ML18030A403
| ML18030A403 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/02/1997 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18030A404 | List: |
| References | |
| NUDOCS 9705060277 | |
| Download: ML18030A403 (5) | |
Text
7590-Ol-P N T D STATES NUCLEAR REGULATORY COMMIS ION ENNSYLVANIA POWER AND LIGHT COMPANY 8=3K US UEHANNA STEAM ELECTRIC STATION UN T NVIRONMENTAL ASSESSMENT AND FINDING F
NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-22. issued to Pennsylvania Power and Light Company (the licensee).
for operation of the Susquehanna Steam Electric Station.
located in Luzerne County, PA.
NVIRONMENTAL ASSESSMENT Identification of the Pro osed Ac i n.
The proposed action would change the Technical Specifications for the unit to permit the use of ATRIUM-10 fuel in the reactor.
The changes include core flow dependent minimum critical power ratio (MCPR) Safety Limits in Sections 2.1.2 and 3.4.1.1.2.
addition of Siemens Power Corporation (SPC) methodology topical report references in Section 6.9.3.2, changes in Section 5.3.1 to. reflect new fuel design features.
changes in definitions in Section 1
to reflect the new fuel design.=and changes to the Bases to correspond to the above changes as appropriate:
The proposed action is in accordance with the licensee's application for amendment dated December
- 18. 1996.
as supplemented by letters dated February 26. 1997.
March 12 and 27, April,3. 9. 16. 18, and 24.
1997.
The Need for the Pro osed Action:
The proposed action will enable the licensee to complete its maintenance 9705060277. 970502 PDR ADOCK 05000388 P,
PDR and refueling outage on this unit and begin a new fuel cycle which will include a portion of the core consisting of the new ATRIUH-10 nuclear fuel.
Environmental Im acts of the Pro osed A ti n The Commission has completed its evaluation of the proposed action and concludes that it is acceptable.
The safety considerations associated with the use of the ATRIUM-10 fuel in the Susquehanna Steam Electric Station, Unit 2. have been evaluated by the NRC staff and the staff has concluded that this change in the reactor fuel design would not adversely affect plant safety.
The proposed change to the fuel design has no adverse effect on the probability of any accident previously analyzed.
The increase in fuel enrichment from 4.0X versus 4.5X for an increased fuel cycle.of 24 months results in an increase in the projected maximum burnup rate or discharge exposure from the current 45 to 48 HMd/kgU.
This increased burnup may slightly change the mix of fission products that might be released in the event of a serious accident, but such changes would not significantly affect the consequences of serious accidents.
Routine radiological effluents are not affected.
As a result. there is no increase in individual or cumulative radiation exposure.
The environmental impacts of transportation resulting from the use of higher enrichment and extended irradiation are discussed in the staff assessment entitled.
"NRC Assessment of the Environmental Effects of Transportation Resulting from Extended Fuel Enrichment and Irradiation."
This assessment was published in the FEDERAL REGISTER on August ll, 1988 (53 FR 30355),
as corrected on August 24, 1988 (53 FR 32322). in connection with the Shearon Harris Nuclear. Power Plant, Unit 1: Environmental Assessment and Finding of No Significant Impact.
As indicated therein, the environmental cost contribution of an increase in fuel enrichment of up to 5 weight percent U-235 and irradiation limits of up to 60 Gigawatt Days per Metric Ton (GWd/MT) are either unchanged.
or may in fact be reduced from those summarized in Table S-4 asset forth in 10 CFR 51.52(c).
These findings are applicable to the proposed increase in the allowable exposure of SPC ATRIUM-10 fuel for Susquehanna.
Unit 2.
Accordingly. the Comoission concludes that this proposed action would result in no significant radiological environmental impact.
Mith regard to potential nonradiological impacts. the proposed change will in no way affect environs located outside the restricted area as defined in 10 CFR Part 20. It does not affect nonradiological plant effluents and has no other environmental impact.
Therefore, the Coamission concludes that there are no significant nonradiological environmental impacts associated with the proposed change in the fuel exposure limit and the use of'he new fuel design.
lt rnatives to the Pro sed A
ion:
Since the Commission has concluded there is no measurable environmental impact associated with the proposed action.
any alternatives with equal or greater environmental impact need not be evaluated.
As an alternative to the proposed action, the staff considered denial 'of the proposed action.
Denial of the application would result in no change in current environmental impacts.
The environmental impacts of the proposed action and the alternative action are similar.
lternative Use of Resour es.
This action does not involve the use of any resources not previously considered in the Final Environmental Statement for the Susquehanna Steam
3
~
- 4 Electric Station. Unit 2.
encies and Persons Consulted.
In accordance with its stated policy, on May 1, 1997, NRC staff consulted with the Pennsylvania State official, R. Maiers of the Pennsylvania Department of Environmental Protection, regarding the environmental impact of the proposed action.
The State official had no coments.
IND NG OF NO SIGNIFICANT IMPACT Based upon the environmental assessment, the Commission concludes that the proposed action will.not have a significant effect on the quality of the human environment.
Accordingly, the Commission has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action.
see the licensee's letter dated December 18.
1996.
as supplemented by letters dated February 26. 1997.
March 12 and 27. April 3, 9. 16.
18, and 24.
1997, which are available for public inspection at the Commission's Public Document Room.
The Gelman Building. 2120 L Street, NW.. Washington.
DC, and at the local public document room located at the Osterhout Free Library, Reference Department, 71 South Franklin Street.
Wilkes-Barre, Pennsylvania 18701.
Dated at Rockville, Maryland. this Wd day of my 1997.
FOR THE NUCLEAR REGULATORY COMMISSION
~
~
n
. Stolz. Director ject Directorate I-2 Division of Reactor Projects
- I/II Office of Nuclear Reactor Regulation
1 ll I+
4