ML070320728
| ML070320728 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/12/2007 |
| From: | Alicia Mullins Office of Nuclear Reactor Regulation |
| To: | Ballaron P Susquehanna River Basin Commission |
| References | |
| TAC MD3021, TAC MD3022 | |
| Download: ML070320728 (7) | |
Text
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-Page'1 From:
Alicia Mullins To:
Paula Ballaron Date:
01/12/2007 9:36:39 AM
Subject:
Information Request
- Paula, It was good to meet with you and the team yesterday. Rich and I have added you to the mailing list to receive notice on future meetings and the Draft EIS.
Below are some accession numbers and links to information that you requested yesterday. Please contact us if you have futher questions.
10 CFR 50.59:
http://www.nrc.qov/readinq-rm/doc-collections/cfr/partO5O/partO5O-O059.html NRC power uprate webpage:
http ://www.nrc.qov/reactors/operating/licensinq/power-uprates.html Electronic Reading Room/Agencywide Documents Access and Management System (ADAMS) link:
http://www.nrc.,ov/readinq-rm/adams/web-based.html The documents below can be accessed by inputting the associated accession nos.using the ADAMS link above:
Most Recent Monthly Operating Reports Sept 2006 - ML062970349 August 2006 - ML062690470 July 2006 - ML062350147 PPL Susquehanna 1.4% Power Uprate Application to NRC - ML003766289 (dated 10/30/00)
NRC Approval and Safety Evaluation of 1.4% Power Uprate request - ML011760551 (dated 7/6/01)
Also, attached, please find the Environmental Assessment as published in the Federal Register on 6/25/2001 If you have any questions or need additional information, please contact Rich Guzman at 301-415-1030 or rvq(.nrc..ov Thanks Alicia Mullins Environmental Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 301-415-1224 "USNRC Protecting People and the Environment"axm7@nrc.gov CC:
Rani Franovich; Richard Guzman; Yoira Diaz Sanabria
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Information Request Creation Date 01/12/2007 9:36:39 AM From:
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It'Alicia Mullins - MU Zb.U1.PC1t Page 1!1 IliAlIcla Mullins - MUREA6 2b.U1.pdt Page 1 ji 33716 Federal Register/Vol. 66, No. 122/Monday, Jine 25, 2001 /Notices June 19, 2001.
Beth M. McCormick, Advisory Committee Management Officer, National Aeronautics and Space Administration.
[FR Doc. 01-15867 Filed 6-22-01; 8:45 am]
BILLING CODE 7510-01-P NATIONAL AERONAUTICS AND SPACE ADMINISTRATION
[Notice (01-081)]
NASA Advisory Council (NAC), Space Science Advisory Committee (SScAC, Sun-Earth Connection Advisory Subcommittee AGENCY: National Aeronautics and Space Administration.
ACTION
- Notice of Meeting.
SUMMARY
- In accordance with the Federal Advisory CommitteeAct, Pub.
L.92-463, asamended, the Nationd Aeronautics and Space Administration announces aforthooming meeting of the NASA Advisory Coundil, Space Science Advisory Committee, Sun-Earth Connection Advisory Subcommittee DATES: Monday, July 23, 2001, 8:30 am.
to6 p.m.; Tuesday, July 24, 2001,8:30 am. to 5 p.m.
ADDRESSES
- National Aeronautics and Space Administration, Conference Room 6H46, 300 EStree, SW, Washington, DC, 20546.
FOR FURTHER INFORMATION CONTACT: Dr.
George L.Withbroe, CodeS,Nationd Aeronautics and Space Administration, Washington, DC20546, 202/358-2150.
SUPPLEMENTARY INFORMATION : The meeting will beopen tothe public up tothe capacity of the room. The agenda for the meting indudes thefollowing topi eS:
-- State of the Sun-Earth Connection Theme
--Gespa0e Management Operations Working Group
-Living With aStar Science Architecture Committee
-- Solar/Haliospher icManagemant Operation Working Group
-Report of Disdpline Scientists It is imperative that the meeting be held onthese dates toaccommodate the scheduling priorities of the key partidpants. Visitors will berequested tosign avisitor's register.
Dated: June19, 2001.
Beth M. McCormick, Advisory committee Management Officer, National Aeronautics and Space Adminisration.
[FRDoc. 01-15868 Filed 6-22-01; 8:45 am]
BILLING CODE 7510-01-P NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-387 and 50-388]
PPL Susquehanna, LLC; Susquehanna Steam Electric Station Environmental Assessment and Finding of No Significant Impact The U.S. Nudsar Regulatory Commission (NRC) isconsidering issuance ofaamendments toFacility Operating License (FOL) Nos. NPF-14, end NPF-22, issued to PPL Susquehanna, LLC (thelicensee), for operation of the Susquethanna Steam Bectric Station (SSES), Units 1 and 2, located in Luzerne County, Pennsylvania Environmental Assessment Identification of the Proposed Action The proposed license amendment would revise the FOLs and Technical Speifications (TS) of SSES, Units 1 and 2,to allow thelicensee toincrease the licensed core power level from 3441 MWt to 3489 MWt, which represents a 1.4 percent increase in the allowablle thermal power. SSES Unit 1 was granted conditional authorization for power production by its FOL issued on Jily 17, 1982. Full power operation of Unit 1 at 3,293 MWt core power was authorized by Amendment No. 5to the FOL, issued on November 12, 1982. Amendment No.
143tothe FOL, issued on March 22, 1995, authorized apower uprate for Unit 1 to 3,441 MWt. SSES Unit 2wes granted conditional aithorization for power production by its FOL issued on March 23, 1984. Full power operation of Unit 2at 3,293 MWt core power was authorized by Amendment No. 1 to the FOL, issued on Jine 27, 1984.
Amendment No. 103tothe FOL, issued onApril 11, 1994, aithorized apower uprate for Unit 2to 3,441 MWt.
The proposed action isin accordance with the I icnsee'sapplication for license amendment dated October 30, 2000, assupplemented by latters dated February 5, May 22, and May 31, 2001.
The Need for the Proposed Action The proposed action would allow an increase in power generation atSSES, Units 1 and 2,to provide additional electrical power for distribution tothe grid. Power uprate has been widely recognized bythe industry esa safeand cost-effective method toincreese generating capacity.
Environmental Impacts of the Proposed Action The environmental impact assodated with operation of SSES, Units l and 2, has been previously evaluated by the U.S. Atomic Energy Commission in the "Final Environmental Statement Related to Operation ofSusquehaina Steam Bl*ctric Station, Units 1 and 2," dated June 1981. In this evaluation, the staff considered the potantia doses due to postulated accidents for the site, at the site boundary, and to the population within 50 miles of the site With regard toconsequanoes of postulated accidents, the licesee has reevaluated the current design basis accidents (DBAs) in its application for license amendments and determined that accident source terms are based on core power levels that bound the proposed core power level of 3489 MWt. Therefore, the current analyses bound the potential doses due to DBAs based on the proposed 1.4 perent increased core power level. No increase inthe probability of these accidents isexpected tooccur.
With regard to normal releases, the licensee has caculated the potential impact on the radiologcal affluents from the proposed 1.4 percent i nore in power lenad. The licensee condcuded that the offsite doses from normal effluent releases remain significantly below the bounding limitsof Title 10of the Code of Federal Regulations (10 CFR), Part 50, Appendix I. Normal annual average gaseous rdees remain limited toa small fraction of 10 CFR Part 20, Appendix B,Table 2 limits. The liensee evaluatled the effects of power uprate on the radiation sources within the plant and the radiation levels during normal operating conditions, Post-operation radiation levels are Expected toincree sligitly due to the power uprate; but are expected to have no significant effect on the plant.
Occupational doses for normai operations will bemaintained within acceptable limits by the siteALARA (es-low-as-reesonabl y-acheivable) program.
Solid and liquid waste production may increase slightly esa result of the proposed 1.4 percent upratea however, waste procesi ng systems are epected tooperate within their design requirements.
The NRC has completed itsevaluation of the proposed action and cndudes that the proposed action will not increase the probability or cnsequences ofaccidents, nochanges are being made inthe types of effluents that may be released offsite, and there isno significant increase inoocupational or public radiation exposure Therefore, there are no significant radiologcal environmental impacts assodated with the proposed action.
With regard topotantial non-radiologcal impacts, the proposed action does not involve any historic
~Aiicia Mullins - MUREA6.2b.U1.pdt Page 2~I IIiAlicia Mullins - MUREA15.2ti-M.PCIt Page 21t I
Federal Register/Vol. 66, No. 122/Monday, Jine 25, 2001/Notices 33717 sites. With regard tothermal discharges to the Susquehanna River, the staff has previously evaluated temiperature effects during normal operations atfull power and determined thetemperature impact on the river tobe insignificant. The licensee indicated that aninerease in theoooling tower air flow rate will o~mpensate for the slight increase in condenser outlet circulating water temperaature such that noperceptible change in the temperature of the cooling tower basin blowdown to the Susquehanna River isexpected.
Therefore, the temperature effects on the river will beinsignificant Existing administrative controls ensure the conduct of adequate monitoring such that appropriate actions can betaken to preclude exceeding thelimitsimposed by the Nationai Pollution Discharge Bimination System permit. No additional requirements orother changes are required asa result of the power uprate Noother non-radiologicai impacts are assodated with the proposed action.
Based upon theebove, the NRC concludes that the proposed action does not affect non-radiological plant affluents and has noother environmental impact. Therefore, there are nosignificant non-radiologicai environmental impacts assodated with the proposed action.
Accordingly, the NRC mcndudes that there are no significant environmental impacts assodated with the proposed action.
Alternatives to the Proposed Action Asen alternative tothe proposed action, the staff considered denial of the proposed action (i.e, the "no-action" alternative). Denial of the application would result in no change in current environmentai impacts. The environmental impacts of the proposed action and theaiternative action are similar.
A/ternative Use of Resources This action does not involve the use of any resources not previously considered inthe Final Environmental Statement for the SSES, Units 1 and 2.
Agencies and Persons Consulted In accordance with its stated policy, on June 19, 2001, the staff consulted with the Pennsylvania State offidial, Mr.
Michael Murphy of the Peansylvania Department of Environmental Protection, regarding the environmental impact of the proposed action. The State offidca had nocmments.
Finding of No Significant Impact On the basis of the environmentat assessment, the NRC oondudes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not toprepare an environmental impact statement for the proposed action.
For further details with respect tothe proposed acti on, see the Ii censee's I etter dated October 30, 2000, as supplemented by letters dated February 5, May 22, and May 31,2001.
Documents may beearnined, end/or copied for afea, atthe NRC'sPublic Document Room, located at One White Flint North, 11555 RockvillePke (first floor), Rockville, Mayland. Publidy available records will beacoessible Electronically from the Agecywide Documents Access and Management Systems (ADAMS) Public Bectronic Readi ng Room on the I ntemat at the NRCweb site, httpY/www.nrc.g ov/NRC/
ADAMS/index.htm/. If you do not have access toADAMS orif there are problems in accusing the documents located inADAMS, contact the NRC Public Document Room (FOR) Reference staff at 1-800-397-4209, 301-415-4737 orby e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland,this19th day of June 2001.
For theNuclear Ragulatory Commission.
Richard P. Correia, Acting Chief, Section 1, Prcject Directorate I, Diviaon of Ucensfng Project Management, Office of Nuclear Reactor Regulation.
[FRDoc. 01-15815 Filed6-22-01; 8:45 am]
BILLING CODE 7590-01-P requires that pressure-tempera ture (P-T) limitsbeestablished for reactor pressure vesses (RPVs) during normal operating and hydrostatic orleak rate testing conditions. Specfically, 10CFR Part 50, Appendix G, states, "The appropriate requirements on both the pressure-temperature limits and the minimum permissible temperature must bermet for al conditions." The purpose of 10 CFR Part 50, Appendix Q is to protect the integrity of the reactor coolant pressure boundary in nudear power plants. This isaoomplished through these regulations that, inpart, spedfy fracture toughness requirements for ferritic materials of the reactor coolant pressure boundary. Appendix Gof 10CFR Part 50 specfies that the requirements for these limitsare the American Sodety of Mechanical Engineers (ASME) Boiler and Pressure Vessd Code (Code),
Section Xl, Appendix GLimits.
The proposed action would exempt HCGSfrom application ofspecific requirements of 10 CFR Pat 50, Appendix Gaid would substitute use of ASME Code Cases N-588 and N-640 as alternatives pursuant to 10 CFR 50.60(b).
The proposed acti on is in accordance with the liiensee'sapplication for exemption dated December 1,2000, as supplemented by letters dated February 12, May 7, and May 14, 2001.
The Need for the Proposed Action The proposed action isneeded to allow the licensee to implement ASME Code Cases N-588 and N-640 i n order torevise the method used to determine the P-T limits.
Code Case N-588, "Alternative to Reference Flaw Orientation of Appendix Gfor Circumferential Welds in Reactor Vessets,Section XI, Division 1," amends the provisions of the 1989 Edition of ASME Section XI, Appendix G, by permitting thepostulation of a drcumferentiall y oriented reference flaw asthe limitingflaw ina RPV drcumferentiai wdd for the purpose of establishing RPV P-T limits. The 1989 Edition ofASME Section XI, Appendix G,would require that such areference flaw bepostulated asan axily oriented flaw in the droumferential weld. The licensee addressed thetechnicai justification for this exemption by dting industry experience and aspects of RPV fabrication which support the postulation of drcumferenti ally oriented flaws for these welds. The reference flaw isapostulated flaw that accounts for the possibility of a prior existing defect that may have gone undetected during the fabrication process. Postulating theAppendix G reference flaw ina circumferential weld NUCLEAR REGULATORY COMMISSION
[Docket No. 50-354]
PSEG Nuclear LLC; Hope Creek Generating Station Environmental Assesment and Finding of No Significant Impact The U.S. Nudear Regulatory Commission (NRC)isconsidering issuance ofan Exemption from certain requirements of Title 10of the Code of Federai Regulations (10 CFR) Part 50, Appendix Gfor Fadlity Operating License No. NPF-57, issued to PSEG Nuclear LLC, (the licensee) for operation ofthe HopeCreek Generating Station (HCGS), located in Salem County, New Jersey.
Environmental Assessment Identification of the Proposed Action Title 10 of the Code of Federal Regulations, Part 50, Appendix Q