 3.0659 2.00+9 1.30.9 1.32.9 1.1839

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT I
TABLE AS*. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - CASK OPTION

(1983 DOLLARS)

---- --- --- ----- --- ---- --- --- --- --- --- --- --- ---- --- --- --- --- --- --- ---- --- --- --- --- -- m - ---

ADD. YEAR

SHUTDOWN STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADDIL TIME

(ASSEM- STOR. (MON.)

BLIES) NEEDED

I.-- ---- COST

... I"$M -- -- -- -

CONSTRUCTION -I_ -I TOTAL "-%---- --- ---

I % 110% 1s0% 1 6% 11lo -------------

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK 1

A BRAIDWOOD 1

A BRAIDWOOD 2

8 BROWNS FERRY 1

B BROWNS FERRY 2

BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

A BYRON 1

A BYRON 2

CALLAWAY I

Co B CALVERT CLF 1 UT B CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

8 COMANCHE PK 1

B COMANCHE PK 2

A COOK 1

A COOK 2

COOPER STm

CRYSTAL RVR 3

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 8

DUANE ARNOLD

ENRICO FERMI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND OULF 1

HADDAM NECK

HARRIS 1

2008

2012

2018

2026

2028

2030

2001

2028

2027

2014

2014

2017

2010

2010

2024

2026

2024

2014

2018

2025

2028

2027

2830

2030

2009

2009

2008

2018

2017

2025

2025

1984

2008

2008

2010

2025

2012

2012

2015

2008

2007

2008

2022

2007

2028

377

565

853

859

1900 1900

95

3827

(a)

3228

2441

2401

2281

3827 (a)

1129

2213

(a)0

0

2672

2067

(a)

1241

(a)

1238

.432

2490

517

617

0 1815

693

998

5355

298

140

2248

413

219

4392

319a

1998

1999

1996

2009

2009

2011

1995

1998

2002

2001

1990

1991

1994

2005

1992

2025

2028

2006

2015

1998

1997

2005

1995

2011

2011

1998

2000

1999

1997

2006

2008

1997

1994

2000

1998

1997

2026

39

39

40

40

43

43

39

47

41

40

40

40

47

40

43

0

0

40

43

41

39

39

45

39

39

39

39

39

43

39

39

40

39

39

42

39

0

1.84+7

2.13+7

3.28+7

3.24+7

8.43+7

8.43+7

1.84+7

1.21+8

4.54,7

3.60.7

3.56+7

3.89.7

1.21.8

3.92.7

8.39.7

0.060.

0.00+0

3.75+7

7.14.7

4.37+7

2.08+7

8.93+7

2.14+7

2.14.7

1.84.7

1.84+7

1.84+7

7.38.7

1.84+7

1.84.7

3.37.7 1 *84.7

1.84+7

5.94+7

1.84+7

0.00+0

9.78+6

9.74+6

1.73+7

9.12+8

1.81+7

1.84+7

1.03.7

8.43,7

1.80.7

1 . 60.7

2.53+7

2.29.7

7.09+7

1.34.7

4.12+7

0.00.0

0.00+0

1.22+7

1 • 50,7

2 • 10.7

1.60+7

2.18+7

1.04+7

6.31+6

4.97+7

5.47.6

5.47+6

8.87.8

8.05+86

8.46.8

3.72+7

8.00.6

5.4568

1.70.7

1.08.7

8.05+86

2.86+7

9.31+6

0.00+0

5.34+8

4.83+6

9.45.8

2.72+8

5.40+8

4.48+8 6.88+6

3.51+7

7.42.8

8.47+8

1.83+7

1.68.7

4.25+7

4.82+6

2.71+7

0.00+0

0.00+0

4.18+8

3.38+8

1.05+7

6.44+6

2.27+8

2.85+7

1.49+8

1.49+6

4.42+6

3.865+6

4.01+6

1.94+7

2.086+8

1.70+8

8.46+6.

3.85+6

1.42+7

4.86+8

6.60+6

1.47,8

1.71,8

2.96+8

2.61+6

3.17.6 3.17,8

7.33+6

1.18.7

1.74+6

2.37+8

2.90+8

2.81,8

1.18.7

2.79.8

3.8568

0.00,8

0.00+0

3.10+8

2.81+6

1.60+8

1.43.8

1.34+8

5.70+6

1.8658 1.85,8

1.22+8

9.78.5

1. 34+8

6.48+8

7.33+6

4.89.6

2.67+8

1.34+8

7.33.5

3.75+6

1.22+6

0.00,0

5.74.5

6.67+5

9.78+5

4.69+5

5.67.5

5.14+6

3.45.5 S 8.168

6.10+6

8.88+5

1.31+8

1.21+8

3.48*6

8.07+5

1.41.8

0.00+0

0.*00.0

6.186+5

4.08+5

5.82+5

5.465+

3.47+6

1.90+6

3.34+5

3.34.5

4.64+5

3.45.5

4.86+6

1.47+8

2.02+5

1.28+6

8.74.5

6.94+5

2.71.5

1.04.6

4.77+6

0.00+0

2.41+5

2.04+6

3.85+5

9.98+4

1.17+5

9.67+4

1.70+6

1.08+8

1.62+5

2.08+6

8.47+6

5.78+6

1.28+6

1.51+6

8.17.5

0.*00+0

0.00+0

1.43+5

8.75.4

2.26+5

2.22+5

9.78+4

7.24+5

6.76+4 8.76+4

1.80+5

1.29+5

1.73+5

4.78+5

*.94+4

3 .58+4

3.20+5

2.78+5

1.05+5

3.386+5

1.98+5

0.00+0

1.99+7

2. 0+7

3.56+7

3.49+7

6.76+7

6.75+7

1.91+7

1.33+8

0.00+0

4.71+7

0.8000

3.84+7

3. 86,7

0.00+0

3.67+7

0.00,0

1.33+8

0.00+0

4.20+7

8.76+7

0.00,0

0.00+0

0.00+0

4.68.7

7.42+7

0.00+0

4.63.7

0.00+0

2.20+7

1.98+7

9.50+7

2.33+7

2.33+7

0.00+0

1.96+7

1.94.7

1.97.7

7.91+7

1.91+7

1.89+7

3.84+7

1.97+7

0.00+0

1.91,7

6.32+7

1.98+7

0.00.0

0.00+0

1.04+7

1.03+7

1.83+7

9.59+6

1.87+7

1.89+7

1.85+7

1.67+7

2.68+7

2.41.7

7.44+7

1.40+7

4.26a7

0.00+0

0.00+0

1.28.7

1.54+7

2.16,7

1.09+7

8.68+8

5.18+7 5.8088

9.00+6

9.32+6

8.40+6

8.92+8

3.87+7

8.20+6

5.68+8

1.79.7

1.14+7

8.32+a

2.96+7

9.79,8

5.68,8

4.*3+8

9.82+8

2.82.8

5.52*8

4.68+8

8.065.

3.82+7

7.58+8

68.88+8

1.89+7

1.84+7

4.38+7

4.97*8

2.77+7

0.00+0

0.00+0

4.32+8

3.46+8

1.07.7

5.88.8

2.37+6

2.92*7

1.58+6 1.56,8

4.60+8

3.78.8

4.18+8

1.99+7

2.1228

1.74+6

9.20+8

6.74+6

3.78*6

1.4657

5.068+
v

TABLE ASs. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - CASK OPTION

(1983 DOLLARS) (cont'd)

ADD . YEAR COST

SHUTDOWN STORAGE WHEN CONS. I I

PLANT NAME YEAR REQ80 ADDOL TIME CONSTRUCTION . 0 S U TOTAL

(ASSEM- STOR. (MON.) ----- ---... I-- - .. -- - -- - -I-- -- -- - - -- - --- - - - BLIES)NEEDED .10 e. 1..% l- 16% -10- I e. 1.6% lox

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 3

KEWAUNEE

LACROSSE

B LASALLE CTY 1

8 LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

UCGUIRE 1

MCGUIRE 2

MILLSTONE 1 co MILLSTONE 2 o• MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 3

PERRY I

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR 8N 1

SALEM 1

SALEM 2

2009

2012

2026

1976

1980

2098

2016

2014

2002

2822

2023

2024

2029

200S

2021

2023

2010

2016

2026

2007

2005

2028

2018

2020

2013

2013

2014

2004

2011

2024

2026

2028

2008

2008

2026

208S

2007

2008

208D

2008

2007

2007

2008

2007

2026

2018

2020

2874

(a) 2820

0

0

493

36o

679

206

9824

(a)

4096

4238

632

966

989

2480

623

$41

365

884

1971

1886

(a) 2102

(a)

1921

912

a35

1117

1121

1121

1812

1689

2648

1612

849 (a)

1142

(a

(a)

228

888

2462

1007

1168

20"

2007

1994

2004 1999

1992

1990

1996

1998

1998

2005

209

1987

1997

2016

20"4

1998

2011

1099

1089

1991

1994

1988

2005

208

2007

1997

1997

2009

1993

1996

1993

2086

2004

1990

2007

1997

2001

41

41

39

39

s9

39

48

42

42

39

40

40

40

40

39

39

39

40

43

43

40

39

39

49

40

40-

39

39

40

39

39

40

39

39

39

40

40

41

4.13.7 1.80.7 8.17,6 1.32+6

4.08.7 1.28.7 4.14.8 2.78+8

4.64+6

6.49,6

2.04.7

2.21,7

2.00,7

1.84.7

1.39+8

6.88+7

6.80+7

2.10+7 8.68+7

3.88+7

3.6657

2.83+7

2.23.7

1.84.7

1.84+7

3.02+7

8.84+7

1.19,7

7.93+0

9.17.8

1.19+7

9.86.7

3.16+7

2.79+7

1.11+7

1.22-7

1.19+7

2.92+7

1.43,7

4.46#0

6.82+8

9.78+8

7.71.8

3.04+7

7.16+8

2.99.8 4.906+

7.62+8

7.11.7

1.80.7

1.39.7

8.09+6

4.*40*6

4.08.6

2.43+7

7.46+8

9.69+6

2.49.6

6.34+6

2.10.8

1.46.7

1.66J 8 6.69+6

1.47.8 4.00.6

1.92.6 8.08+6

1.228 6.08.86

1.23+7 4.33.6

4.40+6 1.28.8

4.77+6 1.16+0

1.67.8 6.1685

2.37.8 6.48+6

2.61+8 6.43+6

3.40+6 1.64#8

2.62+6 8.69*.

1.21+6 1.91-6

3.67.6 1.19.6

1.10.6 4.81.6

2.21.8 3.89.6

3.27.8 9.64.5

4.63.6 1.99.6

3.39*6 1.36+0

1.22.6 6.62+6

3.33+0 1.63+8

2.81.6 6.11.5

2.81+8 6.81#6

2.81.8 6.64+6

1.6806 6.10+6

1.65+6 6.93+6

2.61.6 4.6886

2.07.8 8.79+6

1.74+8 7.14.6

2.22+8 9.44+5

1.67.6

1.24+6

3.68*6

1.18+6

2.12+6

3.18+6

1.89.8

4.63,5

3.49+6

2.69.6

1.42.6

1.32+5

8.98+6

3.14.6

3.34.4

4.11.4

2.04*6

7.7654

3.14.6

9.78+6

8.11.6

2.83*6

8.00.6 1.62#6

1.38-6

1.26+6

2.49.6

2.42+6

9.93,4

4.06,6

3.14.6

4.34+6

2.81+4

6.24+4

6.78+6

1.23.5

3.26*5 2.20+6

4.26.7

0.00+0

4.38.7

0.00.8

0.60+0

2.20*7

2.38+7

2.19.7

1.98+7

1.61+8

0.00.0

8.10.7

8.29+7

2.28+7

3.82.7

3.91+7

3.89+7

3.09-7

2.36+7

1.88,7

1.95.7

3.24.7

6.97.7

0.00.0

7.7687

0.00+0

4.11.7

1.9607

3.12.7

3.96.7

3.98+7

3.98.7

2.98+7

2.69.7

4.0a.7 2.68+7

2.93+7

3.81.7

0.00+0

1.88+7

0.00.0

1.89.7

2.70+7

3.92.7

3.99+7

4.46+7

1.8657

1.31.7

1.28+7

8.33+8

9.78+8

1.26+7

1.03.8

3.28.7

2.91.7

1.17,7

1.27+7

1.24.7

3.08,7

1.62.7

4.64+8 6.74.8

1.02.7

8.10+8

3.14.7

6.8667

2.69.7

1.14.7

2.34.7

1.32.7

1.28.7

1.20+7

1.49.7

1.34.7

1.10*7

1.64+7

1.61+7

2.17+7

6.38.6

6.78.8

1.88.7

1.18.7

1.96.7

1.81.7

8.34.8

4.26+6

7.48.6

3.11+8

4.67.8

8.14.6

7.30+7

1.8657

1.42.7

6.36+0

4.64+6

4.21.6

2.62.7

7.77+6

9.92.6

2.63.8 6.64+6

2. 18.6

1.48.7

4.22.7

1.82+7

8.72+6

1.81.7

4.68.6 4.26+8

3.87.8

7.68*86

8.91.6

3.24*6

9.64+6

9.19+8

1.3657

2.30+6

2.64.8

1.32+7

3.83.6

1.01.7

7.74+8

7.30+7 6.45+7 4.12.7

3.77.7

1.84+7

2.79.7

3.87.7

3.68.7

3.6887

2.82.7

2.63.7

3.7657

2.37+7

2.78.7

2.66+7

1.08.7

2.19.7

1.2687

1.20.7

1.14+7

1.43+7

1.28.7

1.0657

1.4657

1.64+7

1.76.7

8.4868

1.73.7

4.61.8

4.11.6

3.74+6

7.43+6. 6.67.6

3.14.6

9.13+6

8.79+4

a.39+7 2.08.7 1.31+7

1.84.7

1.84.7

2.4687

3.85+7

3.71.7

4.18.7

6.30.8

8.62+0

1.7657

1.13+7

1.87+7

1.74+7

2.27+6 2.44+6

2.49+6

1.28+7

3.71.8

9.77+6

7.62+0

4.89.6

2.38+8

2.68+6

2.8126

2.78+0

7.77,4

1.68+6

1. 12.8 6.90+6

9.01.6

7.34.6
TABLE ASa. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - CASK OPTION

(1992 DOLLARS)(contId)

----------------------------------------------------------------------------------------------------------------------

co

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 8

SEABROOK 1

A SEQUOYAH 1

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUtMER 1

A SURRY 1

A SURRY 2

B SUSQUEHAINA 1

8 SUSQUEHANNA 2

THREE MILE ISL

TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOGTLE 1

B VOCTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK I

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2012

2018

2031

2021

2022

2027

2027

2028

2021

2023

2024

2012

2013

2022

2024

1 2008

2011

2007

2007

2027

2028

2012

20283

2024

2025

2027

2025

2001

2008

2008

2382

1281

2680

2588

258 25O

1182

1128

781

97

(a)

7288

(a)

75r

873

384

(a)

2495

(a) 10888

4018

1143

2691

(a)

857

36

1295

(a)

2008

1995

2008

20283

2024

1987

200I

2008

2012

2000

2006

2004

2002

2006

1999

1998

2008

2001

2008

1999

1995

41

45

40

39

39

40

40

40

39

45

39

39

39

44

39

42

40

45

40

39

41

4.47+7

9.53.7

3.81+7

1.84+7

1.84+7

3.58+7

3.42+7

2.94+7

1.84+7

1.02+8

1.84.7

1.84+7 1.84+7

8.778.7

1.84.7

5.52+7

3.74+7

9.57+7

3.25+7

1.84+7

4.58.7

1.32+7

5.31*7

1.24+7

2.82+8

2.49+8

2.93+7

1.42+7

8.89+1

4.48.8

4.43+7

8.62.6

7.30.8

2.8a+7

8.4568

2.85+7

1.22.7

3.99*7

9.81+6

8.45+6

2.55.7

4.13.8

3.04.7

4.28+6

4.07*5

3.70+5

2.43+7

8a. 15.8

2.71+8

1.18+8

2.01+7

2.08+8

2.49+8

3.02+8

9.81.8

4.01+6

1.32.7

4.18.8

1.72+7

3.00.+

4.01+8

1.46+7

3.3"+

7.43+6

3.108+

4.89+5

4. 89+5

3.40*8

3.26*6

2.34+8

0.00.0

8.90.8

2.44+5

8.5685

6.11+5

5.380+8

1.59+6

3.75+8

2.688+

8.90+8

2.62+6

2.44+5

1.89+8

5.79.5

2.29.8

8.15.5

8.18+4 56.86.4

1.64+8

8.10+5

4.89+6

6.00+0

1. 80.8

7.40+4

2.54+5

2.09+5

1.05+8

5.28.5

1.02+6

5.82.5 1.85.8

4.93+5

1.04+5

7.80+5

1.19+5

9.34+5

1.42+5

8.58+3

7.78.3

8.98+6

2.34.5

1.0865

0.00+0

5.44+5

2.37+4

8.04+4

7.68+4

2.44*5

1.89+5

3.28#6

1.35.5

4.85+5

1.10+5

4.62#4

3.29+5

1995 43 8.51.7 3.83+7 2.07.7 8.75.5 3.33+5 1.79.5 6.58+7

6.00.0

0.*00.0

4.80.7

1.03+8

0.00+0

4.12+7

I. 89+7 1.89+7

3.90+.7

3.76+7

3.17+7

1.•84.7

1.09.8 0.00+0 1.88+8

1.• 8+7

1.93+7

1.90+7

0.*00+0

9.31+7

6.00+6

2.00+7

5.90+7

4.01+7

1.03+8

0.00+0

8.50+7

1.86+7

4.77+7

0.00+0

3.93+9

3.66.7

1.39.7

5.54,7

1.30.*7

2.69+6

2.6656

3.09.7

1.50+7

9.15+8

4.48.6

4.61.7

8.07+8

6.87+6

7.51+6

2.98+7

8.98+6

2.75+7

1.29-07

4.15+7

1.01.7

8.55+6

2.63+7

2.019+7

4.25.6

3.12+7

4.40+8

4.16+5

3.78.5

2.62#7

8.38+8

2.82+8

1.16+8

2.08.7

2.088+6

2.57+8

1.01.7

4.2086

1.35.7

4.32.8

1.77+7

3.51+8

4.06+8

1.49+7

3.88*9 1.72.9 9.09+8 2.49+8 7.44+7 2.75+7 1.79.9 9.37+8

A INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

B INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

E INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1
TABLE A6b. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - CASK OPTION

(1983 DOLLARS) (cont'd)

-- -- -- -- -- -- -- -- -- -- -- -- -- - -- -- -- -- -- -- -- -- -- -- -- -- - -- -- -- -- -- -- -- -- -- -- -- -- -

ADD. YEAR

SHUTDOWN STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADD'L TIME

(ASSEU- STOR. (MON.) BLIES) NEEDED --------- -------- ------- ------ ------

COST

CONSTRUCTION 0S a TOTAL

-- -s6 110% --- x - 1-1-0i -

013

E SAN ONOFRE 1

E SAN ONOFRE-2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH 1

A SEqUoYAH 2

SHOREHAMi

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSqUEHANNA 1

B SUSQUEHANNA 2

THREE MILE ISL

TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOGTLE 1

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK I

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2012

2013

2031

2021

2022

2027

2027

2028

2010

2023

2024

2012

2013

2022

2024

1 2008

2011

2007

2007

2027

2028

2012

2023

2024

2026

2027

2026

2001

2008

2008

8172

1646

8400

(a)

3371

670

670 1838

1668

1189

674

(a)

86880

(a)

613

681 816 (a)

3251

(a)

1690

4842

1871 3411

(a)

1813

264

1943

(a)

1989

1989

1989

200

1989

1989

200

2017

2018 (b)

1992

1999

2006

2006

1995

1996

1997

1998

1996

1995

2"0

200

1993

1994

1997

1994

1994

1999

1990

1988

1988

45 8.97+7 8.69+7 6.00+7 2.61.6 1.50.8

42

47

41

39

39

41

41

41

39

47

39

39

40

48

39

43

42

47

41

39

43

6.88+7

1.238.

4.69.7

2.87.7

2.65.7

4.87.7

4.47.7

4.18.7 2.33+7

1.22.8

2.14.7

2.6837

3.11+7

1.18+8

2.66+7

6.36+7

6.17+7

1.24+8

4.83+7

1.84+7 8.28*7

2.48+7

9.20.7

2.06.7

6.08+8

3.6867

2.88.7

1.91+7 7.96+6

8.82+7

1.08.7

1.27+7

1.78.7

6.14.7

1.67,7

8.71,7

2.81.7

7.23+7

2.12.7

1.31+7

6.24+7

1.12+7

8.98+7

9.27.6

1.04.8

9.42+6

2.90.7

1.90.7

9.09+8

2.88+6

3.90.7

6.83.8

6.*306

9.92.6

2.33+7

9.87+6

2.22*7

2.*38+7

4.84.7

1.01+7

9.48+0

4.16.7

4.71.6

1.28.7

3.92.6

1.43.8

1.43.6

3.20+6

4.61.6 3.86+6

9.6806

1.06+7

1.46+6

1.68+8

1.77.6

1.02.7

2.69+6

4.78+8

3.97+8

1.22.7

3.78.6

1.34.6

3.47+8

1.03.6

4.8363

9.29.5

2.11+6

2.00+5

1.6506

1.48.6

9.44+6

2.71+5

8.19.6

6.64+6

6.48+6

7.28+5

2.42+8

1.06+8

1.46.6

1.09.6

3.69+6

9.67.6

7.21+6

1.708.6

2.8656

2.11.6

2.88+6

3.4654

3.18+4

7.92,5

6.86+6

2.89+6

8.20*4

1.16.6

2.26+.

2.43*6

3.22,6

6.91.6

4.57+6

6.41.5

3.67+6

1.31-6

2.90+6

4.07.6

9.18-6

6.15.7

1.36.8

6.08.7

2.81.7

2.79+7

4.99+7

4.92.7

4.6657

2.43.7

1.33.8

2.29+7

2.82.7

8.29+7

1.28.8

2.*83.7

6.83+7

6.67+7

1.36.8

6.61.7

1.97+7

7.04+7

2.68#7

9.6887

2.14.7

6.29.8

6.00.8

8.81+7

3.03.7

2.00.7

8.23.6

7.14.7

1.14.7

1.33.7

1.80.7

6.38.7

1.68.7

3.86.?

2.72+7

7.69.7

2.22+7

1.38.7

6.41+7

9.04+6 9.23+7 8.84+7 6.16+7

1.16.7

7.17.7

9.64+6

1.07.8

9.73+8

2.98.7

1.9687

9.38+6

2.94+0

4.02.7

5.88.6

6.4+*6

1.02+7

2.40.7

1.03.7

2.27.7

1.40-7

4.47+7

1.04+7

9.87+6

4.24+7

------------------------------------------------------------------------------------------------------ 4.79+9 2.92+9 1.94.9 8.78+8 1.381+ 5.67,7 6.17.9 3.0659 2.00.9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COUBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANALs CAPACITIES AND INVENTORIES ARE COMKINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REqUIRINQ CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

I INCLUDED IN UNIT 1.

NEED ADDITIONAL SPACE AS OF 1988.
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - SILO STORAGE OPTION(1983 DOLLARS)

PLANT NAME TYPE RACKS ------------------------------------------------------ REACIN --

LOW DEN BEFORE CONVERSION AFTER CONVERSION INCREMENTAL COST

PLANT NAME ITYPEI RACKS ----------------- RERACKZINK ----------...------------

I INEEDEDI0 OX 6 1 16 0 110 86 0% S s0w e I 5x I lox - -- - -- ------ -- - - - - - - - -

ARK NUCLEAR 1 P 120 3.83.7 1.47+7 7.58.6 5.42.5 4.689+7 8.10+7 2.23+7 1.70+7 1.69+7 1.82.7

ARK NUCLEAR 2 P 136 8.39+7 1.41+7 8.28+8 5.54+5 5.88.7 3.27+7 2.22.7 2.00+7 1.9147 1.84+7

BEAVER VALLEY 1 P 138 4.97.7 2.24.7 1.1117 8.21+5 8.91.7 4.2867 2.98+7 2.00+7 2.08+7 1.93+7

BEAVER VALLEY 2 P 146 4.66.7 1.15+7 8.17+6 6.47+6 8.73+7 2.86.7 9.65.8 2.13+7 1.29+7 7.12+8

BELLEFONTE I P 168 7.70.7 1.91+7 6.31.8 7.34+5 1.04+8 8.72+7 1.53+7 2.77.7 1.8897 1.88+7

BELLEFONTE 2 P 168 7.70*7" 1.74+7 4.39+8 7.84,5 1.0408 3.37#7 1.27#7 2.77.7 1.71+7 9.02+8

BIG ROCK I B 46 2.6557 1.38.7 7.70+. 8.56+4 2.79.7 1.70+7 1.07.7 2.49.6 3.29+8 3.10-8

A BRAIDWOOD I P 252 1.87.8 6.95.7 2.96.7 1.88+6 1.82.8 9.59.7 5.96+7 4.52+7 3.74+7 3.10.7

A BRAIDWOOD 2 P (a)

B BROWNS FERRY 1 B 684 5.17+7 1.91.7 7.63,6 1.32+6 7.18+7 3.14+7 1.47+7 2.14+7 1.36+7 8.48.6

B BROWNS FERRY 2 B (a)

BROWNS FERRY 3 B 456 4.84.7 1.80+7 7.21.8 9.02+5 6.41+7 3.02+7 1.58+7 1.8.+7 1.32+7 9.49+6

BRUNSWICK 1 B 876 5.21+7 3.1867 2.08+7 7.59+5 6.20.7 4.08+7 2.92+7 1.87+7 9.92+6 9.16+6

P 0.00+0

BRUNSWICK 2 B 376 4.97.7 2.91.7 1.83+7 7.52+5 8.0387 3.97.7 2.84+7 1.14.7 1.14+7 1.09.7

P 0.88,0

A BYRON 1 P 264 1.37.8 6.67.7 3.58+7 1.07.6 1.82+8 9.90+7 6.20+7 4.5657 3.44+7 2.73.7

A BYRON 2 P (a)

CALLAWAY I P 168 5.40.7 1.6807 5.29.8 7.13+5 7.82+7 3.32+7 1.62+7 2.49.7 1.79+7 1.16+7

B CALVERT CLF I P 192 8.06.7 4.45+7 2.69+7 7.16+5 1.00+8 8.28+7 4.31+7 2.0657 1.98+7 1.89,7

B CALVERT CLF 2 P - (a)

CATAWBA I P 144 0.080+ 0.0+0 0.800+0 6.42.5 2.38+7 3.68.6 8.21+5 2.45+7 4.32+6 1.26+8

CATAWBA 2 P 144 0.00+0 8.08,+ 0.00.0 5.94+5 2.38.7 8.24+6 6.0085 2.36.7 3.84+6 1.09.6

CLINTON 1 B 844 5.46.7 1.51.7 4.89.8 6.98+5 8.84.7 2.39.7 9.89+6 1.45.7 9.53.6 5.69.6

B COMANCHE PK I P 198 7.75+7 1.50+7 3.20+6 8.78+6 1.80.8 2.38.7 6.34+6 2.36.7 9.70+6 4.02+6

B COMANCHE PK 2 P (a)

A COOK I P 256 4.92.7 2.23+7 1.06+7 1 1.12+6 7.93+7 4.79.7 8.89.7 8.12+7 2.67+7 2.14.7

A COOK 2 P (a)

COOPER STH B 232 3.17.7 1.49.7 7.33+6 4.90+5 4.08.7 2.23.7 i.3807 9.42+6 7.98+6 6.11+6

CRYSTAL RVR 3 P 72 2.96.7 9.36+8 3.19.6 8.34+5 4.17.7 1.67.7 7.26+8 1.24+7 7.6+8 4.48.6

DAVIS-BESSE 1 P 128 9.98.7 4.84.7 2.56.7 5.48+5 1.28+8 7.24.7 4.84.7 2.09+7 2.45.7 2.33+7

DIABLO CANYON 1 P 85 3.49+7 8.01+8 2.02+6 3.89+5 4.68+7 1.30+7 4.0686 1.21+7 5.40.6 2.43+6

DIABLO CANYON 2 P 85 3.49+7 8.01.6 2.02+6 3.89+5 4.68+7 1.8067 4.08+8 1.21+7 5.40+8 2.43.8

DRESDEN 1 B 0.080+

DRESDEN 2 B 316 2.87+7 1.29.7 8.1868 6.12.5 3.98.7 2.26.7 1.37+7 1.17.7 1.0347 8.21.6

DRESDEN 3 B 318 2.71+7 1.13.7 4.93.8 6.12.6 3.42.7 1.88+7 1.08+7 7.74+6 7.36+8 5.70+6

DUANE ARNOLD B 266 2.95.7 1.25.7 6.83.6 5.,3+5 4.19+7 2.41.7 1.60+7 1.29+7 1.21.7 9.93+6

ENRICO FERMI 2 B 652 9.70.7 3.997 1.88.7 1.088 1.28.8 6.57+7 4.24+7 2.40+7 2.89+7 2.47+7

FARLEY I P 136 2.5657 8.0868 2.7068 6.13+5 4.13.7 1.87+7 9.05+6 1.6567 1.12.7 6.98+8

FARLEY 2 P 136 2.38.7 8.9568 2.15+. 6.13.6 3.62+7 1.47+7 6.53+6 1.20.7 8.38.6 6.00+6

FITZPATRICK B 368 4.88+7 2.14+7 1.82.7 7.30+5 8.28+7 3.46.7 2.15+7 1.41.7 1.40+7 1.28+7

FORT CALHOUN P 98 2.95+7 1.60.7 9.08.6 3.19+5 3.78+7 2.57+7 1.86+7 8.63+6 9.98+6 9.87+6

FT ST VRAIN 0 240 0.00,8

GINNA P 84 2.55.7 1.08+7 4.78+8 2.32+5 3.03.7 1.6837 9.17+8 5.08G6 6.72+6 4.63+8

GRAND GULF 1 B 536 7.88.7 3.18.7 1.44+7 1.04.8 1.08.8 5.17.7 3.05.7 2.26+7 2.89+7 1.72.7

HADDAM NECK P 104 2.87.7 1.36+7 6.7568 4.19+5 3.89.7 2.48.7 1.59.7 1.06+7 1.09.7 9.62+8

HARRIS I P 184 0.88+0 4.75+5

B 0.00+0
TABLE A8. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - SILO STORAGE OPTION(1983 DOLLARS)((cont/d)

-- a-- - ---- -- --- -- -- --- -- -- --- -e e- --- ew-- --- -- -- --- :e-- --- -- -- --- -- -- e -- e- -- --e ---e

J I LOW DENI PLANT NAME TYPE RACKS I

I NEEDED I ---- - -- - - I

II

BEFORE

0---- T

CONVERSION

-; -- ,1--oS -

I_._ _..! AFTER CONVERSION

I KtNAKAfKNU REAKN I I - - - ------- II INCREMENTAL COST

a HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT SAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT a KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE I

MCGUIRE 2

MILLSTONE 1 o MILLSTONE 2

MILLSTONE a

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE a

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHOOTTOM 2

PEACH4BOTTOM 3

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES I

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND I

SALEM 1

SALEM 2

a

B

B

B

P

P

P

B

B

B

B

B

P

P

P

B

P

P

B

a

B

P

P

P

P

B

P

P

P

P

B

B

P

P

seBB

(a)

484

136

162

74

48

(a)

448

440

148

144

144

198

168

188

240

184

278

196

(a)

18O(a)

120

268

88

170

170

170

468

440

448

192

98

(a)

120

Ig)

98

a84

160

168

4.62.7 1.89.7 8.28.4 1.14.6 7.19.7

9.22.5 7.•2.77

3.06+7 1.69+7 1.79.7

2.49+7 9.7386 1.84.7

1.29+7 8.78.6

6.62.7 1.09.7 6.17.+

0 .000. 0.600.

3.23.7

3.29.7

3.44.7

2.87+7

1.68.8

8.21.7

8.60*7

a.29.7

4.83+7

4.98.7 6.61,7

4.46+7

3.13.7

2.30*7

2.79+7

4.31+7

7.88+7

9.10+7

6.69+7

2.87+7

4.89.7

S. 20.7

6.21+7

6.21+7

3.78+7 3.68+7

6.06+7

a.79+7

3.82+7

1.49+.7 4.48+6

1. 73.7

1.10.7

1.40+7

1.73.7

9.24+7

3.8637

8.23*7

1.60.7

1.47.7

1.48.7

3.63.7

1.94+7

6.93.8

8.20.6

1.40.7

9.84.6

3.20+7

6.76+7

3.19.7

1.68.7

3.12+7

1.54+7

1.47.7

1.39.7

1.78.7

1.08.7

1.26.7

2.07.7

1.97+7

9.77+6

3.92.6

6.14+6

1.09+7

6.83+7

1.8667

1.43.7

8. 22.6

4.91+6

4.64+6

2.61+7

9.26.8

1.23+6 3.08.6

7.*33.

2.49+8

1.4127

3.97+7

1.98*7

8.98*6

2.20+7 6.06+8

4.61.6

4.19+6

8.0826

8.28+6

3.47+6

1.20.7

1.06+7

6.01.6

6.77.6

2.84+6

8.68.4

1.27-6

8.93.6

8.73.6 6.26+6

6.42.6

6.42.6

4.05+6

6.13+6

7.4656

4.89+6

3.80*6

6.71.5

8.91.6

8.01-6

6.42+6

6. 11.6

2.70*6

8.74.6

8.74*6

8.74.6

9.0246

8.73.6

8.93+6

3.*97.5

3.64+6

4.86*7

6.40.7

4.66+7

3.27.7

1.81+8

1.04.8

1.08.8

6.07+7

6.83.7

7.0127

6.79+7

6.39+7

6.21.7

2.79+7

3.4657

5.23.7

1.08.8

1.07+8

7.03+7

3.6887

6.33+7

7.4657

7.48.7

7.4687

6.21+7

4.98.7

8.68+7

4.6687

4.80+7

3.31+7

2.87+7

2.33,7

2.*38.7

9.97+7

6.89.7

6.3657

3.41+7

2.87.7

2.78.7

3.81,7

3.98.7

1.41.7

1.27.7

2.18.7

1.40+7

5.72+7

6.74.7

4.43+7

2.43.7

3.44+7

3.16.7

3.00+7

2.66,7

3.12+7

2.98.7

2.11.7

8.09+7

3.05+7

2.41.7

1.46,7

1.32.7

1.78.7

6.23.7

3.9*97

3.24,7

2.48+7

1.3657

1.26#7

2.73.7

2.79.7

4.28.6

1.4657

4.21.0

3.44.7

4.69+7

3.11.7

1.70.7

2.44*7

1.54.7

1.40.7

1.28+7

1.99+7

T.89+7

7.64.6

2.21+7

2.03+7

1.6887

2.17.7

1.16.7

4.09.6

1.43*7

2.23+7

2.24.7

1.83.7

2.06.7

2.09.7

3.21.8

2.68+7

2.16.7

6.34.6

7.01.8

9.77.6

2.79*7

1.72.7

1.39+7

8.43+8

4.67+6

2.32.7

2.32+7

2.32+7

1.62.7

1.49+7

1.69.7

9.18.6

1.08.7

1.64.7

1.64.7

9.61.8

6.356+

8.67+6

2.3657

2.21+7

1.86.7

1.48+7

1.41+7

2.21+8

2.10.7

8.9.86

4.98+6

8.24+8

4.76+8

2.61+7

1.07+7

1.30.7

9.68.8

3.47+6

1.6887

1.00+7

1.64+7

1.43+7

1.38+7

9.44.0

1.08+7

1.12+7

1.49.7

1.12+7

7.34.6

7.00+6

6.27.0

2.20.7

1.90.7

1.71+7

9.20.6

8.68.6

1 . 68.6

1 . 93.7

3.79.8

3.48+6

7.564+

2.29+6

2.12.7

8.9+86

1.19+7

8.60*8

2.62+6

1.10.7

1.01.7

9.26+8

1.20.7

1.16.,7

4.98.8

1.0657

1.01.7

4.67.7 2.6837 1.48.7

2.22+7 7.67.6 2.71.8

4.31.5 6.78*7 3.89.7 2.81.7 1.2657

9.21+6 2.8657 1.10.7 4.47.6 7.18+6

1.41+7 1.87.7

4.38+8 2.68+6

2.38+7

4.06+7

6.08+7

6.23+7

5.62+7

8.44+6

2.61+7

1.38+7

2.28.7

2.03#7

3. 14.6

1.68-7

4.16.8

1.09+7

8.08+6

6.19+6

4.00.6

7.81+5

7.11+6

7.46+6

4.0657

4.91+7

8.53+7

7.48+7

8.17-7

2.31+7

2.26+7

4.60+7

4.23+7

1 • 40.7

2.39,7

8.78+6

3.04+7

2.5 07

1.73.7

9.08.6

1.63+7

2.30.7

2.62+7

1.5627

9.37.8

9.49*8

2.29#7

2.27.7

1.18-7

7.79+8

6.42+4

2.02*7

1.77.7
TABLE AS. COST FOR THE ADDITIONAL STORAGE SPACE BEFORE AND AFTER CONVERSION TO

LOW-DENSITY RACKS AND INCREMENTAL COST FOR ADDITIONAL STORAGE CAPACITY

TO COMPENSATE FOR THE USE OF LOW-DENSITY RACKS FOR VARIOUS DISCOUNT

RATES - SILO STORAGE OPTION(1983 DOLLARS)(contsd)

LOW DENI BEFORE CONVERSION I I AFTER CONVERSION I INCREMENTAL COST

PLANT NAME TYPE RACKS ---------- ..... RERACKINo .---. -- ------------ ..

....--- I .NEEDEDIOe ------.. .I .. .. .. 1%I . . .------ eI . . .m.. -- .6 . .-- .I 1% -lox___ .. --I ----------- I 6 . ...16%

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 3

SEAOROOK 1

A SEQUOYAH I

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 2

A SURRY 2

B SUSQUEHANNA 1

B SUSQUEHANNA 2

THREE MILE ISL 1

L.o TROJAN

w E TURKEY PT 3

E TURKEY PT 4

B VOCTLE 1

B VOOTLE 2

VT YANKEE I

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

276

128

246

(a)

368

104

104

152

144

136

159

(a)

68(a)

146

98

144

(a)

252

(a)

284

312

176

246

(a)

152

76

216

(a)

5.82.7 3.21+7 1.82+7 9.68+5 8.25+7 6.60+7 4.18+7 2.53+7 2.08.7 2.45+7

1.10+8

5.52+7

2.38+7

2.38+7

5.51+7

5.30+7

4.34+7

2.08+7

1.08+8

2.22+7

2.63.7

2.46+7

9.74+7

3.11.7

7.58+7

6.15.7

1.67.0

4.68+7

2.22.7

5.32+7

1.58.7

6.14.7

1.52+7

3. 34.6

3.18+6

3.84+7

1.84+7

1.14+7

5.02+6

4.11+7

7.2126

9.09+6

9.55+6

2.79+7

1.29+7

3.02.7

1.47+7

3.81+7

1.21+7

1.01+7

2.74+7

4.41+6

2.70.7

4.74+6

5.13.5

4.87.5

2.62+7

7.18+6

3.28+6

1.30+6

1.74+7

2.47+6

3.32.6

3.88+6

8.87+6

S.74.6

1.38*7

4.63*6

1.52+7

3. 6.6

4.4096 1.49#7

5.74.5

1.08+6

7.38+5

5.51+6

5.48+5 6.52+6

5.25+6

6.0655

7.03+5

1.31.6

6.54+5

4.37+5 8.39#5

1.11.6

5.5$+S

6.39*6

6.96.5 1.06+6

6.77+5 1.98+5 9.64+5

8.46+7

1.48.8

8.96+7

3.57.7

8.39+7

7.18+7

6.25+7

3.04+7

1.34.8

3.23.7

3.82+7

4.08+7

1.29+8

4.31.7

8.90+7

7.45+7

1.42+8

8.79.7

2.95.7

8.06+7

2.88+7

8.18+7

2.44+7

6.88+8 6.06+8

4.20+7

3.55+7

2.33+7

1.06+7

a.26+7

1.51+7

1.88+7

2.10+7

4.72+7

2.28+7

4.17.7 3.04+7

6.72+7

2.53.7

1.95+7

6.36+7

1.18+7

5.29+7

9.87+6 1.26+6

1.14.6 3.00+'7

2.08.7

9.94+6

3.66.8

3.27+7

7.49+6

7.83.6

1.14+7

1.9867

1.29+7

2.24+7

1.42.?

1.68.?

1.33+7

3.80+7

2.2127

3.49+?

1.51,7

1.24.7

1.22+7

9.35+6

1.93+7

1.97+7

1.065+7

2.73+7

1.67.7

1.24.7

1.68.7

3.25.7

1.26.7

1.38.7 2.07.7

3.64+7

2.18+7

7.46+6

2.83+7

1.37+7

3.16+7

9.98.6

3.59.6

3.43+6 8.16+6

1.77+7

1.26.7

6.76.8

2.27.7

8.5886

8.1686

1.21*7

2.04.7

1.102+7

1.21.7

1.84+7

3.02.7

1.38.7

9.51.8

2.71+7

7.74+6

2 . 70+7

5.87+8

1.29+6

1.22+6

4.35+6

1 . 39+7

7.26+6 2.90+6

1.87+7

5.68+6

4.95+6

8.16+8

1.18.7

?,69+6

9.46+6

1.03+7

2.24+7

7.93+6

8.68.6

2.46,+7

---------- - ----------------------------- w ------------- - -----------------------------------

4.86+9 1.97+9 9.56+8 6.6597 6.46+9 3.23+9 1.96.9 1.68+9 1.32+9 1.01+9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITh ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1
TABLE Aaa. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - SILO OPTION

(1988 DOLLARS)

--------------------------------------------------------------------------------------------------------------- ADD. YEAR

SHUTDOW• STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADD'L TIME

(ASSEM- STOR. (MON.)

I-ES) NEEDED ------------------- --- ------ ------

C OT m ------------------------------------------- I-----------------

CONSTRUCTION I SIM I TOTAL. - -------- --------------------

ox I5 I0 10 I0 x 15% i o I 5% I lox ---------- ------------

ARK NUCLEAR 1

ARK NUCLEAR 2

BEAVER VALLEY 1

BEAVER VALLEY 2

BELLEFONTE 1

BELLEFONTE 2

BIG ROCK 1

A BRAIDWOOD 1

A BRAIDWOOD 2

B BROWNS FERRY 1

B BROWNS FERRY 2

BROWNS FERRY 3

BRUNSWICK 1

BRUNSWICK 2

A BYRON I

A BYRON 2

PA CALLAWAY 1

B CALVERT CLF I

B CALVERT CLF 2

CATAWBA 1

CATAWBA 2

CLINTON 1

B COMANCHE PK 1

B COMANCHE PK 2

A COOK 1

A COOK 2

COOPER STN

CRYSTAL RVR 8

DAVIS-BESSE 1

DIABLO CANYON 1

DIABLO CANYON 2

DRESDEN 1

DRESDEN 2

DRESDEN 3

DUANE ARNOLD

ENRICO FERUI 2

FARLEY 1

FARLEY 2

FITZPATRICK

FORT CALHOUN

FT ST VRAIN

GINNA

GRAND GULF 1

HADDAM NECK

HARRIS 1

2008

2012

2010

2026

2028

2030

2001

2026

2027

2014

2814

2017

2010

2010

2024

2028

2024

2814

2018

2026

2028

2027

2030

2038

28089

2009

2008

2018

2817

2026

2026

1984

2008

2008

2010

2026

2012

2012

2015

2008

2007

2088

2022

2007

2028

377

585

863

8as

190

96

3627

(a)

3226

2 4411

2401

2281

3627 (a)

1129

2213 (a)

0

0

2672

207

(a)

1241

(a)

1238

432

2490

617 517

0

1016

893

998

6366

298

140

2246

413

219

4392

3190

1999

1998

2009

2009

2011 1996

1998

2002

2001

1990

1991

1994

2006

1992

2826

2028

200

2016

1998

1997

2006

1996

2011

2011

1998

2000

1999

1997

208

2008

1997

1994

2000

1998

1997

2026

62

63

67

57

69

89

52

87

62

58

68

67

87

69

89

0

0

69

71

81

52

62

77

63

5a

62

62

62

72

62

62

67

62

62

67

62

0

2.80.7

2.27.7

3.00.7

2.99+7

6.24.7

6.24.7

2.00.7

8.68.7

8.86+7

3.22.7

3.19.7

3.08+7

8.68+7

3.43,7

6.22+7

0.00.0

0.00*0

3.31.7

6.72-7

3.74*79

2.23.7

2.07,7

68.76.7

2.2897

2.28.7

2.08.7

2.08+7

2.06*7

6.8687

2.08+7

2.0867

3.07.7

2.0687

2.08.7

4.00+7

2.08+7

0.00+0

1.09*7

1.04.7 1.69+,7

8.41.6

1.47+7

1.34.7

1 . 1657

4.66+7

4 • 66.7

1.53.7

1.34.7

2.27.7

2.09+7

6.02.7

1.17.7

3.38+7

0.00.0

0.00.0

1.08+7

1 . 20+7

1.80+7

1.13.7

7.08+6

3.77.7

5.83.6

9.93+8

9.01.8

9.46*8

2.9687

0.72+8

8.10.8

1.5667

1.21+7

9.01.8

2.38.7

1.04+7

0.00.0

6.98+6 4.96+6

8.70.8

2.51.8

4.40+8

3.64,6

8. 68.6

2.49.7

6.31.6

6.7906

1.64.7

1.44-7

3.01.7

4.22+6

2.21+7

8.00+0

0.00.0

3.70+6

2.71+6

8.90.8

5.87+6

2.64+6

2.16.7

1.68+8

1.58.6

4.94+8

4.08.6

4.49+6

1.64+7

2.31+8

1.91.6

8.09+.

7.24.6

4.88.6

1.17.7

6.44+8

0.08,0

9.70+6

1.12.7

1.97.7

1.87+7

2.48+7

2.48+7

4.86+0

6.18.7

1.31.7

1.62.7

2.02+7

1.89.7

6.1.87

1.97+7

2.84.7

0.680+ 0.00.0

2.16+7

2.03.7

1.18.7

9.37+6

8.89+8

3.22.7

1.21.7

1.21+7

8.08.6

6.47+6

8.89.6

3.84+7

4.86+0

3.23+8

1.79.7 8.89.8

4.86.6

2.98+7

0.08+6

0.60+0

3.80.8

3.71.8

6.62.6 8.*12.6

4.39+6

3.99+6

2.28.8

1 . 48.7

3.83.8

4.6686

8.94.6

8.16-6

1.66.7

4.29+6

1.09+7

0.00.0

0.00.0

4.27.8

2.96+8

4.30.6

3.67.8

2.30.6

1.07,7

2.18.8

2.18.6

3.00.6

2.28+6

3.08+6

1.03.7

1 . 34.8

8.48+6

6.87.6

3.92.8

1.79+6

8.26+6

3.16-6

0.00.0

1.6086 3.03.7

1.33.6 3.39.7

2.48-6 4.97.7

0.63.6 4.68.7

9.07.6 7.70.7

7.6506 7.70.7

1.12.8 2.6657

4.70+6 1.37*8

0.00+0

1.22.6 6.17+7

0.00.0

1.42.8 4.84.7

4.41.6 6.21.7

0.80+0

3.89+6 4.97+7

0.00.0

6.88.6 1.37.8

0.00+0

1.07+8 6.40+7

4.79+6 8.08+7

0.0+0

0.00.0 0.00.0

0.00+0 0.900.

9.88.5 6.48+7

4.88+6 7.75+7

0.00+0

1.67+6 4.92.7

1.4686 3.17+7

8.4656 2.96+7

4.09+8 9.98+7

4.4256 3.49+7

4.42.6 3.49+7

0.00.0

1.19.6 2.87.7

8.63.5 2.71+7

1.14+8 2.9567

.936.6 9.70.7

3.93+6 2.5657

2.38+6 2.38+7

2.16.8 4.88.7

1.84+6 2.95+7

0.*00.0

6.98+6 2.66+7

2.87+8 7.88+7

1.31-6 2.87+7

0..0+0 0.080+

0.00+0

1.47+7

1.41+7

2.24.7

1.16.7

1.91+7

1.74.7

1.38.7

6.96+7

1.91+7

1. 80.7

8.16.7

2.91.7

8.67+7

1.6807

4.4657

0.00.0

0.00*0

1.61+7

1.66+7

2.23.7

1.49.7

9.38+8

4.84+7

8.01÷8

0.01.0

1.29.7

1.13+7

1.2657

3.99+7

0.6868

6,96.6

2.14+7

1.88,7 1.68+7

1.08,7

3.18.7

1.38+7

7.68+6 8.28+6

1.11.7

3.17*6

6.31+6

4.39+8

7.*70+6

7.*63.6

7.21.6

2.08.7

1.83.7

5.29.5

2.89+7

0.00+0

0.00.0

4.69+6

3.20+6

1.08+7

7.33.

3.1968

2.60+7

2.02*6

2.*02+

8.13.6

4.98+6

5.63.6

1.88.7

2.70+8

2.16+8

2.02+7

9.086+

.13.

4.78+8

1.44.7

8.7658
TABLE A~m. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - SILO OPTION

(1983 DOLLARS) (cont'd)

ADD. YEAR I CO S T

SHUTDOWN STORAGE WHEN CONS. ------- - -m1----- I- 7 -m----- -- ---- PLANT NAME YEAR REq'D ADD&L ITIME CONSTRUCTION J 0M j TOTAL

(ASSEM- STOR. '(MON.)- ------ ---------- -.------- -

BLIES) NEEDEDI e% 6I lax10 e0% 5% 11% ex oI 5 le10 - - - -- w ----- - -- I-- - - -

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT 8

KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

MCGUIRE 2

MILLSTONE 1 o MILLSTONE 2

ui MILLSTONE 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE 1

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBOTTOM 8

PERRY 1

PILGRIM 1

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES 1

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM I

SALEM 2

2009

2012

2026

1978

1980 2008

2015

2014

2002

2022

2028

2024

2029

2008

2021

2023

2010

2015

2025

2007

2005

2026

2018

2020

2013

2013

2014

2004

2011

2024

2025

2028

2008

2008

2026

2008

2007

2008

2008

2008

2007

2007

2008

2007

2025

2016

2020

* 2874

(a)

2820

0

0

493

536

679

205

9824

4098

4236

832

966

989

2480

823

541

355

884

1971

1866

(a)

2102

(a)

1021

912

836

1117

1121

1121

1812

1689

2648

1512

849

(a)

1142

(a) 503

(a)

228

6e6

2452

1007

1183

2000 60 3.57.7 1.56.7

200? 60 3.58,7 1.10.7

1994 52 2.21.7 1.29.7

2004 53 2.38$7 8.37+6

1999 62 2.18.7 1.00+.

1992 52 2.086.7 1.38.7

1990 98 1.01.8 8.9127

1995 66 4.89.7 2.81.7

1998 67 4.79.7 2.31.7

1996 53 2.2687 1.20+7

2005 58 3.21.7 1.10.7

2006 58 8.25,7 1.06.7

1987 58 3.19.7 2.51+7

1997 55 2.74.7 1.38.7

2018 53 2.34.7 4.68+8

2004 52 2.06.7 7.41+6

1996 52 2.06+7 1.09.7

2011 56 2.86.7 7.28*6

1999 70 5.39.7 2.47.7

1989 72 5.82+7 4.34.7

1991 59 3.33.7 2.25.7

1994 52 2.08.7 1.21+7

1988 55 2.71.7 2.12,7

2005 58 3.27+7 1.12.7

2006 58 3.27.7 1.07.7

2007 58 3.27.7 1.01.7

1997 55 2.73.7 1.38.7

1997 54 2.65.7 1.29.7

2009 59 3.31.7 9.32+.

1993 53 2.44.7 1.50.7

1995 55 2.89.7 1.50.7

1993 57 3.08.7 1.89.7

2005 52 2.06,7 7.06.6

2004 52 2.08.7 7.41.8

1990 64 2.0.507 1.78.7

2007 58 3.25.7 1.01.7

1997 59 3.29,7 1.66.7

2001 60 3.817 1.50+7

7.06.6 9.49.8

3.59.8 1.99+7

7.75.6

8.15+8

4.745.8

8.76+6

4.81+7

1.49.7

1.15.7

6.53* 8

3.94.6

8.63.8

2.00+7

7.21.6

1.01.8

2.79.6

S .98+8

1.989.6

1.17.7

1.02.7

9.64.8

1.2047

0.09.6 8.89+7

8.52.7 3.81+7

1.62+,7 1.788,7

2.32.7

1.71.7

7.91.6

2.42.8

7.27.6

1.45.7

2.49+7

8.27.8 1.20-8 4.52.7

0.00.0

3.98.8 8.92.5 5.62+7

0.00.0

0.00.0

4.39.6 2.02.8 3.23.7

2.61.8 7.89.5 3.29+7

4.00.6 1.39.6 3.44+7

4.02.6 2.11+6 2.87.7

2.38,7 1.02+7 1.68.8

0.00+0

1.02-7 3.82.8 8.21,7

9.21.8 2.796 8.0.007

4.03,6 1.89.6 3.29.7

3.74+8 9.71.5 4.88.7

3.73.8 9.10.5 4.98.7

1.12+7 8.12+8 5.51+7

5.82+8 2.05+6 4.45.7

1.25.6 2.18.5 3.13.7

7.90,6 2.72.5 2.30+7

8.05.8 1.3568 2.79.7

2.56." 5.10.6 4.31.7

7.27.8 2.39.0 7.88.7

0.00.0

1.41#7 6.94.8 9.10÷7

0.00+0

9.36.8 4.25.8 5.69.7

3.8658 1.74.6 2.87.7

1.00.7 5.22.8 4.89.7

4.20+6 1.0568 5.20.7

4.01,6 9.61.5 5.21.7

3.82.6 8.86.5 5.21.7

3.99.8 1.83.8 3.78.7

3.86+8 1.576 3.68+.7

3.24+. 8.89+5 5.05.7

5.73+8 2.64+8 8.79.7

4.86,8 2.05.8 8.82+7

0.00.0

.35+.6 2.92+8 4.67+7

0.*00+0

5.14.5 1.72+5 2.22,7

0.00+0

1.08.6 3.4865 2.38.7

7.30.8 3.75.8 4.06+7

3.88+8 8.46,5 5.08.7

6.23+8 2.25+8 5.23.7

5.32+8 1.59.8 5.62.7

1.89.7

1.49,7

1.73.7

1.*10.7

1.4047

1.78+7

9.24,7

8.86.7

8.2+2.7

1 . 60,7

1.47.7

1.4387

3.68.7

1.94+7

6.98.8

8.228.6

1.40+7

9.84+6

8.20+7

5.75.7

3.19.7

1.58.7

8.12+7

1.54.7

1.47+7

1. 39.7

2.778+7

1.88+7

1.28.7

2.07.7

1.97.7

2.58.7

7.567+8

8.44.6

2.51.7

1.38+7

2.28.7

2.03.7

8.20.6

4.48.6

9.77.6

8.92.8

8.14+8

1.09.7

5.83.7

1.86.7

1.43.7

8.22,8

4.91.6

4.54*8

2.61-7 9. 28#8

1.23.8

8.06,6

7.33,6

2.49+.

1.41.7

3.97.7

1. 98.7

8.98+6

2.20.7

6.06.6

4.81.8

4.19.8

8.82+6

S. 28+.

3.47.8

1.20.7

1.06.7

1.48.7

2.71.6

3.14+.

1.88.7

4.1*.6

1.09.7

8.08+8

3.28.7 8.28,7

1.55.7

7.24.8 1.688.7

4.01.8

3.68#6

.32+.8

7.19+.

8.71.6

2.78.8

9.40.8

8.57.8

2.3867

8.08+8

2.218.7

1.93.7

1.94+7

1.94.7

1.05.7

1.0127

1.74.7

1.35.7

1.13+7

1.194.7 1.49.7

2.64+6 1.62.8

2.79.8

1.2897

8.88.8

8.49.8

3.238.6

1.56.7

1.83.7

1.94.7

2.01.7
TABLE Asa. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

IN THE CURRENT HIGH DENSITY RACK CONFIGURATION - SILO OPTION

(1983 DOLLARS) (cont*d)

----------------------------------------------------------------------------------------------------------------------

I ADD. YEAR

I SHUTDOWN STORAGE W4EN CONS.

PLANT NAME I YEAR REQ'D ADDIL TIME

I (ASSEM- STOR. (MON,) IBLIES) NEEDED

COST

CONSTRUCTION . 0 Mi TOTAL

-- ---- e --- --o---- 1-x 6I loxs

E SAN ONOFRE 1

E SAN ONOFRE 2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAN 1

A SEQUOYAN 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSQUEHANNA 1

8 SUSQUEHANNA 2 •o THREE MILE ISL

o• TROJAN

E TURKEY PT a

E TURKEY PT 4 a VOCTLE 1

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2012

2013

2031

2021

2022

2027

2027

2028

2010

2023

2024

2012

2013

2022

2024

1 2008

2011

2007

2007

2027

2028

2012

2023

2024

2026

2027

2026

2001

2008

2008

23862

1281

2680

(a)

2836

258

268

1182

1128

781

97

(a)

7288

(a)

75

373

384

(a)

2495

(a)

1088

4018

1143

2891

38

1295

(a)

1985 69 5.30.7 2.96.7 1.6897 6.20.6 2.67+6

2098

1996

200

2023

2024

1987

2001

2008

2012

200

2008

2004

2802

2008

1999

1998

200

201

2008

1999

1995

62

79

59

62

62

s8

67

so

62

80

62

62

62

78

62

608

69

79

67

62

02

3.81-7

7.08.7

3.38.7

2.08.7

2.08.7

3.19.7

3.10.7

2.809.7

2.08*7

7.41.7

2.80.7

2.00.7

2.68+7

6.68.7

2.08.7

4.69+7

3.31.7 7.10+.7

3.00+7

2.00*7

3.89+7

1.18.7

3.94.7

1.09.7

2.93.0

2.79.8 2.62+7

1.29.7

8.28.8

6.02+8

3.23.7

6.72.6

7.41.6

8.17.6

2.1867

9.4.68

2.21.7

1.08.7

2.96+7

8.865+

9.42+1. 2.17+7

3.52#8

2.28.7

3.76+86

4.6856

4.16+6

2.01.7 56,68.86

2.69+*8

1.30+8

1.47.7

2.31.6

2.79.8

3.38.*8

7.406+

4.49.+

1.10+7

3.69+8

1.28.7

2.77.0

4.49.0

1.24.7

2.60.7

3.88.7

2.16+7

3.23.8

3.23+0

2.32.7

2.20.7

1.64.7

0.00.0

3.38.7

1.62.6

6.68+8

4.04.6

3.06.7

1.06.7

2.99+7

1.84.7

3.69.7

1.68.7

1.82.8

1.43.7

4.33+8

1.220.7

4.29.6

4.07.6

3.88+5

1.12.7

6.48.6

3.07+6

0.00+0

0.77.6

4.89.6

1.88+8

1.38.8+

6.08.6

3.48+6

8.12.6

3.89+8

8.68.+8

3. 28.0

8.88+*6

6.73+6

1.31+6 6.82+7

0.09

0.00.0

8.91+6 6.31.7

4.386+8 1.18.8

0.60.0

9.93.6 6.62.7

6.88.4 2.38.7

6.16.4 2.38+7

8.12.8 6.61.7

1.68.6 6.38.7

6.94.6 4.34.7

0.00+0 2.08.7

0.00+0

2.8656 1.08+8

0.06+0

1.67.6 2.22.7

6.32+6 2.63.7

6.01+6 2.46+7

0.00+0

1.41.0 9.74+7

0.00.0

1.2568 3.11.7

2.60.6 7.68*7

9.37+6 6.16.7

2.42.8 1.07.8

0.00*0

7.380.6 4.68*7

3.0.56 2.22.7

2.48+8 6.32+7

0.0+.0

1.77.8 4.86.9

3.21.7 1.82+7

1.6507

6.14+7

1.62+.7

3.34.8

3.18.8

3.84.7 1.*84-.7

1.14+7

6.02+6

4.11+7

7.21.8

9.09.8

9.66.6

2.79+7

1.29.7 8 .02.*7

1.47.7

3.81.7

1.21*7

1.01.7

2.74.*7

4.41.8

2.704.7

4.74.8

6.13.6

4.7.+6

2.62.7

7.18.8

3.28.6

1 • 30.8

1.74.7

2.47.6

3 .32.8

3.88.6

8.*87,6

S .74.8

1.38.7

4.83.6

1.62.7

3.60+*6

4.80+0

1.49+7

---------------------------- m -------- 3.24.9 1.49.9 7.79.8 1.81+9 4.79+8 1.97.9 9.65.8

A INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

B INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

E INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

(a) INCLUDED IN UNIT 1
TABLE Abf. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - SILO. OPTION

(19S DOLLARS)

----------------------------------------------------------------------------------------------- ------ -------

ADO. YEAR CO0S T

SHUTDOWN STORAGE WHEN CONS. - - --------------

PLANT NAME YEAR REQ'D ADOIL TIME CONSTRUCTION O08M' TOTAL

(ASSEM- STOR. (MON.) . ...- .. .... .

BLIES) NEEDED ex I 1% 6% I 5; 5% i 1 o6 1- 16%

-ee----------------- ------ -- -- - - - - - - - - - - - - - - -

ARK NUCLEAR I 2068 787 (b) 55 2.77*7 2.17.7 1.72.7 1.91.7 9.34.6 5.65.6 4.80.7 3.1.+7 2.23*7

ARK NUCLEAR 2 2612 973 1989 57 3.05+7 2.27.7 1.72.7 2.26.7 9.99+6 4.9786 5.33*7 3.27+7 2.22.7

BEAVER VALLEY 1 2618 1287 (b) 62 3.85.7 2.99.7 2.35+7 3.0687 1.27.7 6.31.6 6.91.7 4.28.7 2.98.7

BEAVER VALLEY 2 2028 129 2969 82 3.89.7 1.89.7 7.67.6 2.85.7 8.88.6 1.9.06 6.7387 2.38.7 9.65.6

BELLEFONTE 1 2628 2404 2906 75 8.4067 2.79*7 1.27+7 4.60.7 9.29+6 2.83.6 1.64.8 3.72.7 1.53.7

BELLEFONTE 2 2030 2404 2602 75 6.46*7 2.63+7 1.0657 4.0987 8.43.6 2.18.8 1.04.8 8.37.7 1.27+7

BI1 ROCK 1 2061 175 1992 52 2.08.7 1.33.7 8.78.8 7.27.6 3.76*6 1.97.6 2.79.7 1.70+7 1.67'7

A BRAIDWOOD 1 2026 4383 1990 9 1.065.8 7.69.? 4.99.7 7.68*7 2.56.7 1.0667 1.82.8 9.59*7 5.96.7

A BRAIDWOOD 2 2627 (a) 1996

B BROWNS FERRY 1 2014 4594 1998 68 6.14.7 2.47.7 1.23.7 2.04.7 6.68.8 2.39+6 7.18*7 3.14.7 1.47.7

B BROWNS FERRY 2 2014 (a) 1998

BROWNS FERRY 3 2017 3353 1995 62 3.97.7 2.21.7 1.27.7 2.44.7 8.12.6 3816.8 6.41.7 3.62.7 1.68.7

BRUNSWICK 1 2016 8153 (b) 82 3.8127 2.96+7 2.33.7 2.39.7 1.12.7 5.91.6 6.2067 4.68.7 2.92.7

BRUNSWICK 2 2010 3633 (b) 81 3.68.7 2.87.7 2.26.7 2.35.7 1.16.7 6.82.8 6.03+7 3.97.7 2.84.7

A BYRON 2 2026 (4) b

CALLAWAY 1 2024 1633 1996 65 4.5607 2.38.7 1.36.7 3.32.7 9.3656 3.19+6 7.82.7 3.32.7 1.6247

8-. B CALVERT CLF 1 2014 2789 (b) 75 8.34*7 4.68.7 3.60.7 3.76.7 1.60.7 8.18.6 1.60.8 6.28+7 4.31.7

B CALVERT CLF 2 2016 (a) b

CATAWBA 1 2925 226 2021 52 2.8667 3.23+6 6.52+5 3.23.6 4.49+5 6.05.4 2.38.7 3.89+6 6.21.5

CATAWBA 2 2026 216 2628 52 2.86*7 2.93+6 4.56+5 2.4286 3.13+5 4.44+4 2.30.7 3.24.8 5.6065

CLINTON 1 2027 3260 2696 62 3.89.7 1.89.7 7.68.6 2.96.7 7.00.6 2.66.6 8.84.7 2.39+7 9.6+88

B COMANCHE PK 1 2630 2061 2610 78 7.64.7 1.88.7 6.37.8 2.99*7 4.97.6 9.67.5 1.00.8 2.38.7 6.34.6

o COMANCHE PK 2 2036 (a) 2610

A COOK 1 2009 2909 1991 70 5.63+7 3.74.7 2.68*7 2.40+7 1.05.7 5.09.8 7.93.7 4.79*7 3.89.7

A COOK 2 2009 (a) 1l91

COOPER STN 20098 1702 1993 55 2.85.7 1.63.7 1.62.7 1.41.7 6.98.6 2.75.6 4.66.7 2.23.7 1.39.7

CRYSTAL RVR 3 2618 848 1999 54 2.59.7 1.19.7 5.63.6 1.58.7 4.79.6 1.62.6 4.17.7 1.67+7 7.25.6

DAVIS-BESSE 1 2617 2866 1998 81 7.54.7 6.41.7 3.94.7 4.48,7 1.83.7 8.98.8 1.26.8 7.24.7 4.84.7

DIABLO CANYON 1 2625 772 20068 6 2.83.7 9.22.6 3.16.6 1.83+7 3.89+8 9.61.6 4.68+7 1.30+7 4.08+6

DIABLO CANYON 2 2025 772 2006 56 2.83.7 9.22.6 3.16.6 1.83.7 3.8066 9.01.6 4.68.7 1.39.7 4.68+0

DRESDEN 1 1984

DRESDEN 2 2008 1647 1992 54' 2.52.7 1.62.7 1.67.7 1.46.7 6.39.6 3.03.6 3.99+7 2.26+7 1.37.7

DRESDEN 3 2908 1325 1994 62 2.23+7 1.31+7 7.82.6 1.19.7 .4.93.6 2.2098 3.42.7 1.89.7 1.00+7

DUANE ARNOLD 2016 116e 1991 54 2.47.7 1.67.7 1.15-7 1.72.7 7.41.8 3.53.6 4.19.7 2.41.7 1.5607

ENRICO FERMI 2 2026 8459 1996 77 8.84.7 4.86.7 8.61.7 5.15.7 1.71.7 7.28.8 1.20+8 6.67+7 4.24.7

FARLEY 1 2012 768 1997 65 2.7127 1.37.7 7.15.6 1.42+7 4.97.6 1.9.86 4.13.7 1.87.7 9.05+6

FARLEY 2 2012 648 1999 53 2.37.7 1.09+7 5.1868 1.15.7 3.81.8 1.37+8 3.52+7 1.47.7 6.5386

FITZPATRICK 2616 2966 1991 81 3.65+7 2.47.7 1.70.7 2.55.7 9.94.8 4.46.8 6.26.7 3.46.7 2.15+7

FORT CALHOUN 2008 683 (b) 53 2.38.7 1.80.7 1.43.7 1.48.7 7.68+6 4.33.6 3.78.7 2.57.7 1.86.7

FT ST VRAIN 2067

GINNA 2006 411 1994 62 2.0867 1.21.7 7.24+8 9.76+8 4.19.8 1.93+8 3.03+7 1.83.7 9.17+6

GRAND GULF 1 2922 5464 1992 72 5.91.7 3.81.7 2.68+7 4.13.7 1.36+7 5.51.8 1.66.8 6.17.7 3.05.7

HADDAM NECK 2007 631 1990 53 2.38+7 1.69.7 1.22.7 1.51+7 7.11+6 3.65+8 3.89.7 2.4067 1.59.7

HARRIS 1 2026 6 2026 6 0.66.6 6.66.0 6.9.6 0.69.6 9.666 60.6.008
TABLE Ahb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - SILO OPTION

(1983 DOLLARS) (cont'd)

ADD. YEAR COS T

SHUTDOVWI STORAGE WHEN CONS. - I ........ i.

PLANT NAE IYEAR (ASSEM- REQ'D ADD'L STOR. (UON.).-- TIME CONSTRUCTION j 0 6 M" TOTAL ------------------- -------- P ABLIES)NEEDED 1 106 - 0 I , Ia 0% Io 1a0l I~~~ .....I...- ................ sI 1 

B HATCH 1

B HATCH 2

HOPE CREEK

HUMBOLDT BAY

INDIAN PT 1

INDIAN PT 2

INDIAN PT a KEWAUNEE

LACROSSE

B LASALLE CTY 1

B LASALLE CTY 2

LIMERICK 1

LIMERICK 2

MAINE YANKEE

MCGUIRE 1

UCGUIRE 2

MILLSTONE 1

MILLSTONE 2 00 3

MONTICELLO

NINE MILE PT 1

NINE MILE PT 2

A NORTH ANNA 1

A NORTH ANNA 2

A OCONEE I

A OCONEE 2

OCONEE 3

OYSTER CRK 1

PALISADES

PALO VERDE 1

PALO VERDE 2

PALO VERDE 3

PEACHBOTTOM 2

PEACHBDTTOM 3

PERRY 1

PILGRIM I

A POINT BEACH 1

A POINT BEACH 2

A PRAIRIE ISL 1

A PRAIRIE ISL 2

B QUAD CITIES I

B QUAD CITIES 2

RANCHO SECO 1

ROBINSON 2

RVR BEND 1

SALEM 1

SALEM 2

2009

2012

2028

1976

1980

200

2016

2014

2002

2022

2023

2024

2029

2008

2021

2023

2010

2016

2026

2007

2006

2028

2018

2020

2013

2013

2014

2004

2011

2024

2026

2026

2008

2008

2028

2008

2007

2008

2808

2008

2007

2007

2008

2007

2026

2016

2020

4050

(a)

3748

901

992

801

301

11144 * (a)

4992

6116

1070

1397

1421

2872

1291

1046 835

1252

2533

2461

(a) 2641

(a)

1381

1424

1039

1627

1631 1831

2724

2469

3444 1898

1137

(a)

1602

(a)

640

956

3220

1481

1667

1998

2998

2001

(b)

1994

1993

1987

1988

1991

1987

1997

1998

2007

1998

1990

2007

1992

1992

1989

(b)

1998

1997

1998

1991

1991

2003

1988

1990

1990

1988

1988

2082

2002

1992

(b)

2001

1989

1992

68

64

6758

64

62

100

70

71

67

63

84

680

6069

62

6259

77

78

63" 53

676464

64

59

s8

63

e6

68

81

63

5467

62

64

66

4.63+7 2.48+7

4.38+7 1.81+7

1.34.7 1.66+7

7.88"6 2.91+7

8.00+8 2.48"0 6.19.7 3.8+.7

6.81+6 1.g086 7.27+7 2.49.7

8.08+7

3.26.7

2.61+7

2.08+7

1.11+8

6.66+*7

6.64+7

3.00.7

4.12+7

4.17.7

3.49+7

3.66.7

3.36.7

2.06.7

2.19.7

3.29+7

6.77+7

2.40+7

1.91.7

1.60.7

1.67+7

7.38.7

4.16.7

3.81.7

2.37.7

2.0887

2.01.7

2.7387

2.77.7

1.04.7

9.93+6

1.68.7

1.02.7

4.36+7

1.90.7

1.14.7

1.01+7

1.3867 6.91-7

9.16+7

2.63+7

1.+9,7

1.08.7

9.99+6

2.1867

2.19+7

3.42*6

4.94*6

1.12+7

3.34+6

2.87+7

1.79.7

2.14.7

1.96+7

1.21.7

6.9657

4.80.7

6.11+7

2.07.7

2.71.7

2.84+7

2.90+7

2.84.7

1.86.7

7.27.6

1.28+7

1.94.7

3.81,7

9.10.8

7.62.8 7.33,6

6.9*98

2.69.7

1.73+7

1.64+7

1.04+7

7.8868

7.70+6

1.08+7

1.21+7

3.73+8

2.7686

6.21.8

3.82,6 1.36.7

6.08+6

3.08+6

8a. 10.6

4.20.6

1.22.7

8.02.8

8.11-8

6.82+6

2.67.6

2.47+6

6.89.6

6.03.6 8.67+6

1.11.6

3.29.8

8.6865

5.69.6

4.86*7

6.40+7

4.6.*7

3.27.7

1.81.8

1.04.8

1.08+8

6.07.7

6.83.7

7.01.7

6.79.7

6.39.7

6.2127

2.79.7

3.45+7

6.23.7

1.0•.8

3.81+7

2.67+7 2.99+7

2.38+7

9.97.7

6.89+7

6.35.7

3.41+7

2.87.7

2.78.7

3.81.7

3.98+7

1.41.7

1.27.7

2.18+7

1.40.7

6.72+7

1.69+7

9.73*6

2.41.7 1.46+7

1.32.7

1.78,7

6.23+7

3.96*7

3.24.7

2.48.7

1.3657

1.26+7

2.73+7

2.79.7

4.28.6

8.06*6

1.4657

4.21+6

3.44+7

7.02,7 6.10.7 3.7657 3.72+7 1.64+7 8.39+6 1.07+8 6.74+7 4.69.7

4.10.7

2.34.7

3.05+7

4.24.7 4.26+7

4.26.7

3.44+7

3.24+7

4.07*7

2.7657

3.1657

3.1687

1.76-7 2.29+7

2.26+7

2.14+7

2.04+7

2.33.7

2.19+7

1.64.7

2.16.7

2.24.7

2.47.7

1.32.7

1.89.7

1.23+7

1.12.7

1.82.7

1.680+7

1.61+7

1.08.6 1.71-7

I1.8627

2.93.7

1.32.7

2.28.7

3.21.7

3.21.7

3.21.7

1.77.7

1.72+7 2.68#7

1.91,7

1.7127

1.27.7

6.880.

1.06,7

9.06+8

8.63*6

8.22+0

7.92*8

7. 74*8

6.71+8

9.31.6

8.0586

6.40+8

3.77.6

6.47.6

3.09.6

2.81.8

2.686+ 3.69*6 8.89+6

1.48.6

6.04+6

4.13+6

7.03.7

3.6887

6.3a+7

7.46*7

7.48.7

7.4687

6.21+7

4. 98.7

8.86+7

4.66.7

4.8687

4.4837

2.43.7

3.44.7

3.16.7

2.86.7

3.122+7

2.96+7

2.11,7

3.09.7

3.6+7

3.11,7

1.70+7

2.44+7

1.64.7

1.4+.7

1.28.7

1.99.7

1.89.7

7.64+6

2.21.7

2.03.7

3.65.7 2.8657 2.2657 2.13.7

2.40.7 9.6086 3.92.6 4.46+0

1.04.7 6.63.6 6.78.7

1.63+6 6.62+6 2.86+7

3.89,7 2.81,7

1.10,7 4.47+8

2.67.7

3.03.7

3.90+.7

4.33+7

4.7657

1.6867

2.37+7

1.6827

3.23.7

3.0687

1.0997

1.88+7

7.01.6

2.44.7

2.02+7

1.48.7

1.88+7

2.63+7

3.13+7

3.42+7

8.46.8

9. 37.6

6.29.6

1.27.7

1.17.7

3.07+0

6.14+6

1.77-6

6.04+6

4.82.8

4.06.7

4.91.7 8.63+7

7.46.7

6.17.7

2.31,7 3.81-7

2.2657

4.6507

4.23+7

1.40.7

2.39.7

8.78.6

3.04.7

2.6*57
TABLE Afb. COST FOR ADDITIONAL SPENT FUEL STORAGE CAPACITY

AFTER CONVERSION TO LOW DENSITY RACK CONFIGURATION - SILO OPTION

(1983 DOLLARS)(cont'd)

------------------------------- w---------------------------------------- w--------------

ADD. YEAR

SHUTDOWN STORAGE WHEN CONS.

PLANT NAME YEAR REQ'D ADtD'L TIME

(ASSEM- STOR. (MON.)

BLIES) NEEDED -------- 7-------- -------------- --------

CONSTRUCTION II

COST

OSM I TOTAL

a

0o - I 5 lO- 10 --- I r o0x --- 10% ---

E SAN ONOFRE 1

E SAN ONOFREi2

E SAN ONOFRE 3

SEABROOK 1

A SEQUOYAH 1

A SEQUOYAH 2

SHOREHAM

SOUTH TEXAS 1

SOUTH TEXAS 2

ST LUCIE 1

ST LUCIE 2

SUMMER 1

A SURRY 1

A SURRY 2

B SUSQUEHANNA 1

B SUSQUEHANNA 2

to THREE MILE ISL

to TROJAN

E TURKEY PT 3

E TURKEY PT 4

B VOOTLE 1

B VOOTLE 2

VT YANKEE 1

WASH NUCLEAR 2

WATERFORD 3

A WATTS BAR 1

A WATTS BAR 2

WOLF CREEK 1

YANKEE-ROWE 1

A ZION 1

A ZION 2

TOTAL

1999

2012

2013

2031

2021

2022

2027

2027

2028

2010

2023

2024

2012

2013

2022

2024

1 2008

2011

207

2007

2027

2028

2012

2023

2024

2025

2027

2025

2001

2008

2008

3172

1845

8400

(a)

3371

670

1638 570 1838

1558

1169

574

(a)

861

816

(a)

3251

4842 1871

3411

(a) 1813

264

1943

(a)

1989

1989

1989

200

1989

1989

2000

2017

2018

(b)

1992

1999

2005

2005

1995

1995

1997

1998

1995

1995

2000

2000

1993

1994

1997

1994

1994

1999

1992

1988

1998

77 6.78+7 4.95.7 3.67+7 1.47.7 8.45.8 5.0806 8.25*7 5.80+7 4.18.7

86

87

62

55

54

62

82

60

53

87

53

54

5s

85

54

89

64

87

62

52

70

4.70+7

8.73.7

3.97+7

2.83.7

2.82.7

3.96+7

3.81+7

3.80.7

2.41.7

8.67+7

2.28.7

2.81+7

2.91+7

8.38+7

2.56+7

5.18+7

4.32.7

8.78+7

3.93*7

2.06+7

6.42+7

2.05.7

8.11.7

1.7 7.7

5 .01,6

4.75.6

3.08.7

2.46+7

1.65+7

8.25.8

4.83+7

1.15+7

1.26.7

1.82+7

3.65.7

1.57.7

3.03.7

2.18+7

5.1227

1.80.7

1.47+7

4.07+7

9. 30+6 4.86,7

7.85*6

1.03+8

9.32.6

2.40+7

1.62+7

7.8e65

2.96.6

2.76*7

6.*01+6

6.25.6

9.27+6

1.66.7

9.89.6

1.82.7 1.1447

3.07.7

8.55+6

1.0867

3.1207

3.76.7 5.61.7

2.99.7

9.35,6

9.338.6

.2.4387

3.37,7

2.85.7

6.26.6

4.70.7

9.51.6

1.21.7

1.17+7

4.52.7

1.75.7

3.72.7

3.13.7

5.46.7

2.86.7

8.89+6

2.83+7

8.26.6

2.07.7

7.08.6

1. 37,6

1.31.8

1.14.7

1.09.7 6.*84,6

1.77.6

1.42.7

3.683.6

4.2126

4.81,6

1.07+7

6.85.6

1. 14.7

8.57*6

1.80.7

7.26.8

4.77*8

1.29+7

2.28.6

9.43.6

2.02.6

2.25.5

2.04+5

6.02+6

4.37+8

2.09.6 5.35+8

5.12.6

1.48.6

1.58.6

2.12.8

3.06.6

2.9896

4.22+8

2.82*6

5.85.6

2.20+6

2.89+8

6.968+

8.46.7

1.43.8

6.96.?

3.57+7

3.55,7

8.39.7

7.18.7

6.25.7

3.04.7

1.34.8

8.23.7

3.82+7

4.08.7

1.29.8

4.31+7

8.90.7

7.45+7

1.42*8

6.79.7

2.95.7

8.05.7

2.88.7

8.18.7

2.44.7

6.38.6

6.06+6

4.20+7

2.33*7

1.00.7

6.25+7

1.51.7

1.6887

2.1*+.7

4.72.7

2.26.7

4.17.7

8.04+7

8.72.7

2.53.7

1.95+7

5.3687

1.18.7

5. 29+7

9.87.6

-1.26.6

1.14.6

8.00.7

2.08+7

9.94.6

3. 50*8

3.27+7

7.49.8

7.83.6

1.14+7

1.96.7

1.29.7

2.24.7

1.42.7

3.68+7

1.08.7

1.33.7

3.80+7

------------------------------------------------------------------------------------------------------ 4.00+9 2.37.9 1.53+9 2.4869 8.67*8 3.71.8 6.48.9 3.23+9 1.90+9

A

B

E

INDICATES COMMON POOL SHARED BY TWO REACTORS: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS CONNECTED BY TRANSFER CANAL: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

INDICATES POOLS REQUIRING CASK TRANSFER: CAPACITIES AND INVENTORIES ARE COMBINED WITH ONLY ONE FULL CORE RESERVE

I . INCLUDED IN UNIT 1.

NEED ADDITIONAL SPACE AS OF 1986.

NBC FORM 3x 62441

NACM I M2.

3201.202

U.ILL NUCLEAR REGULATORY COMMISSION

BIBUOGRAPHIC DATA SHEET

1. REPORT NUMBER IAWaipdaV TIOC. MO 1,W ". MOW~'

NUREG/CR-5281

BNL-NUREG-511180

sea P&SMUCTIONS Ohl THE RevERSt.

*. TITLE AND SUSTITLE &3 LEAVE BLANK

Value/Impact Analyses of Accident Preventive and

Mitligative Options for Spent Fuel Pools 4. DATE REPORT COMPLETED

MONTN YEAR

* AUToRIS] January 1989

J.H. Jo, P.F. Rose, S.D. Unwin, V.L. Sailor, . " DATE REPORT .53U'

K.R. Perkins, A.G. Tingle MoNr" YE"A

March 1989

1. PERFORMING ORGANIZATION NAME AND MAIUNG ADVRES3 tIhei go C.OP .. PROJECTITAKMDORK U4NIT NUMIER

Brookhaven National Laboratory a. PI OR GRANT NUMBER

Upton, NY 11973 FIN A-3963

Id. SPONSORING ORGANIZATION NAME ANO MAILING ADDRESS I•KAWh Z* i " I I& TYPE OF REPORT

Division of Safety Issue Resolution Final

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission 1L P• RO1 COVEI RE f,, ,,,

Washington, DC 20555

12. SUPPLEMENTARY NOTES

IS& ABSTRACT R- wr* e11at

A series of value/impact studies were performed for accident preventive and mitigative options intended to reduce the risks posed by the storage of spent fuel at nuclear

power plants In spent fuel storage pools. Options studied included limited low-density

reracking of spent fuel, installation of water sprays above the spent fuel pool, and the

installation of redundant cooling and/or makeup systems. The results of these studies

indicated that the measures were in general not likely to be cost effective. The reason

for this is due to both the low likelihood of a spent fuel pool accident that could

result in a significant radiological release and high cost of proposed modifications.

These insights are largely contingent upon compliance with guidelines developed for

licensees to assure the safe handling of heavy loads in the vicinity of spent fuel pools

thus reducing the likelihood of the structural failure of the pool and rapid loss of

water inventory due to a cask drop event.

I4 DOCUMENT ANALYSIS -. KEYWOROSIOESCRIPTORS

Spent Fuel Pools

Value/Impact Analysis

Rerackitng

Zircaloy Fire

Generic Safety Issue 82

b. IDENTIPIERSIOPEN.ENOEO TERMS

IS AVAILAIITY

STATEMENT Unlimited

IS. SECURITY CLASSIFICATION

(Thom W"i

Unclassified

r('rho mo

Unclassified

1?. NUMIER OF PAGES

Is. PRICE

d

111-'n If/. A/-/,.,
-

.

w