ML17139A885
| ML17139A885 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/17/1982 |
| From: | Saltzman J NRC OFFICE OF STATE PROGRAMS (OSP) |
| To: | |
| Shared Package | |
| ML17139A883 | List: |
| References | |
| B-90-A-01-DRFT, B-90-A-1-DRFT, NUDOCS 8207300533 | |
| Download: ML17139A885 (10) | |
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UNITED STATES NUCLEAR, REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-387 AMENDMENT"TO'NDEMNITYAGREEMENT NO 'B-'90 -- -.
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Effective July 17, 1982,. I'ndemnity Agreement No. B-90,dbetween Pennsylvania Power and Light Company and Al.legheny Electric Cooperative, Inc. and the Nuclear Regulatory Commission,'ated September'10, 1981, is hereby amended as follows:
Item 2a. of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor Item 2 Amount of financial protection'.
$1,000,000 (From 12:01 a.m.,
to 12 midni'ght, inclusive) d
$160,000,000*
(From 12:01 a.m.,
", Item 3 of the Attachment to the indemnity agreement is deleted and the following substituted therefor!
Item 3 - License.number or numbers September 10, 1981 July 16, 1982 July 17, 1982 in its entirety SNM-1878'PF-14 (From 12:Ol a;m.,
September 10, 1981 to 12 midnight July 16 1982 inclusive)
(From 12:01 a.m.
July 17 1982
)
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8207300533 820717 PDR ADOCK 05000387 p
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Item 5,of the Attachment to the. indemnity. agreement is amended by adding the fol.lowing:
Nuclear'Energy Liability Policy (Facility Form) No.-MF-107 issued by Mutual Atomic Energy Liability Underwriters.
FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Je,ome Sal tzman, A sistan Director
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State and Licens Relations
'ffice of State Programs Accepted 1982 By ennsy van>a ower an sg t ompany Accepted
1982 By egheny E ectric-Cooperative, nc..
ASSESSMENT OF THE EFFECT OF LICENSE DURATION ON MATTERS DISCUSSED IN THE FINAL ENYIRONMENTAL STATEMENT FOR THE SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 (Dated June 1988.)
INTRODUCTION The Final Environmental Statement (FES) for the operation of the Susquehanna Steam Electri'c Station Unit Nos.
1 and 2 was published in June 1981.
At that time it was staff practice to issue operating licenses for a period of 40 years from the date of the construction permit.
This was approximately 30 years of operating life.
By letter dated June 8, 1982, the applicant requested that the operatin'g license for their Susquehanna Steam Electric Station, then under consideration by the staff, have a duration of 40 years from the date of issuance.
DISCUSSION The staff has reviewed the Susquehanna FES to determine which aspects considered in the FES are affected by the duration of the operating license.
In general, the FES assesses various impacts associated with operation of the facility in terms of annual impacts and balances'hese against the anticipated annual energy production benefits.
Thus, the overall assessment and conclusions would not be dependent on specific oper-ating life.
There are,. however, four areas in which a specific operating life was assumed:
1.
Project costs are based on a 30-year levelized cost.
2.
Radiological assessments are based on a 15-year plant mi dlife.
3.
Uranium fuel cycle impacts are based on one initial core load and 29 annual refuelings.'.
Uranium availability is evaluated through 30 years of operation.
These were assessed to determine whether the use of a 40-year operating period rather than a 30-year operating period would significantly affect our assessment concerning these areas.
EYALUATION:
The staff's appraisal of the'significance of the use of 40 years of operation rather than 30 as it affects these four areas is presented in the following discus-sions:
1.
Projected Costs - The projected costs of the facility, which include the cost of decommissioning, are based on a 30-year operating life and are levelized over'that period of time.
The use of a 40-year operating period rather than a 30-year period would not signifi-cantly affect the operating and maintanance cost.
If the facility's capital cost were spread over a 40-year period the overall resulting cost of facility operation would be lowered.
Therefore, any exten-sion in the operating life of the facil,ity would result in savings in system production costs.
The production of energy at reduced cost results in an incremental net benefit for the use of a 40-yea'r operating 1 ife-of the faci 1 ity.
2.
Radiolo ical Assessments
- The NRC staff calculates dose commitments to the human population residing around nuclear power reactors to assess the impact on people from radioactive material released from
these reactors.
The annual dose commitment is calculated to be the dose that would be received over a 50-year period following the intake of radioactivity for 1 year under the conditions that would exist 15 years after the plant began operation.
The 15 year period is chosen as representing the midpoint of plant operation and is incorporated into the dose models by allowing for buildup of long life radionuclides in the soil.
It affects the estimated doses only for radionuclides ingested by humans that have half-lives greater than a few years.
For a plant licensed for 40 years, increasing the buildup period from 15 to 20 years would increase the dose from long life radionuclides via the ingestion pathways by 33$ at most.
It would have much less effect on dose from shorter life radionuclides.
Tables 4.8 and 4.9 of the FfS indicate that the estimated doses via the ingestion pathways are well below the regulatory design objectives.
For example, the ingestion dose to the thyroid is 4.3 mrem/yr/unit compared to an Appendix I design objective of 15 mrem/yr.
- Thus, an increase of even as much as 33$
in these pathways would remain well below the Appendix I guidelines and would not'e significant.
3.
Uranium Fuel C cle Im acts - The impacts of the uranium fuel cycle are based on 30 years of operation of a model LWR.
The fuel require-ments for the model LWR were assumed to be one initial core load and 29 annual r'efuelings (approximately 1/3 core).
The annual fuel requirement for the model LWR averaged out over a 40-year operating '
life (1 initial core and 39 refuelings of approximately 1/3 core) would be reduced slightly as compared to the annual fuel requirement averaged for a 30-year operating life.
The net result would be an approximately 1.5$ reduction in the annual fuel requirement for the model LWR.
This small reduction in fuel requirements would not lead to significant changes in the impacts of the uranium fuel cycle.
The staff does not believe that there would be any changes to Susquehanna FES Table 4.16 (S-3) that would be necessary in order to consider 40 years of operation.
If anything, the values in Table 4.16 become more conservative when a 40-year period of operation is considered.
4.
Uranium Resources
- In the Susquehanna FES, the uranium resource avai 1-ability is based on the cumulative lifetime (assumed to be 30 years) uranium requirements for 170,000 MWe capacity as identified in Section 8.5.6;
- However, as stated on page 8-20 the lifetime uranium commitment for this generating capacity would be less than one-third of the currently estimated domestic resources.
A 33$ increase in operating life (to 40 years) of the 170,000 MWe capacity would still be within the uranium resources projected in the Susquehanna FES.
Cancellation'f much of this 170,000 MWe capacity since the Susquehanna FES was.issued will further reduce the demand for uranium.
Furthermore, the increase in operating life assumption to 40-years will reduce the need for replacement generating capacity including nuclear, at the end of 30 years.
CONCLUSION:
The staff has reviewed the Susquehanna FES and determined that only four of the areas related to its NEPA analysis discussed in the statement were tied directly to a 30-year operating period.
We have concluded, based on the reasons discussed in the sections
- above, that the impacts associated with a 40-year license duration are not significantly different ation and are not significantly from those associated with a 30-year license dur-different from those assessed in the Susquehanna FES.
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DISTRIBUTION FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 -
ISSUANCE OF FACILITY OPERATING LICENSE NO. NPF-14:
"w/Tech Specs Document Control~
NRC PDR*
L PDR*
TERA*
NSIC*
LB¹2 Rdg.
RPerch MRushbrook JYoungblood ASchwencer MCutchin, OELD*
- JRutberg, OELD DEisenhut/RPurple TNovak*
AToal ston, AIG JSouder OIE MPA TBarnhart (4 cys)*
WMiller IDinitz
- WJones, OA (10 cys)
ACRS (16)
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