ML20217P176
| ML20217P176 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/31/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| References | |
| NUREG-1437, NUREG-1437-S01, NUDOCS 9910290240 | |
| Download: ML20217P176 (350) | |
Text
{{#Wiki_filter:.- NUREG-1437 Supp.1 Generic Environmental Impact Statement for License Renewal of 1 Nuclear Plants i Supplement 1 Regarding the Calvert Cliffs Nuclear Power Plant Final Report l I
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U.S. Nuclear Regulatory Commission /"g Offire of Nuclear Reactor Regulation [ " Washington, DC 20555-0001 \, l ??A "%88 3 8sa88s u D P.Mt i
NUREG-1437 Supp.I m l Generie Environmental : Impact Statement for l License Renewal of g Nuclear Plants M Supplement 1 f Regarding the Calvert Cliffs Nuclear Power Plant E Final Report ! Ml l x l ) 2 .! U.S. Nuclear Regulatory Commission
= Office of Nuclear Reactor Regulation ((W"'*t,,, ,
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NUREG-1437 Supp.1 Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 1 I Regarding the l Calvert Cliffs Nuclear Power Plant Final Report Manuscript Completed: October 1999 ! I Date Published: October 1999 Division of Regulatory Improvement Programs , l Omce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Wcshington, DC 20555-0001
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4 NUREG-1437, Supplement I has been reproduced from the best available copy. l I l
Abstract The U.S. Nuclear Regulatory Commission (NRC) considered the environmental effects of renewing nuclear power plant operating licenses for a 20-year period in the Generic Environmental /mpact Statement for Renewal of Nuclear Plants (GECS), NUREG-1437, and codified the results in 10 CFR Part 51. The GEIS (and its Addendum 1) identifies 93 environmentalissues and reaches l generic conclusions related to environmental impacts for 69 of these issues that apply to all plants or to l pl:nts with specific design or site characteristics. Additional plant-specific review is required for the r maining issues. These plant-specific reviews are to be included in a supplement to the GEIS. This supplemental environmental impact statement (SEIS) has been prepared in response to an l cpplication submitted to the NRC by Baltimore Gas and Electric Company (BGE) to renew the operating licenses for Calvert Cliffs Nuclear Power Plant (CCNPP) Unit 1 and Unit 2 for an additional 20 years l under 10 CFR Part 54. This SEIS includes the NRC staffs analysis that considers and weighs the l cnvironmental effects of the proposed action, the environmentalimpacts of altcmatives to the proposed cction, and altematives available for reducing or avoiding adverse effects. It also includes the staffs l r commendation regarding the proposed action. l N:ither BGE or the staff have identified significant new information for any of the 69 issues for which the l GEIS reached generic conclusions and which apply to the CCNPP. Therefore, the staff concludes that the impacts of renewing the CCNPP operating licenses will not be greater than impacts identified in the l GEIS for these issues. For each of these issues, the GEIS conclusion is that the impact is of small l significance (except for collective offsite radiological impacts from the fuel cycle and from high-level wiste and from spent fuel which were not assigned a single significance level) and that additional mitigation measures are likely not to be sufficiently beneficial to be warranted. Each of the remaining 24 issues that apply to the CCNPP is addressed in this SEIS. For each rpplicable issue, the staff concludes that the significance of the potential environmental effects of r:newal of the operating license is small. The staff also concludes that additional mitigation measures l tra recommended only for threatened or endangered species and that mitigation measures beyond those recommended by the U.S. Fish and Wildlife Service are not warranted. Th3 NRC staff recommends that the Commission determine that the adverse environmental impacts of l license renewal for Calvert Cliffs Nuclear Power Plant Unit 1 and Unit 2 are not so great that preserving the option of license renewal for energy planning decisionmakers would be unreasonable. This recommendation is based on (1) the analysis and findings in the GEIS; (2) the Environmental Report submitted by BGE; (3) consultation with Federal, State, and local agencies; (4) its own independent l review, and (5) its consideration of public comments. l NUREG-1437, Supplement 1 iii October 1999
Contents Abstra ct . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .... iii Executive Summa ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... . ..... xiii Abbreviations / Acronyms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. ....... xvii 1.0 I ntrod uctio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 The Proposed Federal Action . . . . . . . . . . . . . . . . .. ... ...... .. .. ... . 1-6 1.2 Purpose and Need for the Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 1.3 Compliance and Consultations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.4 References ................. ... .................... ... ......... 1-7 2.0 Description of Nuclear Power Plant and Site and Plant Interaction with the Environment. . 2-1 l 2.1 Plant and Site Description and Proposed Plant Operation During the l Renewal Term . . . . . . . . . . . . . . . . ............... .................. ..... 2-1 l 2.1.1 Extemal Appearance and Setting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 2.1.2 Reactor Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 2-8 2.1.3 Cooling and Auxiliary Water Systems . . . . . . . . . . . . ... ............. 2-11 2.1.4 Radioactive Waste Management System and Effluent Control-Systems . . . . . 2-13 2.1.5 Nonradioactive Waste Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-17 2.1.6 Plant Operation and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-17 2,1.7 Power Transmission System . . . . . . . . . . . . . . . . . . . . . . . . . . .... .. . 2-18 2.2 Plant Interaction with the Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-18 2.2.1 La nd U se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-19 2.2.2 Wat e r U se . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-20 2.2.3 Water Quality . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . ..... 2-20 5 2.2.4 Ai r Q ua lity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-20 2.2.5 Aquatic Resources . . . . . . . . . . . .. . . . . . . . . . . . ........ .. ... 2-22 2.2.6 Terrestrial Resources . . . . . . . . . . . . . . . . . . . . . . .. . ....... .. 2-23 2.2.7 Radiological impa cts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-25 2.2.8 Socioeconomic Factors . . . . . .. . . . . . . . . . . . . . . . . . .. ..... .... 2-27 2.2.9 Historic and Archaeological Resources .. ....... ...... ........... 2-43 2.2.10 Related Federal Project Activities . . ................ . .......... . 2-51 l 2.3 Refe rences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . 2-51 l NUREG-1437, Supplement 1 V October 1999
' Cont:nts -
3.0 Environmental Impacts of Refurbishment . . . . . . . . . . ............................ . 3-1 l 4'.0 Environmental Impacts of Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 l 1 4.1 Cooling System ...................... ................................ 4-2 i 4.1.1 Entrainment of Fish and Shellfish in Early Life Stages . . . . . . . . . . . . . . . . . . . 4-8 4.1.2 Impingement of Fish and Shellfish . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-10 l- 4.1.3 Heat S h ock . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . 4-15 l 4.2 Transmission lines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-18 4.2.1 Electromagnetic Fields-Acute Effects . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-20
'4.2.2 Electromagnetic Fields--Chronic Effects . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-21 4.3 Radiological Impacts of Normal Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-22 4.4 Socioeconomic impacts of Plant Operations During the License Renewal Period . . . . 4-23 4.4.1 Housing Impacts During Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-24 4.4.2 Public Services: Public Utility impacts During Operations. . .... ....... 4-26 4.4.3 Offsite Land Use During Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-27 4.4.4 Public Services: Transportation impacts During Operations . . . . . . . . . . . . . . . . 4-30 4.4.5 . Historical and Archaeological Resources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-30 4.4.6 Environmental Justice . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-31 4.5 ' Groundwater Use and Quality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-35 4.5.1 Groundwater Use, Conflicts . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-36 4.6 Threatened or Endangered Species . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-36 4.7 Evaluation of Potential New and Significant Information on impacts of Operations During the Renewal Term . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-38 4.7.1 Microorganisms That Live in High Radiation, Extreme Heat Conditions . . . . . 4-38 l
4.8 Summary of impacts of Operations During the Renewal Term . . . . . . . . . . . . . . . . . . . 4-39 4.9. References . . . . . . . . . . . . . . . . ....................................... . 4-40 5.0 Environmental impacts of Postulated Accidents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 Postulated Plant Accidents . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . 5-1 October 1999 Vi NUREG-1437, Supplement 1 1
l Cont:nts I
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[ - 5.2 Severe Accident Mitigation Attematives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-3 ! 4 V i 5.2.1 - Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-3 I 5.2.2 > Estimate of Risk for CCNPP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-4 l l 5.2.3 ' Potential Design improvements . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . 5-8 ) l 5.2.4 : Risk Reduction Potential of Design improvements. . . . . . . . . . . . . . . . . . . . . . . 5-15 ! l~ 5.2.5 Cost impacts of Candidate Design improvements . . . . . . . . . . . . . . . . . . . . . . 5-15 5.2.6 Benefit-Cost Comparison . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . 5-17
.5.2.7 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-29
.5.3 . References . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-29 l i
6.0 Environmental Impacts of the Uranium Fuel Cycle and Solid Waste Management . . . . . . . . 6-1 6.1 The Uranium Fuel Cycle ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-2 6.2 C References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 i i
. 7.0 Environmental impacts of Decommissioning . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 7.1 References . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-3 8.0 Environmental impacts of Altcmatives to License Renewal . . . . . . . . . . . . . . . . . . . . . . . . . . 8-1 !
8.1 No-Action Altemative . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-1 i' 8.2 Altomative Energy Sources . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-3 8.2.1 Coal-Fired Generation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .8-4 8.2.2 Gas-Fired Generation . . . . . . . . : . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . 8-15 i 8.2.3 Imported Electrical Power . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 l 8.2.4 Other Attematives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-24 i 1
- 8. 3 ' References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-30 l 9.0' ' Summary and Conclusions . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 9-1 9.1 Environmental Impacts of the Proposed Action-License Renewal . . . . . . . . . . . . . . . 9-4 9.1.1 ' Unavoidable Adverse impacts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-5 9.1.2 Irreversible or Irrctrievable Resource Commitments . . . . . . . . . . . . . . . . . . . . 9-5 9.1.3 ' Short-Term Use Versus Long-Term Productivity . . . . . . . . . . . . . . . . . . . . . . . 9-6 9.2- Relative Significance of the EnvironmentalImpacts of License Renewal and the Altematives ....................................................... 9-6 NUREG-1437. Supplement 1 vii October 1999 j
Contents 9.3 Staff Conclusions and Recommendations . . . . . . . . . . . . . . ..... ........... 9-8 9.4 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-8 l Appendix A - Discussion of Comments on the Draft Supplement. . . . . . . . . . . . . . . . . . . . . . . . . A-1 Appendix B - Contributors to the Supplement . . . . .......................... ........ B-1 Appendix C - Chronology of NRC Staff Correspondence with Applicant . . . . . . . . . . . . . . . . . . . C-1 Appendix D - Organizations Contacted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-1 Appendix E - BGE Compliance Status and Consultations . . . . . . . . . . . . . . . . . . . . . . . E-1 Appendix F - GEIS Environmental Issues Not Applicable to the Calvert Cliffs Nuclear Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . ............. ......... ... .. F-1 I October 1999 - Viii NUREG-1437. Supplement 1 i
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I~ l l l Figures ! l 2-1 ' Calvert Cliffs Nuclear Power Plant Site Area, 50-Mile Region . . . . . . . . . . . . . . . . . . . 2-2
'2-2 Calvert Cliffs Nuclear Power Plant Site Area, Land Uses and Growth Protection Areas . 2-3 l 2-3 Calvert Cliffs Nuclear Power Plant Site Layout and Well Locations. . . . . . . . . . . . . . . . . . 2-5 2-4 Calvert Cliffs Nuclear _ Power Plant Station Layout . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 I 2-5 Calvert Cliffs Nuclear Power Plant (aerial photo) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-7 1
2-6 Regional Geologic Section - Coastal Plain . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-9 2-7 Intake and Discharge Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-12 2-8 Water Supply Systems in Calvert and St. Mary's Counties . . . . . . . . . . . . . . . . . . . . . . . . 2-32 ; 2-9 Aquia Aquifer Potentiometric Surface Map . . . . . . . . . . . ..... ..... ..... ...... 2-33 i 2-10 CCNPP 16-km (10-mi) Population Sectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-42 11 CCNPP 80-km (50-m) Population Sectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -. . . . 2-47 4-1 Geographic Distribution of Minority Populations Within 80 km (50 mi) of the CCNPP . . . . . 4-33 l 4-2. Geographic Distribution of Low-income Populations Within 80 km (50 mi) of the CCNPP. . 4-34 l, NUREG-1437, Supplement 1 iX October 1999
i l r w Tables 1-1 Federal, State, and Local Authorizations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 2-1 A Summary of Groundwater Aquifers Beneath CCNPP . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-10 2-2 Land Use in Calvert County inl1 99 3 . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 1 9 2-3 : Recreationally or Commercially important Aquatic Species Near CCNPP in Order of Abundance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2 3 2-4 Protected and " Watched
- Aquatic Species on and in the Vicinity of the CCNPP Site. . . 2-24 2-5 Protected and " Watched" Terrestrial Species on CCNPP Site and Rights-of-Way. . . . .. 2-26 2-6 ' Geographical Distribution of the Residences of CCNPP Employees, October 1998 . . . . . . 2-W 2-7 Population Growth in the Calvert, St. Mary's, and Charles County, Maryland . . . . . . . . . . 2-30
'2-8 Projected Pumpages by Sanitary District / Planning Area from the Aquia and Piney Point-Nanjemoy Aquifers Based on St. Mary's and Calvert Counties' Population Growth Estimates .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 2-31 2-9 [ Projected Build-Out in Calvert County Under 1995 Zoning '. . . . . . . . . . . . . . . . . . . . . . . . . 2-36 2-10 Estimated Population Distribution in 1990 Within 10 mi (16 km) of CCNPP . . . . . . . . . . . . 2-39 2-11 Estimated Population Distribution in 2010 Within 10 mi (16 km) of CCNPP . . . . . . . . . . . . 2-39 2-12 Estimated Population Distribution in 2020 Within 10 mi (16 km) of CCNPP . . . . . ...... 2-40 2-13 Estimated Population Distribution in 2030 Within 10 mi (16 km) of CCNPP . . . . ...... 2-40 2-14 Estimated Population Distribution in 2040 Within 10 mi (16 km) of CCNPP . . . ....... 2-41 2-15 Estimated Population Distribution in 1990 Within 50 mi (80 km) of CCNPP . . . . . . . . . . 2-44 2-16 Estimated Population Distribution in 2010 Within 50 mi (80 km) of CCNPP . . . . . . . . . . . 2-44 ' 2-17 Estimated Population Distribution in 2020 Within 50 mi (80 km) of CCNPP . . . . ..... 2-45 2-18 Estimated Population Distribution in 2030 Within 50 mi (80 km) of CCNPP . . . . . . . . . 2-45 2-19 Estimated Population Distribution in 2040 Within 50 mi (80 km) of CCNPP . . .. . .. .. 2-46 October 1999 x NUREG-1437. Supplement 1
Tablis l 2-20 Estimated Age Distribution of Population in 1990 and 2020 ... . . . . 2-46 2-21 Projected Age Distnbution in 2030 Within 10 mi (16 km) and 50 mi (80 km) of C' NPP . 2-48 2-22 Transient Population Associated with Major Facilities Within 16 km (10 mi) of CCNPP. . 2-48 3-1 Category 1 issues for Refurbishment Evaluation . . . . . . . . . . . . . . . . . . . . . . 3-1 . 1 52 Categuy 2 issues for Refu bishment Evaluation . ... . .. .. . .. 3-2 4-1 Category i Issues Applicable to the O >eration of the CCNPP Cooling System During the Renewal Term . . . . . . ... .... .. . ....... ..... . .. ..... . 4-3 4-2 Category 2 Issues Applicable to the Operation of the CCNPP Cooling System l l During the Renewal Term . . . . . . .. ... .. ... ... . .. . . . 4-8 l l 4-3 Summary of 1993-1995 Fish Losses Through Impingement . ... ... . . .. . 4-13 l 4-4 Category 1 issues Applicable to the CCNPP Transmission Lines During the l Renewal Term . . . ........ . .. . .. ... .... . . .. . . . . . 4-19 l 4-5 Category 2 issues Applicable to the CCNPP Transmission Lines During the l Renewal Term . . ........... . .... .. . .. .. . . . . . ... .. 4-21 l 4-6 Category 1 issues Applicable to Radiological Impacts of Normal Operations l During the Renewal Term . . . . . . . . .... .... . .. . .. .. . .. . . 4-22 l 4-7 Category 1 issues Applicable to Socioeconomics During the Renewal Term. .. ... . 4-23 l 4-8 Category 2 Issues Applicable to Socioeconomics During the Renewal Term. .. . . 4-25 l 4-9 Calvert County Property Taxes Paid on CCNPP, Selected Years, 1972-1998. . 4-28 l 4-10 Category 1 issues Applicable to Groundwater Use and Quality l During the Renewal Term . . . . . . . . . . ... .. .. . . .... ... 4-35 4-11 Category 21ssues Applicable to Groundwater Use and Quality l During the Renewal Term . . . . ..... ..... ... . . . 4-35 4-12 Category 2 issues Applicable to Threatened or Endangered Species l During the Renewal Term . . .... . ... .. .. . . .. .. . . 4-37 5-1 Category 1 issues Applicable to Postulated Accidents During the Renewal Term . . .. 5-2 l 5-2 Category 2 Issues Applicable to Postulated Accidents .. . . . . 5-2 NUREG-1437, Supplement 1 xi October 1999
Tcbles 5-3 Calvert Cliffs CDF Profile ... ......... ..... .. .. ... .. . ... ..... 5-5 5-4 Contribution of Containment Release Category to Release Frequency and Population Dose . . . . . . . . . . . . . . .. ... . .... . ..... .. . . . 5-5 5-5 Value-impact Results for Potentially Cost Beneficial SAMAs . . . . . . . . . .. . . 5-16 6-1 Category 1 issues Applicable to the Uranium Fuel Cycle and Solid Waste Management 6-2 7-1 Category 1 Issues Applicable to the Decommissioning of the CCNPP Following the Renewal Term . . . . . . . . . . . . . . . . . . . .. ... . .. ... ...... ..... . . . . . 7-2 8-1 Summary of Environmental Impacts from No-Action Alternative. . . . . . . . . .. 8-3 8-2 Summary of Environmental Impacts from Coal Alternative-Once-Through Cooling. . . . 8-6 8-3 Summary of Environmental Impacts from Altemate Cooling System (Cooling Towers with Closed-Cycle Coo!ing) . . ... ... ... ..... . .. ... . . . . 8-14 8-4 Summary of Environmental Impds from Gas-Fired Generation-Once-Through Cooling Altemative . . . . . . . . . . . . . . .. . . . .. . . .. . ... .. . 8-18 8-5 Summary of Environmental Impacts of Gas Fired Generation with Attemate Cooling System (Cooling Towers with Closed-Cycle Cooling) . . .. . ... . . . . .. 8-23 8-6 Retirement Schedule of BGE Power Plants . . . . . . . . .. ... .. . . ... .. 8-28 l 8-7 Summary of EnvironmentalImpacts of 500 MW(e) Demand-Side Measures, Plus l 1200 MW(e) Gas-Fired Generation (Once-Through Cooling) . . . ... .. . . 8-31 9-1 Summary of Environmental Significance of License Renewal, the No-Action Attemative, and Attemative Methods of Generation Assuming a Once-Through Cooling System. . 9-7 l A-1 Calvert Cli#s SEIS Comment Log . . . . . . . . . . . ........ . . . . A-3 l l A-2 BGE's Comments and Staff Response . . . . . .. ..... . .... . A '7 October 1999 XII NUREG-14?7. Supplement 1 i
i Executive Summary By letter dated April 8,1998, Baltimore Gas and Electric Company (BGE) submitted an application to ths U.S. Nuclear Regulatory Commission (NRC) to renew the operating licenses for Units 1 and 2 of the l Calvert Cliffs Nuclear Power Plant (CCNPP) for an additional 20-year period. If the operating licenses l tra renewed, Federal (other than NRC) agencies State regulatory agencies, and the owners of the l pt nt will ultimately decide whether the plant will continue to operate. This decision will be based on l factors such as the need for power or other matters within the State's jurisdiction or the purview of the l owners. If the operating licenses are not renewed, Units 1 and 2 will be shut down at or before the l cxpiration of the current operating licenses, which are July 31,2014, and August 13,2016, respectively. l Under the National Environmental Policy Act (NEPA), an environmental impact statement (EIS) is required for major Federal actions significantly affecting the quality of the human environment. The NRC has implemented Section 102 of NEPA in 10 CFR Part 51. In 10 CFR 51.20(b)(2), the l Commission requires preparation of an EIS or a supplement to an EIS for renewal of a reactor operating license; 10 CFR 51.95(c) states that the EIS prepared at the operating license renewal stage will be a supplement to the Generic EnvironmentalImpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437.'*) l Upon acceptance of the BGE application, the NRC began the environmental review process described ; in 10 CFR Part 51 by publishing a notice ofintent to prepare an EIS and conduct scoping. The staff l visited the CCNPP site in July 1998 and held public scoping meetings on July 9,1998, in Solomons, ; Maryland. The staff reviewed the BGE environmental report (ER) and compared it to the GEIS, l I consulted with Federal, State, and local agencies, conducted an independent review of the issues l following the guidance set forth in the draft Standard Review Plans for Environmental Reviews for NuclearPower Plants, Supplement 1: Operating License Renewal, NUREG-1555, Supplement 1, and l considered the public comments from the scoping process and the comment period for the draft l Supplemental Environmental Impact Statement (SEIS) for CCNPP. l This supplemental EIS (SEl3) includes the NRC staff's analysis that considers and weighs the l environmental effects of the proposed action, the environmental impacts of altematives to the proposed cction, and attematives available for reducing or avoiding adverse effects. It also includes the staff's l recommendation regarding the proposed action. l Th3 Commission has adopted the following definition of purpose and need for license renewal from the l GEIS: l The purpose and need for the proposed action (renewal of an operating license) is to provide an option that allows for power generation capability beyond the term of a cuirent nuclear power plant operating license to meet future system generating needs, as such needs may be determined by State, utility, and, where authorized, Federal (other than NRC) decisionmakers. (c) The GEIS was originally issued in 1996. Addendum 1 to the GEIS was issued in 1999. Hereinafter, l all references to the 'GEIS" include the GEIS and its Addendum 1. l NUREG-1437, Supplement 1 Xiii October 1999
1 l Executiva Summ:ry l The Commission lias provided the criterion to be used in evaluating the environmental impacts, as l follows [10 CFR 51.95(c)(4)]:
. . whether or not the adverse environmental impacts of license renewal are so great that preserving the option of license renewal for energy planning decisionmakers would be unreasonable.
l Both the statement of purpose and need and the evaluation criterion implicitly acknowledge that there are factors, in addition to license renewal, that will ultimately determine whether CCNPP continues to operate beyond the period of the current operating licenses. The GEIS contains the results of a systematic evaluation of the consequences of renewing an operating l license and operating a nuclear power plant for an additional 20 years. it evaluates 93 environmental issues using a three-level standard of significance-small, moderate, or large--based on Council on Environmental Quality guidelines. These significance levels are SMALL: Environmental effects are not detectable or are so minor that they will neither destabilize nor noticeably alter any important attribute of the resource. MODERATE: Environmental effects are sufficient to alter noticeably, but not to destabilize important attributes of the resource. LARGE: Environmental effects are clearly noticeable and are sufficient to destabilize important attributes of the resource. l For 69 of the 93 issues considered in the GEIS. the analysis in the GEIS shows: (1) the environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other plant or site characteristics (2) a single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for collective offsite radiological impacts from the fuel cycle and from high-level waste and spent fuel disposal) (3) mitigation of adverse impacts associated with the issue has been considered in the analysis, and it has been determined that additional plant-specific mitigation measures are likely not to be sufficiently beneficial to warrant implementation. l These 69 issues were identified in the GEIS as Category 1 issues. In the absence of significant new l information, the staff relied on conclusions as amplified by supporting information in the GEIS for issues l designated Category 1 in 10 CFR. Part 51, Subpart A, Appendix B. l Of the 24 issues not meeting the criteria set forth above,22 were classified as Category 2 issues requiring analysis in a plant-specific supplement to the GEIS. The remaining two issues, environmental October 1999 Xiv NUREG-1437, Supplement 1 1
Executive Summary justice and chronic effects of electromagnetic fields, were not categorized. Environmental justice was not evaluated on a generic basis and must also be addressed in a plant-specific supplement to the GEIS. Information on the chronic effects of electromagnetic fields was not conclusive at the time the l GEIS was prepared, or at the time this document was prepared. This SEIS evaluates all 93 environmental issues considered in the GEIS and one new issue- I microorganisms in high-radiation, high-temperature conditions, which was raised during the scoping process. The SEIS considers the environmental impacts associated with attematives to license renewal and compares the environmental impacts of license renewal and the alternatives. The attematives to license renewal that are considered include the no-action attemative (not renewing the CCNPP operating licenses) and alternative methods of power generation. Among the attemative methods of power generation, coal-fired and gas-fired generation appear the most likely if the power from CCNPP is replaced. These attematives are evaluated assuming that the replacement power generation plant is located at either the CCNPP site or an unspecified "greenfield" site. BGE and the staff have established independent processes for identifying and evaluating the l significance of any new information on the environmental impacts of license renewal. Neither BGE nor tha staff is aware of any significant new information related to Category 1 issues that would call into question the conclusions in the GEIS. Similarly, neither BGE or the staff has identified any new issue cpplicable to the CCNPP that has a significant environmentalimpact. Therefore, the staff relies upon th3 conclusions of the GEIS for all 69 Category 1 issues. l The staff has reviewed the BGE analysis for each Category 2 issue and has conducted an independent review of each issue. Five Category 2 issues are not applicable because they are related to plant d; sign features or site characteristics not found at CCNPP. Four additional Category 2 issues are not discussed in this SEIS because they are specifically related to refurbishment. BGE has stated in its ER l that it "has not identified the need to undertake the major refurbishment activities that the GEIS assumed for license renewal, and no other modifications have been identified that would directly affect tha environment or plant effluents." The remaining 13 Category 2 issues, as well as environmental justice and chronic effects of electromagnetic fields, are discussed in detail in this SEIS. For all issues, the staff concludes that the potential environmental effects are of SMALL significance in the context of the GEIS. Fcr Severe Accident Mitigation Alternatives (SAMAs), the staff concludes that a reasonable, comprehensive effort was made to identify and evaluate SAMAs. Although a limited number of cost-beneficial SAMAs (four) l were identified, the SAMAs do not relate to adequately managing the effects of aging during the period , of extended operation and, therefore, need not be implemented as part of license renewal pursuant to l ! 10 CFR Part 54. In addition to considering the 93 issues listed in the GEIS, the staff considered the potential issue l cssociated with microorganisms that live in high-radiation, high-temperature environments and l l concludes that this issue, while new, is not significant. Mitigation measures were considered for each Category 2 issue. In general, current measures to mitigate environmental impacts of plant operation were found to be adequate, and no additional i NUREG-1437, Supplement 1 XV October 1999 l
i l i Encutivs Summary l l
/
mitigation measures were deemed sufficiently beneficial to be warranted. However, the U.S. Fish and Wildlife Service recommended that BGE amend its conservation agreement with The Nature Conservancy relative to tiger beetles and set constraints on activities in the vicinity of bald eagle nests. l No other mitigation measures related to threatened or endangered species are warranted. In the event that the CCNPP operating licenses are not renewed, and the plants cease operation at or before the expiration of their current operating licenses, the advese impacts of likely alternatives will not be smaller than those associated with continued operation of CCNPP. The impacts may, in fact, be greater in some areas. l The NRC staff recommends that the Commission determine that the adverse environmental impacts of license renewal for Calvert Cliffs Nuclear Power Plant Unit 1 and Unit 2 are not so great that preserving l the option of license renewal for energy planning decisionmakers would be unreasonable. This l recommendation is based on (1) the analysis and findings in the GEIS; (2) the ER submitted by BGE; l (3) consultation with other Federal, State and local agencies; (4) its own independent review; and ! l (5) its consideration of public comments. l l October 1999 XVI NUREG-1437, Supplement 1
Abbreviations / Acronyms I AC attemating current i ACC averted cleanup costs AEA Atomic Energy Agency l AFAS auxiliary feedwater actuation signal AFS American Fisheries Society l AFW auxiliary feedwater ALARA as low as reasonably achievable ANSP Academy of Natural Sciences of Philadelphia AOC averted offsite property damage costs l AOE averted occupational exposure l AOSC averted onsite costs APE averted public exposure ATS automatic transfer switch l BGE Baltimore Gas and Electric Company ! BTU British thermal units CAA Clean Air Act l CCNPP Calvert Cliffs Nuclear Power Plant CCPRA Calvert Cliffs Probabilistic Risk Assessment CDF core damage frequency CEO Council on Environmental Quality l CFR Code of Federal Regulations CO carbon monoxide l COE cost of enhancement COMAR Code of Maryland Regulations CST condensate storage tank CVCS Chemical and Volume Control System i CWA- Clean Water Act l l CZMA Coastal Zone Management Act l DAW dry active waste DBA design-basis accidents DC direct current DO dissolved oxygen DOC U.S. Department of Commerce l J DOE U.S. Department of Energy DW demineralized water i ECCS Emergency Core Cooling System l ) EDG emergency diesel generator 1 EIA Energy Information Administration l l EIS EnvironmentalImpact Statement l NUREG-1437, Supplement 1 Xvii October 1999 i
Abbrsvirtions/ Acronyms l E!.F-EMF extremely low frequency-eiectromagnetic field EPA U.S. Environmental Protection Agency ER- environmental report l ESRP Environmental Standard Review Plan l FERC Federal Energy Regulatory Commission FES Final Environmental Statement FONSI finding of no significant impact
- FR Federal Register FSAR Final Safety Analysis Report l FWPCA Federal Water Pollution Control Act FWS U.S. Fish and Wildlife Service
- i. .
l GEIS . Generic Environmental Impact Statement for License Renewal of Nuclear Plants, NUREG-1437 gpd_ gallons per day
.gpm gallons per minute 'GRTS Gaseous Radwaste Treatment System Gy- . gray (unit of radiation dose that is equivalent to 100 rad) ha hectare l HABS. Historic American Building Survey HEPA high-efficiency particulate air (filter)
HPSI high-pressure safety injection l lPA' Integrated Plant Assessment IPE Individual Plant Examination IPEEE Individual Plant Examination for Extemal Events IRP Integrated Resources Plan l 'J joule l J/kg joule / kilogram kG kilogray km kilometer kV kilovolt kWh kilowatt-hour kWh/m2 . kilowatt-hours per square meter l Lid liters per day l L/s liters per second . LOCA loss of coolant accident ' LOS level of service LRTS Liquid Radwaste Treatment System LWR- light water reactor October 1999 XViii NUREG-1437, Supplement 1
1 1 l
' Abbrevittions/ Acronyms m meter mA milliampere MACCS MELCOR Accident Consequence Code System MDE - Maryland Department of the Environment MDNR' Maryland Department of Natural Resources MEA- Maryland Energy Administration mGy milligray l j mi mile l
=
MPF Materials Processing Facility MSL- mean sea level mSv millisievert .
]
MT metric tonne MTHM metric tonnes of heavy metal l_ MW megawatt mwd /MTU megawatt-days per metric tonne of uranium MWe megawatts-electric ' MWPS Miscellaneous Waste Processing System NAS National Academy of Sciences l NEPA. National Environmental Policy Act
'NESC National Electric Safety Code -
l I NIEHS National Institute of Environmental Health Sciences j NMFS National Marine Fisheries Service ' NO, nitrogen oxides _ NPDES National Pollutant Discharge Elimination System l NRC: _ U.S. Nuclear Regulatory Commission i NRR Office of Nuc!cer Reacter Regu!ation l ! ODCM- Offsite Dose Calculation Manual -l OL - operating license l l i PEPCO: Potomac Electric Power Company l PJM Pennsylvania-New Jersey-Maryland l , PMm particulate matter having a diameter of 10 microns or less l l PORV power operated relief valve PRA Probabilistic Risk Assessment ; PSC Public Service Commission l l PX Pool Spot Energy Market l RACT reasonably available control technology l RAI request for additionalinformation l RCDT- reactor coolant drain tank l I RCP. reactor coolant pump - RCRA Resource Conservation and Recovery Act l l RCW reactor coolant wastes NUREG-1437, Supplement 1 : Xix October 1999 l 1
AbbrG;viations/ Acronyms RCWPS Reactor Coolant Waste Processing System REMP radiological environmental monitoring program l RIS representative important species
- s. second SAMA Severe Accident Mitigation Attemative SAMDA Severe Accident Mitigation Design Altemative SEIS cupplemental environmental impact statement SHPO Sth*e Historic Preservation Office SMITTR Survetibnce, online monitoring, inspections, testing, trending, and recordkeeping l SO 2 sulfur dicxide l SO, sulfur oxides SRM Staff Requirements Memorandum SRW service water system .
SSSA spurious safety system actuation Sv sievert (unit of radiation measurement, equivalent to 100 rem) SW saltwater system SWPS Solid Waste Processing System l TDR Transferable Development Right UFSAR Updated Final Safety Analysis Report Ung long-term replacement power costs USC United States Code l USQ unreviewed safety question lV volt VOCs votetile organ!c compsun&: WGPS Waste Gas Processing System October 1999 xx NUREG-1437, Supplement 1
1.0 Introduction l l Britimore Gas and Electric Company (BGE) operates Calvert Cliffs Nuclear Power Plant (CCNPP) Units 1 and 2 in southern Maryland on the west shore of the Chesapeake Bay under operating licenses ; (OLs) DPR-53 and DPR-69 issued by the U.S. Nuclear Regulatory Commission (NRC). These OLs will l cxpire in 2014 for Unit 1 and 2016 for Unit 2. By letter dated April 8,1998, BGE submitted an rpplication to the NRC to renew the CCNPP OLs for an additional 20 years under Title 10 of the Code l of Federal Regulations (CFR) Part 54. BGE is a licensee for the purposes of its current OLs and an l applicant for the renewal of the OLs. l The National Environmental Policy Act of 1969 (NEPA) requires an environmental impact statement l (EIS) for major Federal actions significantly affecting the quality of the human environment. As provided in the Generic EnvironmentalImpact Statement for Ucense Renewal of Nuclear Plants (GEIS), l NUREG-1437 (NRC 1996,1999a),(') under NRC's environmental protection regulations in 10 CFR l Prrt 51 implementing NEPA, renewal of a nuclear power plant operating license is identified as a major Federal action significantly affecting the quality of the human environment. Therefore, an EIS is l required for a plant license renewal review. The EIS requirements for a plant-specific license renewal r: view are specified in 10 CFR Part 51. Pursuant to 10 CFR 54.23 and 51.53(c), BGE submitted an cnvironmental report (ER) (BGE 1998a) in which BGE analyzed the environmental impacts associated with the proposed action, considered alternatives to the proposed action, and evaluated any tit::matives for reducing adverse environmental effects. As part of NRC's evaluation of the application for license renewal, the NRC staff is required under 10 CFR Part 51 to prepare an EIS for the proposed action, issue the statement in draft form for public comment, and issue a final statement after considering public comments on the draft. This report is the l l finil plant-specific supplement to the GEIS (SEIS) for the BGE license renewal application. The staff l will also prepare a separate safety evaluation report in accordance with 10 CFR Part 54. I Th3 following sections in this introduction describe the background and the process used by the staff to essess the environmental impacts associated with license renewal, describe the proposed Federal l cction, discuss the purpose and need for the proposed action, and present the status of compliance with environmental quality standards and requirements that have been imposed by Federal, State, r;gional, and local agencies having responsibility for environmental protection. Chapter 2 describes the sit], power plant, and interactions of the plant with the environment. Chapters 3 and 4 discuss the potential environmental impacts of plant refurbishment and plant operation during the renewal term, r:spectively. Chapter 5 contains an evaluation of potential environmental impacts of plant accidents and includes consideration of severe accident mitigation altematives (SAMAs). Chapter 6 discusses (a) The GEIS was originally issued in 1996. Addendum 1 to the GEIS was issued in 1999. Hereafter, l all references to the "GEIS" include the GEIS and its Addendum 1. NUREG-1437, Supplement 1 1-1 October 1999
Introduction the uranium fuel cycle and solid waste management, and Chapter 7 discusses decommissioning. The attematives to license renewal are considered in Chapter 8. Finally, Chapter 9 summarizes the findings of the prior chapters, draws conclusions related to the adverse impacts that cannot be avoided (the relationship between short-term uses of man's environment and the maintenance and enhancement of long-term productivity, and the irreversible or irretrievable commitments of resources), and presents the l recommendation of the staff with respect to the proposed action. Additional information is included in l Appendices. Appendix A contains a discussion of comments on the draft SEIS issued on February 24, l 1999. Appendix B lists preparers of this supplement, and Appendix C lists the chronology of correspondence between NRC and BGE with regard to this supplement. The remaining appendices are identified in subsequent sections. Generic Environmental Impact Statement The NRC initiated a generic assessment of the environmental impacts associated with the license renewal term to improve the efficiency of the license renewal process by documenting the assessment results and codifying the results in the Commission's regulations. This assessment is provided in the l GEIS. The GEIS serves as the principal reference for all nuclear power plant license renewal EISs. The GEIS documents the results of the systematic approach that was taken to evaluate the , l environmental consequences of renewing the licenses of individual nuclear power plants and operating l them for an additional 20 years. For each potential environmental issue, the GEIS (1) described the activity that affects the environment, (2) identified the population or resource that is affected, (3) assessed the nature and magnitude of the impact on the affected population or resource, (4) characterized the significance of the effect for both beneficial and adverse effects, (5) determined whether the results of the analysis applied to all plants, and (6) considered whether additional mitigation measures would be warranted for impacts that would have the same significance level for all plants. l The standard of significance was established using the Council on Environmental Quality (CEO) l terminology for "significantly" (40 CFR 1508.27) for asses, sing environmentalissues as small, moderate, l or large. Using the CEO terminology, the NRC established three significance levels as follows: SMALL: Environmental effects are not detectable or are so minor that they will neither destabilize nor noticeably alter any important attribute of the resource. ) MODERATE: Environmental effects are sufficient to alter noticeably but not to destabilize important I attributes of the resource. LARGE: Environmental effects are clearly noticeable and are sufficient to destabilize important attributes of the resource. October 1999 1-2 NUREG-1437, Supplement 1
1 l Introduction The GEIS assigned a significance level to each environmentalissue. In assigning these levels, it was esumed that ongoing mitigation measures would continue. Th3 Gels included a determination of whether the analysis of the environmentalissue could be applied to cll plants, and whether additional mitigation measures would be warranted. Issues were then tssigned a Category 1 or a Category 2 designation. As set forth in the GEIS, Category 1 issues are l those that meet all of the following criteria: l (1) The environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other specified plant or site characteristic. (2) A single-significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for collective offsite radiological impacts from the fuel cycle and from high-level waste and spent fuel disposal). (3) Mitigation of adverse impacts associated with the issue has been considered in the analysis and it has been determined that additional plant-specific mitigation measures are likely not to be sufficiently beneficial to warrant implementation. l For issues that meet the three Category 1 criteria, no additional plant-specific analysis is required unless new and significant information is identified. Cctegory 2 issues are those that do not meet one or more of tl'a criteria of Category 1, and therefore, l cdditional plant-specific review for these issues is required. As set forth in the GEIS, the staff assessed 93 environmentalissues and determined that 69 are l C::tegory 1 issues,22 are Category 2 issues, and two issues were not categorized. The latter two issues, environmental justice and chronic effects of electromagnetic fields, are to be addressed in a l pl:nt-specific analysis. A summary of the findings for all 93 issues is listed in Table 9.1 of the GEIS and l is codified in 10 CFR Part 51, Subpart A, Appendix B, Table B-1. l l License Renewal Evaluation Process l l An applicant seeking a renewal of its operating license is required to submit an ER as part of its cpplication. This ER must provide an analysis of the issues listed as Category 2 issues in 10 CFR l l P:rt 51, Subpart A, Appendix B, Table B-1 in accordance with 10 CFR 51.53(c)(0)(ii). The ER must l include a discussion of actions to mitigate adverse impacts associated with the proposed action and environmental impacts of alternatives to the proposed action. Certain issues, including the need for l power, the economic benefits and costs of the proposed action, economic benefits and costs of cit;matives to the proposed action, and other issues not related to the environmental effects of the NUREG-1437, Supplement 1 1-3 October 1999
Introduction l proposed action and associated altematives need not be considered in the ER in accordance with l 10 CFR 51.95(c)(2). In addition, the ER need not discuss any aspect of the storage of spent fuel. l Pursuant to 10 CFR 51.53(c)(3)(i) and (iv), the ER is not required to contain an analysis of any Category 1 issues unless there is significant new information on a specific issue. New and significant information is (1) information that identifies a significant environmental issue not covered in the GEIS l and codified in 10 CFR Part 51, Subpart A, Appendix B, or (2) information that was not considered in the analyses summarized in the GEIS and which bads to an impact finding different from that codified in 10 CFR Part 51. l In preparing to submit its application to renew the CCNPP operating licenses, BGE implemented a process for identifying and evaluating the potential significance of new information related to l environmental impacts that might be associated with the CCNPP license renewal. The process is l described in a paper provided to the staff during a staff site visit in July 1998 (BGE 1998b). The process included forming a team of individuals who represent (1) the principal BGE organizations having responsibilities encompassing license renewal environmental issues, (2) the Maryland l Department of Natural Resources (MDNR), and (3) BGE's vendor for environmental services. This team conducted site inspections, record and document reviews, interviews, and a CCNPP docket review in search of information that might indicate that any of the findings for Category 1 issues or analyses for Category 2 issues were invalid as applied to CCNPP or that there were potential l environmental impacts associated with the CCNPP license renewal that were not addressed in the GEIS. The NRC staff also has a process for identifying new and significant information. That process is l described in detail in a draft of the Standad Review Plans for Environmental Reviews for Nuclear } Powerplants, Supplement 1: Operating License Renewal (ESRP), NUREG-1555, Supplement 1 l (February 1999 pre-publication copy) (NRC 1999b). The search for new information includes review of 1 l an applicant's ER and process for discovering and evaluating the significance of new information; l review of records of public meetings and correspondence; review of environmental quality standards l and regulations; coordination with Federal, State, and local environmental protection and resource l agencies; and review of the technical literature. Any new information discovered by the staff is evaluated for significance using the criteria set forth in the GEIS. For Category 1 issues where new and significant information is identified, reconsideration of the conclusions for those issues is limited in scope to the assessment of the relevant new and significant information; the scope of the assessment l does not include other facets of the issue that are not affected by the new information. Neither BGE or l the staff has identified any new issue applicable to the CCNPP that has a significant environmental l impact; one new issue (extremophiles) was identified, but was determined not to be significant. The discussion of the environmental issues contained in the GEIS that are applicable to CCNPP is found in Chapters 3 through 7. At the beginning of the discussion cf each set of issues, there is a table { that identifies the issues to be addressed and lists the sections in the GEIS where the issue is I J October 1999 1-4 NUREG-1437, Supplement 1
introduction discussed. Category 1 and Category 2 issues are listed in separate tables. For Category 1 issues for which there is no new and significant information, the table is followed by a set of paragraphs that state the GEIS conciusion codified in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, followed by the l staff's review steps and conclusion. For Category 2 issues, in addition to the list of GEIS sections where the issue is discussed, the tables list the subparagraph of 10 CFR 51.53(c)(3)(ii) that describe tha analysis required and the SEIS sections where the analysis is presented. The SEIS sections discussing the Category 2 issues are listed immediately following the table. l
- The NRC prepares an independent analysis of the environmental impacts of license renewal as well as a comparison of these impacts to the environmentalimpacts of alternatives. The evaluation of BGE's license renewal application began with publication of a notice of acceptance for docketing (63 FR 27601, May 19,1998). The staff published a notice ofintent to prepare an EIS and conduct scoping (63 FR 31813, June 10,1998). Two public scoping meetings were held on July 9,1998, in Solomons, Maryland. Comments received during the scoping process were summarized in the EnvironmentalImpact Statement Scoping Process, Calvert Cliffs Nuclear Power Plant, Summary Report, October 1998 (NRC 1998a).
The staff visited the CCNPP site on July 7 through 10,1998, reviewed the comments received during ' scoping, and consulted with Federal, State, and local agencies. A list of the organizations consulted is l provided in Appendix D of this document. Other documents related to CCNPP were also reviewed ana l ara referenced. j l The staff followed the review guidance contained in the February 1999 prepublication version of the l ESRP (which was under development at the time of the BGE application). It issued requests for l cdditional information (RAls) to BGE by letters dated September 9, and September 28,1998 (NRC l 1998b and 1998c). BGE provided its responses in letters dated November 20, and December 3,1998 l (BGE 1998c and 1998d). The staff reviewed this information, incorporated it into its analysis, and, on l February 24,1999, issued a draft of the SEIS, which contains the preliminary results of its evaluation l and recommandation. l 1 With the publication of the EPA notice of filing of the draft SEIS (64 FR 10662, March 5,1999), a 75-day l comment period began to allow members of the public to comment on the preliminary results of the l NRC staff's review. During this comment period, two public meetings were held in Maryland on April 6, l 1999, in which the staff described the results of the NRC environmental review and answered questions l related to it in ordar to provide members of the public with information to assist them in formulating their l comments. The comment period for the CCNPP draft SEIS ended on May 20,1999. l l This report presents the staff's final analysis that considers and weighs the environmental effects of the l license renewal, the environmentalimpacts of alternatives to license renewal, and alternatives available l for avoiding adverse environmental effects. The staff consioered the comments that were received [ during the comment period. The disposition of these comments is addressed in Appendix A of this [ NUREG-1437, Supplement 1 1-5 October 1999 (
- s. m -
Introduction l SEIS. The staff modified the analysis set forth in the draft SEIS to address certain comments, where l appropriate. A vertical bar in the margin indicates where the staff made changes to the draft SEIS. In ; l addition, the NRC staff's final recommendation to the Commission on whether the adverse ! l environmental impacts of license renewal are so great that preserving the option of license renewal for l energy planning decisionmakers would be unreasonable is provided in Chapter 9, " Summary and l Conclusions." 1.1 The Proposed Federal Action l The proposed Federal action is renewal of the operating licenses for CCNPP Units 1 and 2. CCNPP is l located in Calvert County, Maryland, approximately 64 km (40 mi) southeast of Washington, D.C., 12 km (7.5 mi) north of Solomons Island, and 96 km (60 mi) south of Baltimore. The plant has two l pressurized light-water reactors, each with a design rating of 845 megawatts electric (MWe). Plant cooling is provided by a once-through heat dissipation system into the Chesapeake Bay using shc Lne l intake and offshore dischargo structures. CCNPP provides about 12 million MW-hours of electricity 2 annually to more than one million customers in a 5900-km (2300-m2 ) area. The current operating licenses for Unit 1 and Unit 2 expire July 31,2014, and August 13,2016, respectively. By letter dated April 8,1998, BGE submitted an application to renew these operating licenes for an additional 20 years of operation (i.e., until July 31, 2034, for Unit 1 and August 13,2036, for Unit 2). 1.2 Purpose and Need for the Action Although a licensee must have a renewed license to operate a plant beyond the term of the existing operating license, the possession of that license is just one of a number of conditions that must be met l for the licensee to continue plant operation during the term of the renewed license. Once an operating l license is rereved, State regulatory agencies and the owners of the plant will ultimately decide whether the plant will continue to operate based on factors such as the need for power or other matters within the State's jurisdiction or the purview of the owners. Thus, for license renewal reviews, the Commission has adopted the following definition of purpose and l need (GEIS, Section 1.3): The purpose and need for the proposed action (renewal of an operating license) is to provide an option that allows for power generation capability beyond the term of a current nuclear power plant operating license to meet future system generating needs, as such needs may be determined by State, utility, and, where authorized, Federal (other than NRC) decisionmakers. l This definition of purpose and need reflects the Commission's recognition that, unless there are findings in the safety review required by the Atomic Energy Act of 1954, as amended, or findings in the October 1999 1-6 NUREG-1437, Supplement 1
Introduction NEPA environmental analysis that would lead the NRC to reject a license renewal application, the NRC does not have a role in the energy planning decisions of State regulators and utility officials as to whether a particular nuclear power plant should continue to operate. From the perspective of the licensee and the State regulatory autnority, the purpose of renewing an operating license is to maintain tha availability of the nuclear plant to meet system energy requirements beyond the current term of the pl nt's license. 1.3 Compliance and Consultations BGE is required to hold certain Federal, State, and local environmental permits, as well as meat rel:vant Federal and State statutory requirements. BGE provided a list in its ER of the status of l authorizations from Federal, State, and local avhorities for current operatbns as well as environmental approvals and consultations associated with CCNPP license renewal. Authorizations most relevant to ths proposed license renewal action are summarized in Table 1-1. The full list of authorizations provided by BGE is included as Appendix E. MDNR coordinated reviews and interactions with other l St:te agencies. The staff reviewed the list and consulted with the appropriate Federal, State, and local agencies to id:ntify any compiiance or permit issues or significant environmental issues of concem to the reviewing l ag ncies. Agency interactions identified no new compliance or permit issues or significant new cnvironmental issues. l t 1.4 References k 10 CFR Part 51, " Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions." s 10 CFR 51.23, " Temporary storage of spent fuel after cessation of reactor operation-generic d: termination of no significant environmentalimpact." 10 CFR 51.53, "Postconstruction environmental reports." l 10 CFR PE.t 51, Subpart A, Appendix B, Table B-1, " Environmental effect of renewing the operating l license of a nuclear power plant." l 10 CFR Part 54, " Requirements for Renewal of Operating Licenses for Nuclear Power Plants." 10 CFR 54.23, " Contents of application-environmentalinformation." 40 CFR 1508.27, " Terminology and index-Significantly." NUREG-1437, Supplement 1 1-7 October 1999 1 1
l Introduction Table 1-1. Federal, State, and Local Authorizations l l License / Permit l l Licensel Permit Expiration or Agency Authority Requirement Number Consultation Date Activity Covered l NRC Atomic Energy Environmental DPR-53, DPR-69 OLs expire July 31,2014 Refurbishment Act,10 CFR Report August 13,2016 and operation 5423,10 CFR during the Part 51 renewal term l EPA Clean Water Act, State water quality NA Expires June 15,1999*) Discharges under l Section 401* certification NPDES of pro-cess waste water MDE COMAR 26.17.06 State water CA69G010 Expires April 1,2001 CCNPP use of appropriation (04) groundwater from permit 5 wells in 1 protected area l MDE COMAR 26.17.06 State water CA71S001 Expires April 1,2001 CCNPP use of appropriation (02) surface water for pemiit cooling l MDE COMAR 26.08.04 State discharge 92-DP-0187 Expires June 15,19995 Wastewater i permit (MD 0002399) discharge permit FWS and Endangered Consultation NA Consultation letters from Operation during NMFS Species Act, FWS dated November 3, the renewal term Section 7 1998, and from NMFS dated February 12,1998, i identifying threatened and endangered species l MDE Coastal Zone Certification by NA Letter from MDE to NRC Operation during Management Act applicant that dated February 12,1998, the renewal term action is consistent concurring with with coastal consistency certification management programs Maryland National Historic Consultation NA Confirmation from Operation during Historic Trust Preservation Act, Maryland Historic Trust the renewal term , Section 106 on October 22,1997, that l action is unlikely to affect properties l EPA - U.S. Environmental Protection Agency MDE - Maryland Department of the Environment FWS - U.S. Fish ane WLdlife Service NMFS - National Marine Fisheries Service l COMAR - Code of Maryland Regulations l NPDES - National Pollutant Discharge Elimination System l NA - Not applicable l (a) Federal Water Pollution Control Act (FWPCA), also known as the Clean Water Act l (b) Application to extend permit under review October 1999 1-8 NUREG-1437, Supplement 1
Introduction 63 FR 27601, " Notice of Acceptance for Docketing," May 19,1998. 63 FR 31813. " Notice of Intent to Prepare an Environmental impact Statement and Conduct Scoping ' Process." June 10,1998.- 64 FR 10662 " Notice of Filing." March 5,1999. l l Atomic Energy Act of 1954 (AEA), as amended,42 USC 2011, et seg.
.B ltimore Gas and Electric Company (BGE).1998a. Applicant's EnvironmentalReport- Operating l License Renewal Stage Calvert Cliffs NuclearPowerPlant Units 1 and 2. Docket Nos. 50-317 and 'i 50-318. Lusby, Maryland.'
Britimore Gas and Electric Company (BGE).1998b. Attachment to Memorandum to T. Essig l gummarizing the site visit. "New and Significant Information Process for License Renewal of Calvert Cliffs Nuclear Power Plant." July 10,1998. B2ltimore Gas and Electric Company (DGE).1998c. Letters frem. Mr. C.H. Cruse (BGE) to NRC Document Control Desk, " Response to Request for Additional Information for the Review of the Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Environmental Report Associated with License Renewal, , and Errata (TAC Nos. MA1524 and M1525)," November 20, and December 3,1998, Lusby, Maryland. 1 Ccastal Zone Management Act, as amended (CZMA),16 USC 1455 et seq. j i Endangered Species Act (ESA), as amended,7 USC 136; 16 USC 460 et seq. i Federal Water Pollution Control Act (FWPCA) (also known as the Clean Water Act), as amended,33 l USC 121 et seq. N:tional Environmental Policy Act of 1969, as amended,42 USC 4321, et seg. N;tional Historic Preservation Act, as amended,16 USC 470 et seq. l U.S. Nuclear Regulatory Commission (NRC).1996. Generic Environmentallmpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437. Washi:qton, D.C. ' U.S. Nuclear Regulatory Commission (NRC).1998a. Environmental /mpact Statement Scoping Process: Summary Report-Calvert Cliffs NuclearPower Plant, Lusby, Maryland. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1998b. . Letter from Ms. C.M. Craig (NRC) to l Mr. C.H. Cruse (BGE), " Request for Additional Information for the Review of the Calvert Cliffs Nuclear l NUREG-1437 Supplement 1 1-9 October 1999 l i
Introduction - l - Power Plant (CCNPP) Unit Nos.1 & 2, License Renewal Application, Severe Accident Mitigation l Altematives (TAC Nos. MA 1524 and MA 1525)," September 9,1998, Washington, D.C. l . l U.S. Nuclear Regulatory Commission (NRC).1998c. Letter from Ms. C.M. Craig (NRC) to Mr. ~l C.H. Cruse (BGE), " Request for Additional information for the Review of the Calvert Cliffs Nuclear l Power Plant (CCNPP) Unit Nos.1 & 2, Environmental Report Ascociated with License Renewal (TAC l Nos. MA 1524 and MA 1524)," September 28,1998, Washington, D.C. l l U.S. Nuclear Regulatory Commission (NRC).1999a. Generic Environmentalimpact Statement for l License Renewalof NuclearPlants, Main Report, Sectio: 6.3-Transportation, Table 9.1 Summary of l findings on NEPA issues forlicense renewalof nuclearpowerplants. NUREG-1437 Vol.1, Addendum l 1, Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1999b. Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal. NUREG-1555, Supplement _1. Washington, D.C.
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October 1999 1-10 NUREG-1437, Supplement 1
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l i
2.0 Description of Nuclear Power Plant and Site and Plant Interaction with the Environment CCNPP is located near Maryland Highway 2-4 in Calvert County on the west bank of.the Chesapeake B:;y, approximately halfway between the mouth of the Bay and its headwaters at the Susquehanna River. CCNPP is a two-unit plant. Each unit is equipped with a Combustion Engineering Nuclear St:am Supply System pressurized light-water reactor and uses once-through cooling with water from ths Chesapeake Bay. CCNPP supplies more than 12 million megawatt-hours annually to customers in a 5900-km2(2300-mi2) area. The electricity generated is transferred through a power transmission system that consists of two transmission lines to the Waugh Chapel Substation on the Northem Circuit and a single transmission line to the Chalk Point Generat5g Station on the Southem Circuit. Descriptions of the plant and its environs follow in Section 2.1, and the plant's interaction with the environment is presented in Section 2.2. 2.1 Plant and Site Description and Proposed Plant Operation l During the Renewal Term l CCNPP is located on 853 hectares (ha) (2108 acres) in a rural part of southem Maryland on wooded and agricultural lands. It draws its workforce of about 1550 from surrounding communities, and is the major employer in the area. Several small communities are located within a 16-km (10-mi) radius of the sits. The population density of the area increases with seasonal summer residents. The population d:nsity increases with distance to the northwest and the 80-km (50-mi) radius includes a portion of the Washington, D.C., metropolitan area. Baltimore is 96 km (60 mi) to the north. Figures 2-1 and 2-2 t illustrate the plant location with respect to the Chesapeake Bay and the Patuxent River. l Ths property consists of rolling hills, part of it forested primarily with deciduous trees. There is an l understory of grasses, herbs, and shrubs. Part of the land is cultivated under an experimental pest control / fertilization program, and hay, com, and wheat are routinely cultivated. About 89 ha (220 acres) l of the site were altered for plant and auxiliary structures. About 30-40 ha (75-100 acres) of CCNPP borders the Chesapeake Bay. Most of this Bay frontage has near-perpendicular walls. Bay frontage ' cl ,vation varies from sea level to about 42 m (137 ft) with an average of about 30 m (100 ft). t I D.a topography of the vicinity around the plant defines several small watersheds. The watershed j corr aining the plant and the auxiliary structures drains into the Chesapeake Bay. Part of the upper are as, used primarily during the construction period, drains through the Johns Crmk watershed into the l l St. Leonard Creek, which then drains into the Patuxent River approximately 7 km b mi) from the plant. l Th3 Patuxent River drains into the Chesapeake Bay approximately 16 km (10 mi) south of the plant. l NUREG-1437, Supplement 1 2-1 October 1999
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PI:nt and ths Environment Chesapeake Bay is approximately 313 km (195 mi) long and varies in width from 5 to 56 km (3 to 35 mi) l with an average width of 24 km (15 mi) (Figure 2-1). The Bay has an average depth of approximately 9 m (30 ft) and receives the majority of its fresh water, sediment, and nutrients from the Susquehanna River. The Susquehanna watershed encompasses three states, and its flow dominates the circulatory l pattems in the upper Bay during the spring months, with the majority of the net flow directed seaward at l all depths (K. G. Sellner and B. A. Peters in Heck 1987). Circulation in the Bay is typical of a partially mixed estuary with non-tidal and tidal components producing a net seaward-moving fresh water surface layer and a landward-moving saline 'ayer (Pritchard 1967). The Chesapeake Bay is about 10 km (6 mi) wide at the plant site from its western shore to Taylors Island. 2.1.1 External Appearance and Setting CCNPP is sited within a forested natural saddle along the Calvert Cliffs, providing a low profile for the plant. The tallest structures do not rise above the top of the surrounding tree line when viewed from the land areas or from the water. The Turbine Building, which houses two turbine generators and ancillary equipment, is the largest structure on the site and parallels the shoreline of the Bay. Twin containment structures and the Auxiliary Building are located to the west of the Turbine Building. The intake l Structure is located east (bayside) of the Turbine Building. The buildings and the switchyard were designed to minimize their visualimpact. Disturbed areas are landscaped or otherwise maintained. Although several additional facilities have been constructed at CCNPP since 1973, the plant, as it appears from the Chesapeake Bay, has changed little. Figures 2-3 and 2-4 show the station in detail, I highlighting those permanent facilities constructed since plant operation began. Figure 2-5 is a low-level aerial photograph of CCNPP taken from the Bay looking south-southwest that shows the major plant structures, including the Turbine Building and twin containment structures. The Interim Office Building, Intake Structure, North Service Building, and Sewage Treatment Plant are also visible from the Bay. Most of the other new facilities are visible only from the air due to intervening buildings and wooded hillsides. Except for the Independent Spent Fuel Storage Installation, which has a separate NRC license, all of the additional facilities are located on areas previously disturbed during CCNPP construction. The onsite Visitors Center is located in a remodeled old working frame tobacco barn, part of which was l built in 1818 (Stone 1978). The center displays historic artifacts, dioramas, and animated exhibits that cover the history of the location, and focuses on the site's present use for nuclear power generation. The Visitors Center area also includes the stabilized foundation and chimneys of a small Maryland plantation house of the 18th century, known as "Preston's Cliffs," and a historic log tobacco barn that is reported to be the oldest of its kind still standing in Maryland. The log barn was constructed in 1820. In addition to the Visitors Center, BGE maintains a nature trail that begins at the historic house foundation and includes highlights of the area's historical and natural setting, including the Chesapeake Bay and its shoreline ecology. October 1999 2-4 NUREG-1437, Supplement 1
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Plint and the Environm:nt The site's Geologic setting' lies within the Coastal Plain Physiographic Province, and is u1derlain by I approximately 760 m (2500 ft) of sedimentary strata. Underlying these sediments are crystalline and metamorphic basement rock. There is no evidence of faulting in the site vicinity. As shown in Figure 2-6, the strats range from nearly 3 horizontal to gently dipping to the southeast, reflecting the influence of the basement rock slope. Areas above an elevation of 21 m (70 ft) are Pliocene and Pleistocene sitt and sand, and are underlain by approximately 82 m (270 ft) (Elevation +70 to -200 feet mean sea level (MSL)) of the relatively impervious sediments of the Chesapeake group of Miocene age; the CCNPP power block area is Elevation +45 feet MSL.' The Miocene-age sediments consist of horizontally stratified sandy and clayey
' silt with occasional interbeds of sands and shells. Approximately 106 m (350 ft) (Elevation -200 to -550 feet MSL) of dense, relatively pervious glauconitic sand and silt of the Eocene and Paleocene age underlie the Miocene sediments.
The site incluces a portion of the Calvert Cliffs, noted for scenic and scientific significance. Some of the fossils recovered at the site during an in-depth paleoecological study of the Miocene deposits are displayed at the Visitors Center. Table 2-1 provides a brief summary of groundwater aquifers beneath CCNPF The site water table occurs generally within 9 m (30 ft) (above Elevation +70 feet MSL) of the surface in Pleistocene-age deposits. Groundwater flow within approximately 300 m (1000 ft) of the Chesapeake Bay at CCNPP is toward the Bay; flow west of the divide is toward surface stream valleys. Surficial soil -l grain size analysis suggests a maximum permeability coefficient of about 6.1x10d m/s (400 gpd/ft2), Surficial deposits are underlain by approximately 75 m (250 ft) of relatively impermeable deposits, known as the Chesapeake Group, which effectively confine the underlying artesian aquifars. The vertical component of groundwater movement through the Chesapeake Group is upward. Underlying aquifers are composed of glauconitic sand and sitt of the Piney Point, Nanjemoy, and Aquia formation. The Piney Point and Nanjemoy Aquifers act as a single unit, but are separated from the underlying Aquia Aquifer by a layer of clay and sitt called the Nanjemoy-Marlboro confining unit. The Aquia Aquifer beneath CCNPP is approximately 30 m (100 ft) thick (from Elevation -450 to -550 feet MSL). 2.1.2 Reactor Systems CCNPP is a two-unit plant. Each unit is equipped with a Combustion Engineering Nuclear Steam Supply System that uses a pressurized light-water reactor and two steam' generators. Each unit has a design rating for net electrical power output of 845 MW. The two CCNPP reactors are operated at a maximum core thermal power output level of 2700 MW. The Unit 1 turbine generator is a General Electric Company design, and Unit 2 is a Westinghouse Electric Corporation design. Each turbine is an 1800-rpm tandem compound, six-flow exhaust, indoor unit (BGE 1998a). October 1999 2-8 NUREG-1437, Supplement 1
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Pl:nt and the Environment Table 2-1. A Summary of Groundwater Aquifers Beneath CCNPP(*) Physical Thickness in Approximate Elevation Description Description Water-Bearing Properties Region m (ft) at CCNPP* m (ft) Surficial Silt, sand, and Small quantities of water to 0-46 Above +21 deposits some clay shallow wells (0 -150) (Above +70) Chesapeake Sandy and Yields small amounts of water in 9-99 Between +21 and -61 Group clayey sitt a few dug wells (30 - 325) (Between +70 and -200) l Piney Point Glauconitic Yields up to 12.6 Us (200 0-18 Between -61 and -73 Formation sand gpm). Important aquiferin (0 - 60) (Between -200 and -240) Calvert County l Nanjemoy Glauconitic Yields up to 3.8 Us (60 gpm) 12 -73 Between -240 and -300 Formation sand with reported. Important aquifer in (40-240) (Between -240 and -300) clayey layers Calvert County Nanjemoy- Clay, sitt Confining unit 0 - 213 Between -91 and -137 Marlboro (0 - 700) (Between -300 and -450) l Aquia Green to brown Yields up to 18.9 Us (300 gpm). 9 - 61 Between -137 and -168 Formation glauconitic important aquifer in Southem (30 -200) (Between -450 and -550) sand Maryland l (a) Source: BGE 1998a. l (b) Elevations are above (+) or below (-) MSL. CCNPP fuel is slightly enriched uranium dioxide in the form of pellets contained in zirconium alloy fuel rods (tubes fitted with welded end caps). CCNPP was originally licensed to use fuel having a uranium-235 enrichment not exceeding 4 percent by weight." In 1981, NRC authorized an increase in fuel ' enrichment up to 4.1 percent uranium-235. In 1989, NRC authorized another increase to 5 percent uranium-235; at the same time, NRC also authorized an increase the in level of CCNPP fuel bumup,* l above the original 33,000 megawatt-days per metric tonne uranium (mwd /MTU) to 60,000 mwd /MTU. Reactor containment structures are designed with engineered safety features to protect the public and plant personnel from accidental release of radioactive fission products, particularly in the unlikely event of a loss of coolant accident (LOCA). These safety features function to localize, control, mitigate, and terminate such events to limit exposure levels below applicable dose guidelines. The reactor is controlled using a combination of chemical controls (boric acid dissolved in coolant water) and solid absorber material (tubes of boron carbide). (a) Naturally occurring uranium contains several forms of uranium, including approximately 0.7 percent uranium-235, the form that a nuclear reactor uses. The nuclear fuel manufacturing process removes some of the other forms, resulting in si slightly higher percentage (" enrichment") of uranium-235. (b) "Bumup" is the length of use of, or total energy generated by, the nuclear fuel, and is measured as megawatt-l days per metric tonne uranium. October 1999 2-10 NUREG-1437, Supplement 1
Plant and tha Environment l 2.1.3 Cooling and Auxiliary Water Systems l CCNPP is equipped with a once-through heat dissipation system that withdraws cooling water from and discharges it to the Chesapeake Bay. This circulating water system removes heat from the plant and l transfers this energy to the Chesapeake Bay. There are no cooling towers associated with this system. CCNPP uses water from the Chesapeake Bay for cooling purposes, drawing bottom water through a 15-m (45-ft) deep dredged channel that extends approximately 1380 m (4500 ft) offshore. Water l pisses through the plant in approximately 4 minutes and is discharged to the north of the plant from an outfall that is approximately 260 m (850 ft) offshore in 3 m (10 ft) of water. A curtain wall that extends to l a depth of 9 m (30 ft) over the intake channel limits the intake to mostly bottom water, although there is l cvidence that mixing of surface and lower depth water occurs before entrance inte the plant (Heck 1987). The intake and discharge structures are shown in Figure 2-7. Each generating unit has three separate water loops. The primary coolant loop is a closed piping system--pressurized water in the system is circulated th,ough the reactor and transfers b rat from the r: actor to the steam generator. The primary coolant system for each unit consists of a reactor, two l stram generators, two reactor coolant loops, and four reactor coolant pumps. The secondary loop is l also a closed system-water from this syr'em is converted into steam (in the steam generators) that is used to drive the turbine. The third loop is an open system-water from Chesapeake Bay is used to cool the spent steam in the secondary loop and then is retumed to the Bay. The principal components of the circulating water system are the curtain wall, intake structure, i circulating water pumps, condensers and discharge conduits. CCNPP has five groundwater production wells that supply process and domestic water in the protected j ar:a of the plant (Figure 2-3), and eight wells that supply water for domestic use in outlying areas. The l production wells extend into the Aquia Aquifer. Although a gravity drain system was installed during original plant construction to dewater plant areas, CCNPP does not use dewatering pumps for plant operation. Groundwater wells provide the source of water for domestic, plant service and demineralized make-up l water needs, while the Chesapeake Bay is the source of water for the once-through cooling system. All effluento are combined before being discharged through the submerged outfall to the Chesapeake Bay. l Both the quantity of water pumped (from both the groundwater wells and the Chesapeake Bay) and qu lity of the water discharged to the Chesapeake Bay are regulated and permitted by the State of Mrryland. NUREG-1437, Supplement 1 2-11 October 1999
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Pl:nt and tha Environm:nt 2.1.4 Radioactive Waste Management Systems and Effluent Control-Systems The CCNPP waste processing ' systems meet the design objectives of 10 CFR Part 50, Appendix 1, and control the processing, disposal, and release of radioactive liquid, gaseous, and solid wastes (BGE l 1997). Radioactive material in the reactor coolant is the source of gaseous, liquid, and solid radioactive l wistes in light-water reactors (LWRs). Radioactive fission products build up within the fuel as a consequence of the fission process. These fission products are contained in the sealed fuel rods, but smill quantities escape the fuel rods and contaminate the reactor coolant. Neutron activation of the primary coolant system also is responsible for coolant contamination. Non-fuel solid wastes result from treating and separating radionuclides from gases and liquids and from l r: moving contaminated material from various reactor areas. Solid wastes also consist of discarded l rc:ctor components, equipment, and tools as well as contaminated protective clothing, paper, rags, and other trash largely from plant design and operations modifications and routine maintenance activities. Certain dry wastes may be shredded or compacted under high pressure to reduce disposal volume. Spent resins, filters, and evaporator concentrates are dewatered and stored or packaged for shipment : to cn offsite p'rocessing or disposal facility. Fu:1 rods that have exhausted a certain percentage of their fuel and are removed from the reactor core for disposal are called spent fuel. CCNPP currently operates on a 24-month refueling cycle and stores til its spent nuclear fuel onsite either in a spent fuel pool in the Auxiliary Building or in dry storage at its Independent Spent Fuel Storage Installation (BGE 1992). CCNPP also temporarily stores mixed waste onsite. This storage is governed by the Atomic Energy Act (AEA) for radioactive material and the l R: source Conservation and Recovery Act (RCRA) for hazardous waste, consistent with NRC and EPA ] r quirements (42 USC 2011-2259 (AEA]; 42 USC 6901 [ RCRA]) and in accordance with an agreement I with the Maryland Department of the Environment (MDE). Th:re are four waste processing systems: the Reactor Coolant Waste Processing System (RCWPS), the Miscellaneous Waste Processing System (MWPS), the Waste Gas Processing System (WGPS), cnd the Solid Waste Processing System (SWPS). 2.1.4.1 Liquid Waste Processing Systems and Effluent Controls Radioactive liquid waste generated from the operation of CCNPP can be released to the Chesapeake l B y in accordance with the limits specified in the CCNPP Offsite Dose Calculation Manual (ODCM). Th re are four outfalls that provide the pathways for all waste water (non-radioactive and radioactive) discharged into the Bay. NUREG-1437, Supplement 1 2-13 October 1999 i
l Plant and th3 Environm':nt CCNPP liquid waste is processed by two systems: (1) the RCWPS, which processes reactor coolant concurrent with the letdown flow from the Chemical and Volume Control System (CVCS), and (2) the l MWPS, which processes waste from miscellaneous sources. The liquid waste processing systems are used to reduce the radioactive material in liquid wastes before discharge when the activity in the effluent could exceed the ODCM limits. The RCWPS provides temporary storage for reactor coolant waste (RCW) to allow for radioactive decay to maintain releases to the environment as low as reasonably achievable (ALARA), as well as l maintain the concentration of radioactive isotopes in the effluent below the ODCM limits. Sampling and release of liquid waste is performed on a batch basis, rather than a continuous basis, to provide better control over effluent discharge. l The RCWPS consists of two reactor coolant drain tanks (RCDTs), three cartridge filters, four RCW ion exchanqers, two RCW receiver tanks, two evaporators, two RCW monitoring tanks, and various system pump ' he system simultaneously processes reactor coolant and CVCS letdown flow from both Unit 1 and Umt 2. l Before being transferred to the two RCW receiver tanks, the RCW liquid is filtered to remove insoluble corrosion prodtrcts and then degasified to remove hydrogen, nitrogen, and fission gases. The liquid is pumped to ion exchangers that remove soluble ions, thereby resulting in an effluent that is reduced in total activity. The liquid is then routed to the RCW monitor tank where it is sampled. If the activity level in the monitor tank is within discharge limits, then the liquid may be released in a controlled, monitored fashion to meet the administrative limits in the ODCM. t Controls for limiting the release of radiological liquid effluents are described in the ODCM. Controls are l based on (1) concentrations of radioactive materials in liquid effluents and projected dose or (2) dose f commitment to a member of the public. Concentrations of radioactive material that may be released in j liquid effluents to unrestricted areas are limited to the concentrations specified in 10 CFR Part 20, l Appendix B, Tab!e ll?) The dose limits are 0.03 millisievert (mSv) (3 mrem) to the whole body and 0.10 mSv (10 mrem) to any organ during any calendar quarter and 0.06 mSv (6 mrem) to the whole l body and 0.20 mSv (20 mrem) to any organ during a calendar year. Radioactive liquid wastes are I subject to the sampling and analysis program described in the ODCM. 2.1.4.2 Gaseous Waste Precessing System and Effluent Controls Radioactive gaseous waste generated from operation of CCNPP may be released to the atmosphere through the Unit 1 and Unit 2 main vent stacks, the auxiliary boiler deaerator, the steam generator atmospheric steam dump system, the plant nitrogen system, the turbine building ventilation exhaust, the (a) CCNPP is authorized to use the previous version of 10 CFR Part 20, Appendix B, Table 11 (the l current version is Table 2). October 1999 2-14 NUREG-1437, Supplement 1
PI nt and ths Environment Gmergency air lock, the plant compressed air system, the main steam line penetrations, the containment equipment hatch, and the auxiliary feedwater pumps. During normal operation, the WGPS is designed to store the gases removed from liquid waste to allow l for radioactive decay before release. The WGPS consists of a surge tank, two compressors, three wista gas decay tanks and a high efficiency particulate air (HEPA) filter. The WGPS collects, stores, end disposes of gaseous waste from the degasifiers, pressurizer quench tanks, RCDTs, the volume control tanks, and other miscellaneous hydrogenated sources. l Thera are other potential sources of gaseous releases from the plant that are not collected in the l WGPS. Leaks from reactor coolant containment structures, condenser air removal systems, and other pot:ntial sources are released through the plant vent. The following are the pathways for gaseous cfflutnts containing or potentially containing radioactive material:
- WGPS i containment structure purge e containmert hydrogen purge system a cuxiliary building ventilation
- condenser air removal system and gland seal exhauster e aerated tank vents e turbine building ventilation.
BGE maintains all gaseous releases within ODCM limits. Potential release pathways are sampled l tecording to approved plant procedures. l Th3 WGPS is used to reduce the radioactive material in gaseous waste before discharge to meet the l dose design objectives in 10 CFR Part 50, Appendix 1. In addition, the limits in the ODCM are designed I~ to provide reasonable assurance that radioactive material discharged in gaseous effluents would not r:sult in the exposure of a member of the public in an unrestricted area in excess of the limits specified in 10 CFR Part 20, Appendix B. The quantities of gaseous effluents released from CCNPP are controlled by the administrative limits d: fined in the ODCM. The controls are specified for dose rate, dose due to noble gases, and dose due to iodine and radionuclides in particulate form. For noble gases, the dose rate limit at or beyond the site boundary is 5 mSv/yr (500 mrem /yr) to the whole body, and 30 mSv/yr (3000 mrem /yr) to the skin. For l iodin 3 and particulates with half lives greater than eight days, the limit is 15 mSv/yr (1500 mrem /yr) to l Eny organ. The limit for air dose due to noble gases released in gaseous effluents to areas at or y . beyond the site boundary during any calendar quarter is 0.1 milligray (mGy) (10 mrad) for gamma radi: tion and 0.2 mGy (20 mrad) for beta radiation, and, for any calendar year, the limit is 0.2 mGy (20 mrad) for gamma radiation and 0.4 mGy (40 mrad) for beta radiation. The radioactive gaseous waste simpiing and analysis program specifications are provided in the ODCM, and address the gaseous NUREG-1437, Supplement 1 2-15 October 1999
Plant and th3 Environm::nt release type, sampling frequency, minimum analysis frequency, type of activity analysis, and the lower l limit of detection. The WGPS is used to reduce radioactive material in gaseous waste before its discharge when the gaseous effluent air doses due to gaseous effluent releases to the area at and beyond the site boundary are projected to exceed 0.012 mGy (1.2 mrad) tcr gamma radiation and 0.024 mGy (2.4 mrad) for beta radiation in a 92-day period. ' i 2.1.4.3 Solid Waste Processing and Handling { I l Solid waste is packaged in containers to meet the applicable requirements of 49 CFR Parts 171 through l 177. Disposal and transportation are performed in accordance with the applicable requirements of 10 l CFR Parts 61 and Part 71, respectively. The SWPS provides the capability for preparing solid waste for shipment to an offsite disposal facility or processor. The system is designed to minimize radiation exposure to personnel during the handling of solid wastes. The SWPS equipment is located in the Auxiliary Building. Spent radioactive ion exchanger resin is sluiced to a tank where it is stored and partially dewatered. It is then prepared for shipment. RCWPS l evaporator bottoms are normally recycled or otherwise processed in accordance with BGE's Process l Control Program. Radioactive filters are transported from each filter housing to the waste disposal area. All solid wastes are packaged in containers suitable for transfer to an offsite processor or disposal. The Materials Processing Facility (MPF) provides interim storage of dry active waste (DAW) until such l waste can be shipped to a permanent disposal facility or a processing facility. The storage capacity of the MPF can accommodate more than five years of expected waste generated at CCNPP, based on normal operation and generation. Provisions are in place for additional expansion, if needed. The design life of the MPF is expected to meet the needs of the license renewal term. The functions of the MPF are interim storage o' DAW and low-level processed wastes; decontamination of clothing, respirators, tools, hardware, and radioactive waste material; temporary holding of liquid wastes generated from the laundry; receiving, sorting, compacting, packaging, and offsite retum shipment of DAW; office space for radwaste management activities; additional storage of spare plant equipment and l components; and processing of liquid waste in the decontamination facility in preparation for offsite shipment. There are two areas for resin storage: (1) the interim resin storage facility located in the Lake Davies l area (waste is limited to spent resins and filters); and (2) the West Road Cage located west of the l Auxiliary Building. All CCNPP radioactive waste shipments are packaged in accordance with NRC and U.S. Department of Transportation requirements. CCNPP currently transports shipments of radioactive material to
. high-level waste examination sites October 1999 2-16 NUREG-1437, Supplement 1
l Plant and ths Environm:nt e low-level waste disposal site (Bamwell, ' South Carolina) 4 ' offsite processing facility for segregation, recycling, compaction, decontamination, and incineration. l
.CCNPP also transports material from an offsite processing facility to a disposal site or back to the plant site for reuse or storage.
2.1.5 Nonradioactive Waste Systems Nonradioactive waste is produced from plant maintenance and cleaning processes. Most of these wistes are from boiler blowdown (as impurities are purged from plant boilers), water treatment sludges and other wastes, boiler metal cleaning wastes, floor and yard drains, and stormwater runoff. Chemical, cnd biocide waste sources are produced from processes to control the pH in the coolant, to control scale, to control corrosion, and to regenerate resins, as well as for cleaning and condenser defouling. l W:stes may be discharged as separate point sources or combined with the cooling water discharges. Sewage sludge is transported for offsite disposal. The MDE is responsible for permitting the disposal of nonradioactive liquid and solid wastes. 2.1.6 Plant Operation and Maintenance Routine maintenance performed on plant systems and con ponents is necessary for safe and reliable
- operation of a nuclear power plant. Some of the maintenance activities conducted at CCNPP include inspection, testing, and surveillance to maintain the cc, rent licensing basis of the plant and to ensure compliance with environmental and public safety requirements. Certain of these activities can be performed 'while the reactor is operating. Others require that the plant be shut down. Long-term outages are scheduled for refueling and for maintenance, modification, and replacement of major l components. Scheduled refueling outages generally last for about two months and occur at 1- to 2-year l intervals. Periodic in-service inspections may last 2 to 4 months, while other outages vary, depending l on the components being replaced.
BGE performed an aging management review and developed an integrated plant assessment (IPA) for l minaging the effects of aging on systems, structures, and components in accordance with 10 CFR Part 54. It also reviewed its surveillance, on-line monitoring, inspections, testing, trending, and r:cordkeeping (SMITTR) program, and identified the need for new and modified programs that could leid to additional periodic monitoring or to eventual modification, replacement, or repair of selected components.
' Some of the activities listed in Tables 2-7 and B.2 of the GEIS (NRC 1996) have been or are being l conducted at CCNPP. For example, the plant is replacing its steam generators during its current l license term and, consequently, this replacement does not meet the definition of a license renewal term refurbishment activity. The CCNPP IPA, conducted under 10 CFR Part 54, did not identify major l
' refurbishment or replacement activities necessary to maintain the functionality of important systems, NUREG-1437, Supplement 1 2-17 October 1999
I Pl:nt end the Environm:nt I structures, and components during the CCNPP license rene'wal term. Therefore, BGE expects to conduct normal refueling and 5- and 10-year inservice inspections, but plans no refurbishment outages specific to license renewal. 2.1.7 Power Transmission System The CCNPP power transmission system includes the North Circuit, which consists of two separate three-phase 500-kV transmission lines (single right-of-way) from CCNPP to the Waugh Chapel - Substation in Anne Arundel County (Figure 2-1), and the single-line South Circuit from CCNPP l northwest to the Potomac Electric Power Company (PEPCO) Chalk Point generating station. Approximately 35 km (22 mi) of the lines in the northem circuit are in Calvert County and approximately 40 km (25 mi) are in Anne Arundel County in a 106- to 122-m wide (350- to 400-ft) rights-of-way. These lines were constructed to deliver power generated at CCNPP to the Waugh Chapel Substation, located at a point near BGE's load center. Each line consists of about 182 lattice towers and about 47 stylized poles. The liner cross mostly second-growth hardwood and pine forests, pasture, and farmland. In 1994, BGE completed the South Circuit 500-kV line, shifting approximately 1.6 km (1 mi) of the original lines to make room for the new South Circuit lines at the point where the North and South Circuit routes diverge (Figure 2-1). The 29 km (18-mi) South Circuit parallels the Waugh Chapel lines from CCNPP north approximately 14 km (9 mi) before diverging in a northwesterly direction to connect l with a line at the PEPCO Chalk Point generating station (Figure 2-1). BGE owns the land beneath the North and South Circuit lines. At the time that BGE constructed CCNPP, the Southem Maryland Electric Cooperative constructed a 69-kV transmission line to CCNPP, connecting to an onsite substation (Figure 2-3) to provide CCNPP l with offsite power. The plant is connected to the substation via underground lines. After CCNPP l decommissioning, the Southem Maryland Electric Cooperative plans to discontinue the transfer of energy over these lines. 2.2 Plant Interaction with the Environment Subsections 2.2.1 through 2.2.8 provide general descriptions of the environment as background information and detailed descriptions where needed to support analysis of potential environmental l impacts of operation during the renewal term discussed in Chapter 4. Subsection 2.2.9 describes the historic and archaeological resources in the area, and 2.2.10 describes possible cumulative effects of the proposed action and other Federal project activities. October 1999 2-18 NUREG-1437, Supplement 1 l I
- J
Plant and ths Environment 2.2.1 Land Use CCNPP is located in a sparsely populated area that is undergoing population growth. The major portion of the land surrounding the site is devoted to agricultural and forest uses. While declining, the amount ofland being farmed should continue to be substantial. Land devoted to residential and commercial use will increase as the population grows. The land occupied by the CCNPP is zoned 1-1 light industrial by Calvert County. Power generating facilities are a permitted use in 1-1 zoning districts (Calvert County 1997a). l Tha amount of land devoted to various land uses in Calvert County in 1993 is shown in Table 2-2. The region surrounding the CCNPP site is predominately rural in character. However, since 1970, open spice in Calvert County has been converted to residential use at an average rate of nearly 400 ha ' (1000 acres) per year. The amount of farmland in the County declined from approximately 25,000 ha (63,000 acres) in 1970 to approximately 15,000 ha (37,000 acres) in 1992. Commercial, industrial,
-institutional, and utility development accounts for less than 5 percent of land use in the County.
The Coastal Zone Management Act (CZMA) requires that applicants for a Federal license to conduct an l tctivity in the coastal zone shall provide in the application to the licensing agency a certification that the proposed activity complies with the enforceable policies of the State's approved Coastal Zone M nagement Program and that the activity will be conducted in a manner consistent with the program l [33 USC i456(c)(3)(A) CZMA). l The MDE determined that renewal of the operating licenses for CCNPP is consistent with the Maryland Co:stal Zone Management Program established under the CZMA (MDE 1998). l Table 2-2. Land Use in Calvert County in 1993 (Calvert County 1994a) l Land Use Hectares (Acres) % of Total farms and forests 35,400 '(87,400) 62 parks and open space 1710 (4230)_ 3 institutions and utilities 1710 (4230) 3 residential 17,100 (42,300) 30 commercial 570. (1410) 1 industrial 570 (1410) 1 Total 57,000 (141,000) 100 NUREG-1437, Supplement 1 2-19 October 1999
Plant end ths Environm:nt 2.2.2 Water Use Cooling water withdrawal from the Chesapeake Bay and groundwater withdrawal for other plant uses, as described previously in Subsection 2.1.3, are regulated by the State of Maryland. CCNPP uses a once-through heat dissipation system that withdraws from and discharges cooling water to the Chesapeake Bay. Water for plant service, make-up, and domestic uses is withdrawn from five groundwater wells tapping into the Aquia Aquifer. The MDE requires BGE to monitor and report withdrawals from the five l production wells. Average daily withdrawal rates for the period of July 1996 to June 1998 was 1.89x10 2 l m'/s (392,000 gpd) (BGE 1998b). The current State permit limit for groundwater withdrawals is l 2.17x102 m /s (450,000 gpd). 2.2.3 Water Quality l Pursuant to the Federal Water Pollution Control Act (FWPCA) (33 USC 1251), also known as the Clean l Water Act (CWA), the water quality of plant effluent discharges is regulated through the National l Pollutant Discharge Elimination System (NPDES). The MDE is the State of Maryland agency delegated by the EPA to issue the NPDES discharge permit. The current permit (State Discharge Permit l 92-DP-0187) was issued on June 16,1994, and was scheduled for renewal on June 15,1999. BGE l submitted a timely application for permit renewal and continues to operate within the provisions of the l old permit while awaiting issuance of a new permit. The MDE stated that it is unaware of any major issue likely to prevent renewal of this permit. Any new regulations promulgated by EPA or the MDE would be included in future permits and may include development and implementation of Total Maximum Daily Loads. 2.2.4 Air Quality The Chesapeake Bay and the Atlantic Ocean farther to the east generally give the CCNPP site mild winters and summers. Climatological statistics for Baltimore are generally representative of the climate of the site. According to the National Oceanic and Atmospheric Administration, typical January daily temperatures range from a minimum of-4.8*C (23.4*F) to a maximum of 4.6*C (40.2*F). July temperatures typically range from a minimum of 19.3*C (66.8*F) to a maximum of 30.7*C (87.2*F). The record minimum and maximum temperatures are -22*C (-7*F) and 41 *C (105"F), respectively. Typical morning relative humidities range from a low of about 70 percent in the winter to a high of about 85 percent in the early fall. Aftemoon relative humidities are generally about 55 percent. The annual average precipitation is about 104 cm (41 in) and is evenly distributed throughout the year. About one-third of the days have October 1999 2-20 NUREG-1437, Supplement 1 1
Plant and the Environment pracipit4 tion totaling 0.03 cm (0.01 in) or more. Winter precipitation is generally associated with synoptic weather systems. The average snowfall is about 51 cm/yr (20 inlyr). Summer precipitation l t:nds to be associated with thunderstorms. During the summer, the region is generally under the influence of the Bermuda high-pressure system. High-pressure systems are typically associated with low winds and increased potential for air quality problems. Air quality in 1997 in Calvert County was generally rated as moderate using the EPA
- Pollution Standards Index (that is an indicator of community-wide air quality). A moderate rating means thit there should be few or no health effects for the general population. The primary pollutant contributing to the moderate rating was ozone. Ozone is not emitted directly; it is the product of chemical reaction that involves volatile organic compounds (VOCs) and nitrogen oxides (NO,). There l appears to have been a gradual decrease in emissions of VOCs and NO,in Calvert County during the l
. list 10 years (EPA 1999). Cdvert County is within the Washington, D.C., " serious" nonattainment area for ozone (40 CFR 81.321). However, the ozone air quality monitor in Calvert County did not record any exceedences of the National Ambient Air Quality Standard for ozone in 1996,1997, or 1998. To the wast of Calvert County, Prince Georges and Charles counties are also included in the Washington, D.C., nonattainment area. The EPA ozone standard was exceeded at monitors in each of these counties in 1997 and earlier years. To the north of Calvert County, Anne Arundel County is in the Baltimore " severe" nonattainment area for ozone (40 CFR 81.321). The EPA ozone standard has been exceeded in Anne Arundel County each year since 1993. The ozone monitors in Prince Georges and Anne Arundel counties are located generally in the corridor between Washington, D.C., and Baltimore rather than in the ' portions of the counties neerast the Calvert Cliffs site. St. Mary's County south ' Crivert County and the counties across Chesqv ae Bay to the east are designated
" Unclassifiable / Attainment" areas for ozone (40 CFR 81.321).
The State of Maryland has adopted a State implementation Plan for that portion of Maryland that is within the boundaries of the Washington, D.C., " serious" nonattainment area for ozone. This plan, l which is based upon a plan developed by the Metropolitan Washington Council of Govemments, has been approved by the EPA (62 FR 49611). Recent revisions to the plan to achieve an additional percent reduction in emissions of VOCs using reasonably available control technology (RACT) have l also been approved by EPA (63 FR 36578). The CCNPP emergency diesel generators (EDGs) are considered major sources of both VOCs and NO, because of their potential annual release rates (BGE 1998). Permits have been obtained from the MDE for the EDGs.
- Cdvert County is classified as "Better than National Standards" or " Unclassifiable / Attainment" for the r:maining criteria pollutants (40 CFR 81.321). The counties surrounding Calvert County have similar d:eignations for the remaining criteria pollutants except for Anne Arundel County, which does not meet secondary standards for total suspended particulates (40 CFR 81.321). CCNPP is more than 100 km l NUREG-1437, Supplement 1 2-21 October 1999
l u. PI:nt and the Environm nt - l .(62 mi) from the nearest Class I area for the Prevention of Significant Deterioration of Air Quality l designated in the Clean Air Act (CAA) (42 USC 7401).
.2.2.5 Aquatic' Resources
- l The area of the Chesapeake Bay in the vicinity of the CCNPP is used for a variety of purposes,
- including navigation, recreation, and commercial fisheries. - Boating and sportfishing are popular. The Bay supports a variety of aquatic species typical of a warm-water partially mixed estuary, including phytoplankton, zooplankton, epibenthic, intertidal, and subtidal communities, as well as commercially and recreationally important finfish and ' shellfish. .Three representative important species (RIS) identified by the State of Maryland include the eastem oyster, Crassostrea virginica, the soft shell clam, Mya arenaria, and the blue crab, Callinectes sapidus. Oyster breeding and nursery areas occur near the plant, and new beds were created during plant construction to mitigate habitat loss (Abbe 1988, 1992). Softshell clams are also present in the intertidal areas surrounding the plant, but have not l occurred in sufficient number for commercial fishery since at least before 1971 (Heck 1987).
Blue crab are often caught by commercial and recreational fishers and represent a sizable proportion of the fishing industry. . Although mating occurs in the areas near CCNPP, the females typically migrate down-Bay to a spawning and hatching area approximately 110 km (70 mi) south of CCNPP, where an appropriate salinity of approximately 23 to 28 parts per thousand occurs (Sandoz and Rogers 1944). Other recreationally and commercially important species are presented in Table 2-3, in approximate order of abundance. The finfish presented in this table commonly occur in the vicinity of the CCNPP and spend at least part of their life cycle in these waters. 1 l Two Federally protected species, the shortnose sturgeon and the Atlantic loggerhead turtle, are known { to occur in the vicinity of CCNPP. These are also protected under State of Maryland laws. The general
-l location and habitat of these species are shown in Table 2-4. BGE researchers caught one shortnose l sturgeon during trawl studies in the vicinity of the CCNPP in 1979 (Heck 1987). However, dam l: construction has constrained the distribution of most shortnose sturgeon populations to deepwater -l pools from summer through winter. Adults move upstream to spawn during the spring. The ancestral range of this species is believed to extend from the St. John River in New Brunswick, Canada, to the St.
Johns River in Florida. Most populations are considered anadromous, with adults typically living in the ocean and entering freshwater systems to spawn. l Freshwater resources associated with CCNPP include approximately 80 ha (200 acres) of marshlands l (AEC 1973), a small man-made wetland created as a mitigation project, several ponds in the vicinity of
- Camp Conoy, and several small interior streams. The Maryland Natural Heritage Program lists species that are rare-to-uncommon in Maryland (occurrences typically in the range of 21 to 100) as S3 species,
.although they are not active!y tracked by the Heritage & Biodiversity Conservation Programs. A State-
' l ranked S3 aquatic plant species, the humped bladderwort, Utricularia gibba, is found in the littoral zone of a Camp Conoy pond. J j
October 1999 2-22 NUREG-1437, Supplement 1
Plant and th:n Environm:nt 2.2.6 Terrestrial Resources The CCNPP and its associated transmission corridors lie within the oak-pine-hickory association of the l castem deciduous forest (Greller 1988). These mature forested habitat spp. are dominated by oaks, l Qu:rcus spp. and hickory, Carya spp., as the successional dominants, along with several species of l pine, Pinus spp. In 1998, BGE conducted a survey of the natural plant communities at the site and within its associated transmission corridors. These habitats include eight plant community types: agricultural land, managed rights-of-way, chestnut oak association, forested wetlands, open water and emergent wetit,ds, Virginia pine association, tulip poplar /sweetgum association, and old fields. The latter includes all disturbed crets without an actively managed vegetation cover. Table 2-3. Recreationally or Commercially important Aquatic Species Near CCNPP in Order l of Abundance l Scientific Name Common Name Callinectes sapidus blue crab Mya arenaria soft shell clam Crassostrea virginica eastem oyster Leiostomus xanthurus spot Anchoa mitchilli bay anchovy Micropogonias undulatus croaker Morone americana white perch Pseudopleuronectes americanus winter flounder Trinectes maculatus hogchoker Brevoortia tyrannus Atlantic menhaden Morone saxitilis striped bass Bairdiella chrysura silver perch Microgadus tomcod Atlantic tomcod Alosa pseudoharengus alewife Clupea harengus Atlantic herring l Alosa aestivalis blueback herring Source: Heck (1987). l NUREG-1437, Supplement 1 23 October 1999
Plant and tha Environm:nt Table 2-4. Protected and *Watchedi Aquatic Species on and in the Vicinity of the CCNPP Site Federal Location and Species Common Name Status State Status Habitat Acipenser shortnose Endangered S1 (highly rare) Nearshore brevirostrum sturgeon environment in Chesapeake Bay Caretta caretta Atlantic Threatened S1 (highly rare) Chesapeake Bay loggerhead turtle l Utricularia gibba humped .None S3 (Watch List) Littoral zone of Camp bladderwort Conoy Pond l Source: Derived from FWS (1998) and NMFS (1998) and The Natural Heritage Network (1999).
] Virginia pine, Pinus virginiana, is common on power line rights-of-way. Other trees include chestnut oak, Quercus prinus, black gum, Nyssa sylvatica, sweetgum, Liquidambar styraciflua, tulip poplar, Liriodendron tulipifera, sassafras, Sassafras albidum, and American beech, Fagus grandifolia. The 'l understory includes a variety of herbs and shrubs, including rhododendron, Rhododendron spp.
l In 1985 and 1987, BGE foresters developed Forest Resource Management Plans for the CCNPP area l in consultation with the Maryland Department of Natural Resources. These plans emphasize presentation and maintenance of mature hardwood stands and removal of Virginia pine for disease and fire control. BGE maintains a system of fire roads and fire-fighting tool caches throughout the CCNPP site, Non-forested, non-industrial habitats include maintained lawns and agricultural fields (com, wheat, and hay), and disturbed successional habitat. Agriculture has been practiced on the CCNPP site for over 200 years, and BGE retains a forester / land manager to oversee crop production and forest management. BGE continues to preserve those portions of the forest that were not disturbed by construction. Mammalian fauna of the site and rights-of-way include white-tailed deer, Odocoileus virginianus, raccoons, Procyon lotor, red and grey fox, Vulpes fulva and Urocyon cinereoargenteus, eastem gray and fox squirrels, Sciurus carolinensis and niger, eastern chipmunk, Tamias striatus, and a variety of mice and voles. White-tailed deer are the most important game mammal, with eastem cottontail rabbits, Sylvilagus floridanus, of secondary importance. Northern bobwhite, Colinus virginianus, and wild turkey, Meleagris gallopavo, are the most important game birds in the site vicinity. Bobwhites are associated with the agricultural fields and forest edges, October 1999 2-24 NUREG-1437, Supplement 1
PI:nt and tha Environm:nt I while turkeys use the forested habitats, rights-of-way, and old fields. The open water and emergent wetland habitat sup vts a number of migrant waterfowl, and osprey, Pandion haliaetus, use the forested areas near the Chesapeake Bay shoreline. As part of its Forest Resource Management Plans, BGE uses late summer mowing to maintain roads cnd log loading decks as wildlife food plots and wild turkey brooding habitat. In 1987, the State of M:ryland developed a Wildlife Management Plan for the CCNPP site, stressing management of woodlands for wild turkey, and management of fields, road edges, and rights-of-way for wild turkey, bobwhite quail, and eastern cottontail rabbits. BGE updated this plan in 1993 to include additional h:bitat enhancement projectF, li,Jdng a Tiger Beetle Habitat Protection Area operated under a conservation agreement %n The Nature Conservancy, an informative nature trail, osprey nesting anc monitoring program, bluebird nest box program, and a wild turkey stocking reservoir. This update also provided for a Calvert Cliffs Wildlife Habitat Committee. Three Federally protected terrestrial animal species are known to occur on the CCNPP site and l rights-of-way. The generallocation and habitat of these species are shown in Tpble 2-5. These species are niso protected under State of Maryland laws. Two species of concern to the Maryland l NLtural Heritage Program have been identified on the CCNPP site. These are the spurred-butterfly l pel Centrosema virginianum, a State rare species and the pink milkwort, Polygala incamata, a State l w:tch list species. State rare species are considered to be imperiled in Maryland because of rarity, and l w;tch list species are considered rare to uncommon, but otherwise have no specific protection. Older l records suggest that one State endangered species, the blunt-leaved Gerardia, Agalinis obtusifolia, j might exist on the CCNPP site in appropriate habitats. In 1997, BGE initiated consultation with the U.S. l Fish and WildFfe Service (FWS) and the National Marine Fisheries Service (NMFS) under Section 7 of the Endangered Species Act. FWS concurred with the listing BGE provided of threatened or l cndangered species. 2.2.7 Radiologicalimpacts Since 1970, BGE has conducted a radiological environmental monitoring program (REMP) around CCNPP. The radiological impacts to workers, the public, and the environment have been carefully monitored, documented, and compared to the appropriate standards. The purposes of the REMP are to e verify that radioactive materials and ambient radiation levels attributable to plant operation are within the limits contained in the ODCM and the Environmental Radiation Protection standards as stated in 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations NUREG-1437, Supplement 1 2-25 October 1999
Pitnt end the Environm:nt Table 2-5. Protected and " Watched" Terrestrial Species on CCNPP Site and Rights-of-Way Common Federal Species Name Status State Status Location an{ Habitat Cicindella Puritan tiger Threatened Endangered Beach area at base of cliffs puritana beetle Cicindela northeastem Threatened Endangered Beach area at base of cliffs dorsalis dorsalis beach tiger beetle Haliaeetus bald eagle Threatened Endangered Active nest in the vicinity of leucocephalus Camp Conoy; 7 offspring fledged since 1986 Centrosema spurred None Rare Along a fire road south of virginianum butterflypea- St. John's Creek l Polygala pink milkwort None Watch List Along old field community incamata roaoways l Source: Derived from BGE (1998a) and MDNR (1999).
. detert any measurable buildup of long-lived radienuclides in the environment
- monitor and evaluate ambient radiation levels
. determine whether any statistically significant increase occurs in the concentration of radionuclides in important pathways.
These releases are summarized in the annual reports titled " Radiological Environmental Monitoring Program Annual Report" and the annual Effluent Release Reports. The limits for all radiological releases are specified in the ODCM, and these limits are designed to meet Federal standards and requirements. The REMP includes monitoring of the aquatic environment (Bay water, aquatic organisrns, shoreline sediment), atmospheric environment (air particulates and iodine), terrestrial environment including vegetEtion, and direct radiation. A separate radiological environmental monitoring program is in place for the Independent Spent Fuel Storage Installation, which is covered by a separate license. I Review of historical data on releases and the resultant dose calculations revealed that the doses to maximally exposed individuals in the vicinity of CCNPP were fractions of the limits specified in the October 1999 2-26 NUREG-1437, Supplement 1
I Plant and th3 Environm:nt Environmental Protection Agency's environmental radiation standards 40 CFR Part 190 as required by l 10 CFR 20.1301(d). For 1997, dose calculations were performed using the plant effluent release data, onsite meteorological data, and appropriate pathways identified in the ODCM. The summary results for doses to the maximally exposed individual in 1997, which are representative of the doses from the past 5 y:ars, are given below (BGE 1998b). l A r view of whole body and organ doses revealed the following results:
. The maximum thyroid dose to a hypothetical child 1.9 km (1.2 mi) WSW of Calvert Cliffs was l 0.00005 mSv/yr (0.005 mrem /yr) via liquid and gaseous pathways. This is <0.01 percent of the 0.75 ,
mSv/yr (75 mrem /yr) limit specified in 40 CFR Part 190.
. The maximum whole body gamma dose to a hypothetical child 1.4 km (0.8 mi) WSW of Calvert l Cliffs was 0.00009 mSv/yr (0.009 mrem /yr) via liquid and gaseous pathways. This is <0.01 percent of the 0.25 mSv/yr (25 mrem /yr) limit in 40 CFR Part 190. . The maximum calculated dose to all other organs (GI-tract) was 0.0024 mSv/yr (0.24 mrem /yr) at 1.4 km (.8 mi) WSW of Calvert Cliffs. Compared to the 0.25 mSv/yr (25 mrem /yr) limit in 40 CFR Part 190, this is about 1 percent of the limit.
Th3 applicant does not anticipate any significant changes to the radioactive effluent releases or l exposures from CCNPP operations during the renewal period and, therefore, the impacts to the cnvironment are not expected to change. 2.2.8 Socioeconomic Factors Tha staff reviewed the applicant's environmental report, information available in publications from the St te of Maryland, the U.S. Bureau of the Census of the U.S. Department of Commerce (DOC), and l planning and economic development bodies in Calvert, St. Mary's, and Charles Counties. Several county staff members, local real estate agents / appraisers, and social services providers were int:rviewed during a July 1998 site visit. The following information describes the economy, population, l cnd communities near CCNPP. 2.2.8.1 Housing Between 1970 and 1990, total housing units in Calvert County increased from 7932 to 18,974 (Tri-County Council for Southem Maryland 1993). Growth has continued since 1990 at a rapid rate. Approximately 10 percent of the increase may be attributed to the 909 CCNPP employees who live in l C:lvert County (as of October 1998). As of July 1998,256 CCNPP ernployees live in St. Mary's County NUREG-1437, Supplement 1 2-27 October 1999
PI:nt tnd the Environrr t,t I and 46 live in Charles County (Table 2-6). Based on the Maryland total employment multiplier (*) l (3.9997) (DOC 1992a), CCNPP may have accounted for 4200 direct and indirect jobs and 40 percent of the housing growth from 1970 to 1990. Between 1980 and 1990, the number of housing urits in the Tri-County (Calvert, St. Mary's, and Charles) area increased approximately 43 percent to a total of 81,320 units. l Since 1990, the Calvert County resident population has increased from 51,372 at the 1990 Census to l 64,000 in 1995 and about 72,000 in 1998 (Table 2-7). St. Mary's County increased in populanon from l about 76,000 in 1990 to almost 88,000 in 1998. About 6600 housing units were added to the Calvert County housing stock between 1990 and 1996, as the north end of the county became a more popular bedroom community for Washington, D.C., and the Patuxent River Naval Air Station in St. Mary's County added 5200 civilian and military jobs. St. Mary's County added 5100 housing units over the same 1990-1996 period, while Charles County added 6800 units. Housing availability in the Tri-County area is not limited by growth-control measures, although multifamily housing is effectively limited to a handful of town growth centers by water and sewage issues. With a vacancy rate of approximately 7 percent, over 5700 units are available for occupancy (Tri-County Council for Southem Maryland 1993). 2.2.8.2 Public Services Water Supply Fresh water used in Calvert County comes from subsurface sources and is used primarily for domestic and agricultural uses. The county has 22 privately owned residential community water systems, 17 municipally owned water systems, and 24 systems owned by corporations or institutions. Some nearby water systems in St. Mary's County draw from and compete with systems in Calvert County. Table 2-8 shows output of selected water supply systems in communities near CCNPP, as well as the estimated population served by each in 1994-1995; Figure 2-8 shows their locations. The normal output of these systems is small, but incree.as substantially in the summer to accommodate seasonal l increases in population. I in Southem Maryland, the majority of the public water supply is drawn from the Aquia Aquifer (Figure 2-9). There are some water supply systems starting to experience supply problems in the southem portion of the Tri-County area, especially in the Solomons Island and Lexington Park areas. These systems both draw water from the Aquia Aquifer with an average daily output of 9.8 Us l (a) A total employment multiplier is the ratio between total employment associated with an activity and the numt er of persons directly employed. The ratio is alv ays greater than 1.0 because an economic activity generates employment in related businesses and in the general economy as diret.t payroll dollars are spent. ; October 1999 2-28 NUREG-1437, Supplement 1 i
F Plant and ths Environm:nt (225,000 gpd) and 52.7 Us (1,203,000 gpd), respectively. As a result of this large demand, the pot:;ntiometric surface in this area has dropped more than 9 m (30 ft) in the last 10 years. However, there is 90 m (300 ft) of available drawdown still remaining (MDNR 1993) without exceeding regulatory l , limits. ! 1 Education I In 1990, there were approximately 38,900 students enrolled in schools in the Tri-County area (Tri-County Council for Southem Maryland 1993). By 1997, the enrollment totals for the public schools Table 2-6. Geographical Distribution of the Residences of CCNPP Employees, October 1998 l Number of Place of Residence Empicyees Calvert County 909 i St. Mary's County 256 Anne Arundel County 53 Charles County 46 Prince George's County 23 Baltimore County 7 Baltimore City 4 Carroll County 2 Harford 2 Howard 1 Montgomery County 1 Queen Anne's County 1 Out of State 4 Total, BGE Only 1309 Total, Contractor (geographical distribution 240 believed to be similar) Total 1549 Source: BGE (1998c). l NUREG-1437, Supplement 1 2-29 October 1999
. Pirnt and ths Environmtnt i 4 . Table 2 ~. Population Growth in the Calvert, St. Mary's, and Charles County, Maryland l (1970-1995) Calvert County St. Mary's County Charles County ) Annual Annual Annual Year Population Growth % ' Population Growth % Population Growth % 1970 20,682 - 47,388 - 47,678 - 1980 34,638' 5.3 59,895 2.4 72,751 4.3 1990 .51,372 4.0 75,974 2.4 101,154- 3.4 l 1995' 64,359 4.6 80,783 1.2 111,320 1.9 l 1998 71,877 3.8 87,670 2.8 117,963 2.0 l Sources: Maryland Office of Planning,1998a,1998b,1998c,1999. had increased to 14,480 in Calvert County, 21,000 in Charles County, and 14,220 in St. Mary's County, for a total of 49,700. In Charles County, there are 18 public elementary,6 middle / combined schools, 5 high schools, and 17 private schools.. St. Mary's County has 16 public elementary schools,4 middle schools,3 high schools, and 8 private schools. Calvert County has 11 public elementary schools, 4 middle schools,3 high schools, and 10 private schools. Each county has some post-secondary institutions. A branch of the Charles Community College is located in Calvert County, and the Calvert Career Center is located in Prince Frederick. Off-campus courses from the George Washington University and University of Maryland are offered in Charles County, the Charles Community College (enrollment of 6100) is located in La Plata, and the Career and Technology Center is located in Pomfret. A branch of Charles Community College, and the Soutnem Maryland Higher Education Center, which provides distance leaming through several universities, :are located in St. Mary's County; St. Mary's College of Maryland (enrollment of 1650) is also located in St. Mary's County in St. Mary's City. Calvert County has comparatively low student-teacher ratios, despite having relatively low property taxes. For 1996-1997, student / staff ratios were 15.9 in Calvert County,13.8 in St. Mary's County, and 15.2 in Charles County. Property tax rates in fiscal year 1998 were $2.23/$1000 in Calvert County,
$2.08/$1000 in St. Mary's County, and $2.44/$1000 in Charles County Given the rapid growth in Calvert County, enrollment is expected to reach 17,000 by the year 2000. Consequently, the fiscal year 1998 capital improvement budget includes several construction projects that are under way, including the construction of two new schools (Windy Hill and South Central) before 2000. St. Mary's County is meeting its needs by renovating and expanding existing schools rather than building new ones. As of July 1998, additions to Chopticon and Leonardtown High Schools, Esperanza Middle School, and Lexington Park, Banneker, and Leonardtown Elernentary Schools were underway, with additions to Margaret Brent Middle School in the planning phase.
October 1999 2-30 NUREG-1437, Supplement 1
l t Plant and the Environmsnt Table 2-8. Projected Pumpages by Sanitary District / Planning Area from the Aquia and Piney Point-Nanjemoy Aquifers Based on St. Mary's and Calvert Counties' Population Growth Estimates 1995 2020 Pumpage (1000 gpd)* Pumpage (1000 gpd)* Total (Aquia Sanitary and Piney Piney Point- Total (Aquia and Piney Point- I District Population Point) Aquia Nanjemo Population Piney Point) Aquia Nanjemo , ST. MARY'S COUNTY I Luckland Run 8788 607 567 40 12,176 1047 997 50 Dukchart's 6017 277.2 237.2 40 7047 354.2 305.2 49 l Creek Leonardtown 10.532 598 558 40 13.589 724.6 674.6 50 Flood Creek 2070 198.5 89.5 109 2835 266.1 113.1 135 Piney Point 4008 369.1 149.1 220 5787 463.3 190.3 273 lika Conoy 1176 444 0 444 1448 551 0 551 ; Cirroll Pond 3529 722 112 610 4347 923.8 141.8 782 Pine Hill Run 37,639 4398.3 2541.1 1857.2 50,183 5702 3328.5 2373.5 Minor Run 4032 135 95 40 5508 175 125 50 indiin Creek 8235 422.1 382.1 40 12,419 647.9 597.9 50 Tot;l 86,026 8171.2 4731.0 3440.2 115,339 10,854.9 6491.4 4363.5 l (12,973.2) (8663.9) (4309.3) CALVERT COUNTY Plinning 20,870 2256.4 1230 1026.4 39,738 4196.5 2403.7 1792.8 Ar:s1 PIInning 15.331 1114.3 808.4 305.9 29,572 1864.6 1357.8 506.5 Artz 2 Plinning 28,197 2325.1 1619.1 706 53,690 3844.5 2662.5 1182 Arsa3 Total 64,598 5695.8 3657.5 2038.3 123,000 9905.3 6424.0 3481.3 (11,114) (1655.7) (3458.3) (t) 1000 gpd - 0.044 Us. Source: Achmed and Hansen (1997). NUREG-1437, Supplement 1 2-31 October 1999
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PI:nt cnd tha Environm:nt Transportation
^ Ivert County has one main four-lane road (Maryland State Highway 2-4) bisecting the County north to l somh, with smaller roads running to the water bodies on each side of the peninsula (Figure 2-2.) Very I I
few of the secondary roads connect with each other; therefore, Highway 2-4 services the bulk of the traffic for the length of the County. The highway runs adjacent to the CCNPP site and provides the only l access to the site. The highway is considered to meet Service Level D (high density, stable flow in l which speed and freedom to maneuver are restricted-see GEIS Section 3.7.4.2); population growth in j the county is expected to increase crowded conditions on the road, particularly at selected intersections l (Calvert County 1997b). Splitting from Highway 2 at Solomons Island, Highway 4 connects the southem end of Calvert County via the Thomas Johnson Bridge with Maryland State Highways 5 and 235 in St. Mary's County. Highways 5 and 235 run the length of St. Mary's County from north to south. Highway 235 serves all of the main gates to the Patuxent River Naval Air Station. Highway 2-4 serves as a commuting route from Calvert County to the Patuxent River Naval Air Station. As a consequence of the rapid growth of the station, traffic tie ups at the intersection of Highway 4 and Highway 235 during the moming rush hour can create a backup to the bridge, a distance of about 6 km (4 mi). There are plans to mitigate the bottleneck at this intersection and perform other traffic upgrades in St. Mary's County to accommodate the new population. Several of the secondary highways in Calvert County along Highway 2-4 (such as Highway 760 from Drum Point to Highway 2-4 at the south end of the county) are also becoming crowded due to population growth and may require additional traffic control measures. 1 The period from 1998 to 2020 has been projected by the State of Maryland to be one of rapid population growth. Calvert County is projected to be the fastest growing county in the State over that period. At the projected growth rate, the County would approximately double its current population by l the end of the license renewal period (Calvert County 1994a). Upgrading most arterial links and mLn highways is likely to be required to accommodate such growth. The Calvert County Planning l Commission (Calvert County 1997b) has identified costs of $130 million in improvements to maintain adequate service on Highway 2-4 through the year 2030. 2.2.8.3 Offsite Land Use l Figure 2-2 shows the CCNPP location, general land use, and plannee uses for land in Calvert County, respectively. While land use in the Tri-County area would be influenced to some degree by changes at CCNPP, this section concentrates on Calvert County because the bulk of residential and commercial development related to the plant workforce is ',ntained in Calvert County and because the largest share of the CCNPP tax base exists in Calvert County. Spending of CCNPP-related taxes can also affect economic development and land use. The region around OCNPP remains predominantly rural in character, with 32 percent of Calvert County in farms and forests and only 2 percent commercial or industrial (see Table 2-2). Hawever, with October 1999 2-34 NURM-1437, Supplement 1 f , 1 l
l Plant and the Environment population growth,8.3 percent of the County's agricultural land was lost to residential and commercial development between 1985 and 1990, as well as 6.8 percent of the County's forested land (Calvert County 1997b). This continued a trend evident since 1970, which has shown a rate of conversion from open space to residential use of about 400 ha (1000. acres) a year. Farmland declined from 25,000 ha (63,000 acres) in 1969 to 15,000 ha (37,000 acres) in 1992 (Calvert County 1988; DOC 1992b). l l Since the 1970s, the State of Maryland has allowed Transferable Development Rights (TDRs), where land owners can sell their development rights on the open market. Both the State and the County have been active in purchasing and retiring TDRs to preserve agricultural land and resource preservation arcas. The tax base provided by CCNPP was a significant factor in the County's ability to do this. C:lvert County's planning efforts over the last 30 years have been focused on directing growth to suitable locations, promoting selected types of economic growth, and practicing stewardship of the land i and Chesapeake Bay. Calvert County has adopted a Comprehensive Plan (Calvert County 1997b) and s:,veralland preservation and open space plans to preserve the rural character of the County. These plins include large-lot zoning and the Calvert County Agricultural Preservation Program. The implementation strategy contains four steps: (1) Reduce total build-out. In 1995, there were 23,500 dwelling units in the County with a theoretical
- build-out" capacity of around 50,000 dwellings (Table 2-9).
- Build-out" means the total number of dwellings that could be built in the county under cun'ent zoning.
(2) Reduce residential growth rate, which has averaged around 5 percent per year for the last 20 years. (3) Preserve prime farms, forests, historic resources, and sensitive areas. These areas comprise approximately 22,000 ha (54,000 acres). By 1997, about 4900 ha (12,000 acres) of prime farm and forest land had been permanently preserved by the County and an additional 3000 ha (7500 acres) were enrolled in either the State or the County Agricultural Preservation Program (Calvert County l 1997b). l (4) Direct growth to appropriate locations. The 1983 Comprehensive Plan called for creation of Town Centers to avoid scattered strip development along Highway 2-4, to promote business growth by encouraging agglomeration economies, to zone and provide infrastructure for multifamily development (including low-income and elderly housing), to reduce dependence on vehicles, and to reduce growth within agricultural areas (Calvert County 1997b). l By 1997, virtually all new commercial development had been directed to Town Centers in Calvert County. General merchandise sales and commercial real property had grown by over 100 percent and both low-income and elderly housing had been built in Town Centers, which also were attracting high and middle-income families. The 1997 Comprehensive Plan (Calvert County 1997b) continues and expands upon these themes. However, new residential development in the County has been in rural areas on large lots (the County requires a minimum lot size of 5 acres in rural areas); approximately NUREG-1437, Supplement 1 2-35 October 1999
PI:nt end ths Environment 7300 pla'ted, undeveloped lots remain exempt from most current regulations. Approximately 530 ha (1300 acres) of undeveloped land outside of existing residential communities are zoned R-1 (single-family residential) or R-2 (multifamily residential) and need to be reevaluated. Several other land use controls in the County limit either total development or help steer development toward appropriate locations. In 1988, tile County adopted adequate facilities regulations to ensure that roads and schools could accommodate new growth. In the early 1990s, this ordinance effectively stopped the approval of most new subdivisions until schools could be built. Impact fees are also charged for new construction, including a $350/ year / unit for landfill impact, 5600/ unit recreation fee, Table 2-9. Projected Build-Out in Calvert County Under 1995 Zoning Additional Total Build-Additional Acres Needed Out Under Zoning Dwelling Units Dwelling Units for Current Category as of 1995 Permitted Development Zoning BaseN TDRM Total 2700 12% 5000 +1000 6000 0 8700 17 % 6 00 a s
** " 0 17,500 34 %
8500 36 % 9000 9000 g Resource Preservation District and Farm 4000* 17 % 9800 -2800 7000 7500 11,000 21 % Community District 34,000 acres Rural Community District 83005 35% 4500 +1800 6300 7000 14,600 28% 47,000 acres Total 23,500* 100% 28,300 28,300 14,500 51,800 100 % (a) Base number of dwelling units permitted. (b) Number of additional units that need to be transferred in order to meet the county's goal of preserving 20,000 acres of prime farm and forest land through the Calvert County Agricultural Preservation Program. (c) Includes 1200 platted undevelcped lots. (d) includes 2400 platted undevelciped lots. (e) Includes 3600 platted undevelc' ped lots. Source: Calvert County 1997b. October 1999 2-36 NUREG-1437, Supplement 1
i l Piant and the Environment I i and a schoolimpact fee of $3000/ unit for single-family detached housing or $2000/ unit for single-family ctt:ched housing. In 1989, the State mandated the establishment of Critical Areas within 305 m (1000 ft) of the County's waterways. Allowable densities in most of this area were reduced to 8.1 ha (20 acr:s) per dwelling unit. The Maryland Forest Con Iervation Act, adopted in 1993, helped protect large l contiguous forested areas. In 1992, the County acepted mandatory clustering together with the d:signation of three sub-zoning categories: (1) Farm Communities, (2) Resource Protection Districts, end (3) Rural Communities. The provis,on required that lots be clustered onto 50 percent of any given p;rcel within a Rural Community and onto 20 percent of the parcel in the other two types. Design st ndards were adopted to protect fields, forestt., and vistas. Finally, in 1993, a new zoning category criled " Employment District" was defined to designate non-retail uses. These uses were required to be cdjacent to Town Centers to avoid commercial sprawl. 2.2.8.4 Visual Aesthetics and Noise
]
From the air, the principal visual features of the CCNPP region are the Chesapeake Bay, the Patuxent River, and the countryside, which is generally wooded. The distance across the Bay in the vicinity of CCNPP is approximately 10 km (6 mi) and the far shore is a dark line on the horizon; the view up- or down-Bay is water to the horizon. From the Bay, the shoreline is wooded with widely spaced small housing developments and marinas. The CCNPP site has a 460-m (1500-ft) wide developed area approximately in the middle of 10 km (6 mi) of undeveloped, wooded shoreline featuring 30-m (100-ft) cliffs. These scenic resources have remained unchanged since CCNPP construction. ) Offsite scenic resources inland have changed since CCNPP construction due to population growth. This growth has resulted in housing, commercial, and roadside development supplanting agricultural cnd wooded areas. However, Maryland Highway 2-4 is a State scenic highway, affording views of g:ntly rolling, wooded countryside with interspersed development and occasional agricultural lands. CCNPP is not visible from Maryland Highway 2-4 due to intervening wcods and topography. B:cause of setback, woods, and topography, noise from the CCNPP is generally not an issue. The only sounds heard offsite are the plant loudspeakers, which can be heard nearby on the Bay, gunfire from the onsite firing range used by the guards for target practice, and public notification systems for emergencies that are tested periodically. Planting extra trees along the southern boundary of the firing range has mitigated firing range noise and has reduced noise complaints to almost zero. 2 2.8.5 Demography Th3 Fina'l Environmental Statement (FES), Section ll.C (AEC 1973), estimated resident population l within 80 km (50 mi) of CCNPP for the years 1970 ad eul0. As discussed in Section 3.8.2 of the FES, th3 projection for the year 2010 was 20 percent Ng:::r than the current estimate and is approximately th3 same as the current estimate for the end of the license renewal period. NUREG-1437, Supplement 1 2-37 October 1999 m
Pl:nt cnd ths Environm:nt l Sections 3.8.1 and 3.8.2 of the applicant's ER presented U.S. Cen:;us data for 1990 and estimated l resident population for each decade through the proposed CCNPP license renewal term (2010,2020, 2030, and 2040). The 2010 projections represent estimated population near the start of the renewal period for Unit 1 (2014), and the projections for the year 2040 represent populations near the end of the initial renewal term (2036 for Unit 2). Data for 1990 are based on the 1990 Census of Population (DOC 1991). Projections are based on County population projections provided by State planning agencies in Delaware (Delaware Development Office 1995), Maryland (Maryland Office of Planning 1994), Virginia (Virginia Employment Commission 1993), and Washington, D.C. With the exception of Virginia, agency projections extend through the year 2020 for counties in the 50-mile radius. Agency projections for Virginia extend only to the year 2010. Projections for the remaining years in the renewal term are based on the assumption that the last projected rate of population growth in each county would continue unchanged (i.e., the rate of change from 2010 to 2020 is used as the rate of change from 2020 through 2040 for Delaware, Maryland, and Washington, D.C., and the rate from 2000 to 2010 is used as the rate of change from 2010 to 2040 in Virginia). Resident Population Within 16 km (10 mi) The estimated resident population within 16 km (10 mi) of the CCNPP for the years 1990,2010,2020, 2030, and 2040 is listed in Tables 2-10 through 2-14. Figure 2-10 illustrates the locations of the sectors identified in these tables. Between 1970 and 1990, the population within 16 km (10 mi) of CCNPP increased almost 50 percent to approximately 36,000. Current projections indicate that by the year 2010, the population within 16 km (10 mi) will be about 63,000, which is about 5 percent higher than the FES estimate. The higher growth within the 16-km (10-mi) radius is primarily related to rapid population growth in Calvert County, Maryland. Between 1980 and 1990, Calvert County was the fastest growing county in the State. l According to agency projections, it is expected to continue to be the fastest growing county in the State through the year 2020 (Calvert County 1994b). Factors stimulating growth in Calvert County inc!ude l proximity to the Washington, D.C., and Baltimore metropolitan areas (1- to 1.5-hour commute by car), less development and lower taxes than those areas, and less stringent land use, zoning, and development regulations compared with surrounding counties (Calvert County 1994b). Near the end of the initial license renewal term (2040), the population within 16 km (10 mi) of CCNPP is expected to be approximately 124,000. Resident Population Within 80 km (50 mi) The estimated resident population distribution within 80 km (50 mi) of CCNPP for the years 1990,2010, 2020,2030, and 2040 is shown in Tables 2-15 through 2-19. Figure 2-11 illustrates the locations of the sectors idcatified in these tables. October 1999 2-38 NUREG-1437, Supplement 1 ) i
Pl:nt and tha Environm:nt Table 2-10. Estimated Population Distribution in 1990 Within 10 mi (16 km) of CCNPP(*) Sector
- 0-1 mi .12 mi 2-3 mi 3-4 mi 4-5 mi 5-10 mi 10-mi Total N 0 0 0 0 0 0 0 NNE- 0 0 0 0 0 0 0 NE O O O O O 2 2 ENE O O O O O 169 169 E. 0 0 0 0 0 197 197 ESE O O O O O 71 71 SE 2 38 84 130 105 0 359 SSE 52 180 300 420 539 1130 2621 S 58 179 297 410 525 8211 9680 SSW 58 180 279 383 424 6705 8029 SW 59 175 273 331 142 2665 3645
.WSW 58 175 264 151 212 2001 2861 W 58 176 236 218 278 1344 2310 WNW 55 170 189 216 278 2254 3162 NW 13 68 80 120 198 2298 2777 NNW 0 0 0 0 0 474 474 Total 413 1341 2002 2379 2701 27.521 36,357 (a) Source: Derived from DOC 1991 l (b) Figure 2-10 indicates location of sector.
Table 211. Estimated Population Distribution in 2010 Within 10 mi (16 km) of CCNPPia) Sector
- 0-1' mi 12mi 2-3 ml 3-4 mi 4-5 mi 5-10 ml 10-mi Total N O O O O O O O NNE O O O O O O O NE O O O O O 2 2 ENE O O O O O 179 179 E O O O O O -
209 209 ESE O O O O O 75 75 SE 3 70 155 240 194 0 662 SSE 96 332 554 776 996 1825 4579 S 107 331 548 757 970 14,868 17,581 SSW 107 332 515 708 784, 11,022 13,468 SW 109 323 504 612 261 3524 5333 WSW' 107 322 488 277 392 2733 4319 W 107 324 435 402 514 2450 4232 WNV, 101 313 347 399 514 4167 5841 NW 24 124 147 221 366 4248 5130 NNW 0 0 0 0 0 875 875 Total 761 2471 3693 4392 4991 46,177 62,485 (a) Source: Derived from Maryland Office of Planning 1994. l (b) Figure 2-10 indicates location of sector. NUREG-1437, Supplement 1 2-39 October 1999 I
Plint cnd tha Environm:nt Table 2-12. Estimated Population Distribution in 2020 Within 10 mi (16 km) of CCNPP(*) Sector *' 0-1 mi 1-2 mi 2-3 mi 3-4 mi 4-5 ml 5-10 mi 10-mi Total N O O O O O O O NNE O O O O O O O NE O O 0 0 0 2 2 ENE O O O O O 182 182 E O O O O O 213 213 ESE O O O O O 76 76 SE 4 90 200 309 250 0 853 SSE 123 429 715 1001 1285 2217 5770 S 138 426 707 977 1250 19.011 22,509 SSW 138 429 664 913 1011 13,502 16,657 SW 140 416 650 789 337 3818 6150 WSW 138 417 629 359 505 3024 5072 W 138 419 562 519 662 3142 5442 WNW 131 404 450 515 662 5374 7536 NW 30 161 190 286 472 5479 6618 NNVV 0 0 0 0 0 1129 1129 Total 980 3191 4767 5668 6434 57,169 78.209 l (a) Source: Derived from Maryland Office of Planning 1994 (b) Figure 2-10 indicates location of sector. Table 2-13. Estimated Population Distribution in 2030 Within 10 mi (16 km) of CCNPP(*) Sector *' 0-1 mi 1-2 mi 23mi 3-4 mi 4-5 mi 5-10 mi 10-mi Total N O 0 0 0 0 0 0 NNE O O O O O O O NE O O O O O 2 2 ENE O O O O O 185 185 I E O O O O O 216 216 ESE O O O O O 77 77 SE 6 116 258 399 322 0 1101 SSE 159 553 922 1291 1657 2712 7294 S 178 550 912 1260 1614 24,338 28,852 SSW 178 553 857 1177 1303 16,640 20,708 SW 181 537 839 1017 436 4138 7148 WSW 178 537 811 464 651 3358 5999 W 178 540 725 669 854 4034 7000 WNW 169 521 580 664 854 6929 9717 NW 39 209 245 368 608 7065 8534 NNW 0 0 0 0 0 1456 1456 i Total 1266 4116 6149 7309 8299 71,150 98.289 l (a) Source: Derived from Maryland Office of Planning 1994. (b) Figure 2-10 indicates location of sector. October 1999 2-40 NUREG-1437, Supplement 1
1 Plant and ths Environment Table 2-14. Estimated Population Distribution in 2040 Within 10 mi (16 km) of CCNPP( Sector
- 0-1 mi 12mi 2-3 mi 3-4 mi 4-5 mi 5-10 mi 10-mi Total N O O O O O O O NNE O O O O O O O NE O O O O O 2 2 ENE O O O O O 187 187 E O O O O O 219 219 ESE O O O O O 79 79 SE 7 150 333 515 416 0 1421 SSE 206 713 1189 1665 2137 3336 9246 S 229 709 1177 1624 2080 31,195 37,014 SSW 229 713 1105 1518 1681 20.622 25.868 SW 233 693 1082 1312 562 4483 8365 ;
WSW 229 633 1046 597 840 3743 7148 W 229 697 935 863 1102 5181 9007 WNW 218 072 748 856 11-02 8936 12,532 NW 51 269 317 475 785 9110 11,007 ' NNW 0 0 0 0 0 1878 1878 Total 1631 5309 7932 9425 10.705 88.971 123.973 (a) Source: Derived from Maryland Office of Planning 1994. l (b) Figure 2-10 indicates locatica of sector. l I Between 1970 and 1990, the population within 80 km (50 mi) of CCNPP increased approximstcly 30 percent to about 3,086,000 (Table 2-15). Current population projections by Maryland, Virginia, Del: ware and the District of Columbia indicate that by the year 2010, the population within 80 km (50 mi) will be approximately 3,718,000 (Table 2-16), which is about 20 percent lower than the FES estimate. This difference may be attributed to the slower than expected growth in the Washington, l D.C., metropolitan area. In fact, the FES population estimate of 4,757,810 for the year 2010 is higher i thin the current population projection of 4,719,00'O (Table 2-19) for the year 2040. During the license ; r;n:wal period, major growth areas within the 80-km (50-mi) radius include Calvert, Charles, and Queen Annes Counties in Maryland, and Stafford County in Virginia. l Tcble 2-201ists the age distribution of Calvert County in 1990 and the projected age distribution in 2020 compared to the U.S. population. Given the similarities in percentage distributions in the year 2020, the percentage age distribution for the U.S. population in the year 2030 (approximately the midpoint of the license renewal term) can be used to estimate the age distribution of the population in the region surrounding the plant in the year 2030. Table 2-20 shows the percentage age distribution of the U.S. l 4 population, and Table 2-21 shows the estimated age distribution of the population within 16 and 80 km l (10 and 50 mi) of CCNPP in 2030. As shown in Table 2-21, the population under the age of 18 is l cxpected to represent approximately 23.7 percent of the total population. The largest group is expected l to be composed of individuals aged 18 to 44 years. l NUREG-1437, Supplement 1 2-41 October 1999
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Plant and the Environm:nt Tr:nsient Population The transient population can be classified as daily or seasonal. Daily transients are associated with pt ces where a large number of people gather regularly, such as local businesses, industrial facilities, and schools. Seasonal transients result from the use of recreational areas such as parks, museums, cnd marinas in the area. It is estimated that seasonal transients increase the Calvert County population by epproximately 23 percent during the summer months (BGE 1992). The daily and seasonal populations associated with selected industry and recreation within 16 km (10 mi) of the station are listed in Table 2-22. It should be noted that on most weekdays, a significant portion of the resident population is absent from Calvert County during daytime hours. According to the 1990 Census of Population,57 percent of cmployed County residents (about 13,000 people) commuted to jobs outside of Calvert County (Calvert County 1997b). With increased numbers of in-movers to the County, the number of commuters was l estimated by the State to have increased to 19,250 in 1996 based on the 1990 Census patterns. However, with the large increase in commuter households since 1990, the percentage of commuters may have increased despite increasing commercial development in the County. 2.2.9 Historic and Archaeological Resources This section discusses the cultural background and the known historic and archaeological resources at th3 CCNPP site and in the surrounding area. 2.2.9.1 Cultural Background The area around the CCNPP site is rich in both prehistoric and historic period resources. This part of southem Maryland has a cultural sequence that extends back to about 10,000 B.C. Aboriginal occupation of the area lasted until the early 1600s when European encroachment pushed the remaining Native American groups from the area. The prehistoric and proto-historic Native American chronology includes three major cultural periods: (1) Paleo-Indian (10,000-7500 B.C.); (2) Archaic (7500-1000 ( B.C.); and (3) Woodland (1000 B.C.-1600 A.D.) (Pogue and Smolek 1985). Generally speaking, this s:quence includes a semi-nomadic existence emphasizing hunting in the earlier timeframe, followed by a shift to more sedentary settlements, more dependent on maize horticulture, along the larger rivers end Chesapeake Bay coastline in Woodland times. Before contact by Europeans in the early 1600s, l the region was occupied for several centuries by two Algonkian tribes known as the Nanticokes and the Piscataway. Another tribe, the Susquehannocks, an Iroquoian group from the area that was to become Pennsylvania, moved into the area just before the European contact. l NUREG-1437, Supplement 1 2-43 October 1999
Pl:nt end ths Environm:nt Table 2-15. Estimated Population Distribution in 1990 Within 50 mi (80 km) of CCNPP(') Sector" 0-10 mi 10-20 mi 20~!D mi 30-40 mi 40-50 mi 504 nil Total N O O 4755 103,099 154,220 262,074 NNE O 199 9621 24,321 8205 42,346 NE 2 1979 13,694 15,302 12,862 43,839 ENE 169 10,449 19,585 8998 22,817 62,018 E 197 958 1051 6137 60,307 68,650 ESE 71 361 416 26,220 18,838 45,906 SE 359 1 14 663 13,502 14,539 SSE 2621 1266 635 12,844 479 17,845 S 9680 13,864 7475 12,564 13,779 57,362 SSW 8029 13,829 13,962 6458 14,588 56,866 SW 3645 7222 21,808 5836 5243 43,754 WSW 2861 10,129 4757 26,296 6836 50,879 W 2310 10,488 16,982 25,813 42,789 98,382 WNW 3162 7764 41,305 52,317 262,046 366,594 NW 2777 9051 16,050 223,107 1,244,547 1,495,532 NNW 474 13,018 42,692 68,978 234,075 359,237 Total 36,357 100,578 214,802 618.953 2,115,133 3.085.823 (a) Source: Denved from DOC 1991, (b) Figure 2-11 indicates location of sector. Table 2-16. Estimated Population Distribution in 2010 Within 50 mi (80 km) of CCNPPt") Sector
- 0-10 mi 10-20 mi 20-30 mi 3040 mi 40-50 mi 50 mi Total N O O 5684 122,158 180,326 308,168 NNE O 230 11,147 32,781 11,077 55,235 NE 2 2107 15,865 17,832 15,465 51,271 ENE 179 11,123 20,987 9882 30,274 72,445 E 209 1019 1117 7157 73,078 82,580 ESE 75 383 442 30,930 22.239 54,069 SE 662 1 14 780 15.895 17,352 SSE 4579 1672 839 16,514 550 24,154 S 17,581 18,338 9833 15,510 15,721 76,983 SSW 13,468 18,290 17,830 7144 15,628 72,360 SW 5333 9551 26,877 6813 5432 54,006 WSW 4319 13,396 6804 38,057 8682 71,258 W 4232 13,907 24.538 40,493 66,623 149,793 WNW 5841 12,064 65,890 75,829 361,175 520,799 NW $130 16,374 22,121 270,772 1,349,440 1,663,837 NNW 875 24,069 55,006 82,903 280,590 443,443 Total 62.485 142.524 284,994 775,555 2,452,195 3,717,753 l (a) Sources: Denved from Maryland Office of Planning 1994; Delaware Development Office 1995; Virginia Employment Commission 1993; Washington, D C. Mayor's Office of Planning 1995.
(b) Figure 2-11 indicates location of sector, October 1999 2-44 NUREG-1437, Supplement 1 l j
Plant and ths EnvironmSnt Table 2-17, Estimated Population Distribution in 2020 Within 50 mi (80 km) of CCNPP(*) Sector'** 0-10 mi 10-20 mi 20 30 mi 30-40 mi 40-50 mi 50-mi Total N- 0 0 5,954 127,647 187,707 321,308 NNE D. 240- 11.650 35,504 11,998 59,392 NE 2 2140 16,580 18,669 16,321 53,712 ENE 182 11,297 21,363 10,142 32,382 75,366 E 213 1035 1134 7505 77,285 87,172 ESE 76 389 449 31,698 22,752 55,364 SE 853 1 15 791 16,123 17,783 SSE 5770 1812 910 17,698 586 26,776 S 22,509 19,870 10,648 16,666 16,689 86.382 l SSW 16,657 19,818 19,238 7501 16,156 79,370 SW 6150 10,349 28,988 7282 5522 58.291 WSW 5072 14,516 7594 43,246 9645 80,073 W 5442 15,098 27,491 46,793 76.674 171,498 WNW 7536 14.241 76,286 86,001 405,880 589,944 j NW 6618 20,980 25,269 296,136 1,417,969 1,766,972 l NNW 1129 31,036 60,761 89.588 302.196 484,710 Total 78,209 162.822 314,330 842,867 2.615,885 4.014.113 (a) Sources: Denved from Maryland Office of Planning 1994; Delaware Development Office 1995; Virginia Employment l Commission 1993; Washington, D.C. Mayor's Offce of Planning 1995. (b) Figure 2-11 indcates location of sector. I 1 I Table 2-18. Estimated Population Distribution in 2030 Within 50 mi(80 km) of CCNPP(*) Sector'* 0-10 mi 10-20 mi 20-30 mi 30 40 mi 40-50 mi 50-mi Total N O O 6240 133,412 195,396 335,048 NNE O 251 12,177 38,468 13,005 63,901 NE 2 2173 17,329 19.543 17.233 56,280 ENE 185 11,471 21,744 10,412 34,639 78,451 E 216 1051 1150 7871 81,735 92,023 ESE 77 396 456 32,496 23.286 56,711 SE 1101 1 15 802 16,359 18.278 SSE 7294 1964 986 18,976 624 29,844 S 28,852 21,530 11.531 17,909 17,717 97,539 SSW 20,708 21,475 20,757 7878 16,701 87,519 SW 7148 11,215 31,286 7796 5618 63,063 WSW 5999 15,730 8486 49,194 10,725 90,134 W 7000 16.393 30,834 54,070 88,259 196,556 WNW 9717. 16,908 88,320 97,604 456,889 669.438 NW 8534 26,906 28,973 323,884 1,491,.231 1,879,528 NNW 1456 40,019 67,748 96,854 325,633 531,710 Total 98,289 187,483 348 032 917,169 2,795,050 4,346.023 (a) Sources: Denved from Maryland Office of Planning 1994; Delaware Development Office 1995; Virginia Employment ' l Commission 1993; Washington, D.C. Mayor's Office of Planning 1995, (b) Figure 2-11 indicates location of sector, NUREG-1437, Supplement 1 2-45 October 1999
Pl nt end ths Environm::nt Table 2-19. Estimated Population Distribution in 2040 Within 50 mi (80 krn) of CCNPP(') Sector *8 0-10 mi 16-20 mi 20-30 mi 30-40 mi 40-50 mi 50-mi Total N 0 0 6541 139,462 203,399 349,402 NNE 3 262 12,727 41,700 14,105 68,794 NE 2 2207 18.114 20,461 18,198 58,982 ENE 187 11,649 22,139 10,695 37,053 81,723 E 219 1068 1170 8257 86,445 97,159 ESE 79 402 463 33,323 23,840 58,107 SE 1421 1 15 814 16,596 18,847 SSE 9246 2129 1067 20,357 664 33,463 S 37,014 23,331 12,488 19,250 18,806 110,889 SSW 25,868 23,270 22,403 8275 17,270 97,086 SW 8365 12,152 33,787 8364 5717 68,385 WSW 7148 17,044 9493 56,017 11,942 101,644 W 9007 17,807 34,618 62,487 101,630 225,549 WNW 12,532 20,186 102,258 110,857 515,198 761,031 NW 11,007 34,535 33,353 354,218 1,569,565 2,002,678 NNW 1878 51,603 76,309 104,756 351,064 585,610 Total 123,973 217,646 386,945 999,293 2.991,492 4,719,349 l (a) Sources: Derived from Maryland Office of Planning 1994; Delaware Development Office 1995; Virginia Employment Commission 1993; Washington, D.C. Mayor's Office of Planning 1995. (b) Figure 2-11 indicates location of sector. Table 2-20. Estimated Age Distribution of Population in 1990 and 2020
' Calvert County, Maryland United States Yearand Age Group Nember Percent Number Percent 1990: Under5 4066(*) 7.9 18,757,0004* 7.5 5-19 11,854(*) 23.1 52,981,00044 21.3 20-44 21,316(*) 41.5 99,731,000(4 40.1 45-64 9554'* 18.6 46,169,000(4 18.6 65 and Over 4582(* 8.9 31,080'* 12.5 Total 51,372(*) 100.0 248,718,000(4 100.0 2020: Under 5 7940*) 6.5 21,979,000(* 6.6 5-19 23,130*) 18.9 64,246,000(* 19.3 2044 40,360'* 32.9 103,844,000(* 31.2 45-64 32,530*) 26.6 79,453,000(* 23.9 l 65 and Over 18,530*) 15.1 53,220,000(* 16.0 I 332,742,000(*
Total 122,500*) 100.0 100.0 (a) U.S. Bureau of the Census Database: C90STFIA. l (b) Maryland Department of Business and Economic Development 1996-1997. (c) DOC 1995. (d) DOC 1996. October 1999 2-46 NUREG-1437, Supplement 1
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i Plint end tha Environm::nt Table 2-21. Projected Age Distribution in 2030 Within 10 mi(16 km) and 50 mi (80 km) of CCNPP Estimated Percentage Estimated Estimated Age Distribution of Population Within Population Within Age Group U.S. Population 10 mi of CCNPP(') 50 mi of CCNPP(*) Under 5 6.5 6389 282,491 5-17 17.2 16,906 747,516 18-44 34.4 33,811 1,495,032 45-64 21.8 21,427 947,433 65 and Over < 20.1 19,756 873,551 Total 100.0 92,289 4,346,023 (a) Total population for the areas within 10 and 50 mi of CCNPP is derived from Tables 2-10 and 2-15, respectively. Table 2-22. Transient Population Associated with Major Facilities Within 16 km (10 mi) of CCNPP Population Family Location Annual Daily Patuxent River Naval Air Station 6-8 mi S and SW 1500 Chesapeake Bay B'ological i Laboratory 8-9 mi S 125 Calvert Cliffs State Park 2-4 mi S, SSE, and SE 137,500 Jefferson Patterson State Park and Museum 5 mi SW 17,560 Cypress Swamp Sanctuary 9-10 mi WNW 15,510 Flag Ponds Park 1-2 mi NW 23,750 Calvert Marine Museum 7-8 mi S 47,960 Appeal Elementary School 4-5 mi S 820 1 Patuxent Elementary School 4-5 mi S 880 Mutual Elementary School 6-7 mi WNW 760 Southern Middle School 1-2 mi SSW 740 Our Lady Star of the Sea School 7-8 mi S 140 Town Creek Elementary School 9-10 mi SSW 320 St. John Elementary School 9-10 mi SW 240 Hollywood Elementary School 9-10 mi SW 270 CCNPP Visitors Center Onsite 29,000 l
Reference:
Calvert County 1994a; BGE 1992. i October 1999 2-48 NUREG-1437, Supplement 1
l l Plant and the Environment l Historic European intrusion settlement in the area today known as Calvert County began in the 1620s with visits by fur traders, with the first settlement in the county established in the 1640s. During the later pirts of the 1600s and continuing into the 1800s, the economy of Calvert County centered on cgriculture, primarily the tobacco crop. Small planters, later supplanted by larger plantations, dominated this agrarian context at first. While other sectors of Maryland were undergoing transitions from agricultural to industrial and rural to urban in the late 1800s and early 1900s, Calvert County remained dependent on tobacco farming (McGrath and McGuire 1992). In the early 1900s and continuing until today, shellfish and tourism were added to the important economic pursuits. Th3 land on which the CCNPP is located is believed to have been part of an original land grant of 1000 acres in 1658 from Cecilius Calvert, the 2nd Lord Baltimore, to Richard Preston. This grant is commonly referred to as "Preston's Cliffs" or " Charles' Gift." In the mid-1700s, the general area was rnferred to as "Gideon and Cleverlys Right." By 1782, the acreage where the power phnt is located was owned by Andrew Wilson, whose heirs owned the land until 1916, at which time it was sold to Goodman Goldstein. The land was purchased from the Goldstein heirs in May 1967 by BGE to be the sita of the CCNPP. 2.2.9.2 Historic and Archaeological Resources at CCNPP Archaeological Thare are no known or recorded prehistoric archaeological sites at CCNPP, although no records could be located to indicate that any field surveys have been undertaken to identify such resources at the 2300-acre plant site. Today,70 percent of this area remains forested and relatively undisturbed by pl:nt activities. Numerous important archaeological sites occur in proximity to CCNPP (Pogue and Smolek 1985), and it is possible that undetected or buried archaeological sites may be present within the plant area boundary. Away from the plant, several archaeological field surveys and site evaluations have been completed for BGE transmission line activities, beginning in 1980 (Evans 1980) and subsequently in the early 1990s (Hopkins et al.1992; Davis and Polglase 1992; Davis et al.1992; Davis and Simons 1993, and l Goodwin and Associates 1993). Hi; toric Although a systematic cultural resources field survey of the CCNPP tract has not been performed, s:veral historic period sites have either been recorded or are known to exist. These historic properties include the following (site number designations are from either the Maryland Historical Trust State Historic Sites Survey or the Maryland Archaeological Site Survey): (1) CT-58 (Parran's Park) - This historic farmstead included a Maryland Colonial clapboard house, original construction about 1750, that bumed in 1955 and other farm outbuildings. Part of an NUREG-1437, Supplement 1 2-49 October 1999
PI:nt and ths Environm:nt original tobacco barn, dating to 1840-1860, still exists as part of a reconstructed structure and is used by BGE as a farm and maintenance center as part of the Old Bay Farm operation. (2) CT-59 (also designated 18-CV-7) (Preston's Cliffs; Wilson Place)- The remnants of this farm are conspicuous today as the location of the CCNPP Visitors Center and Nature Trail. The farm site i consists of the foundation and fireplace chimneys of the house (extant by at least 1691), which was i destroyed in 1972 because of its deteriorated condition. a standing log bam (CT-59A), indicated as being the oldest of its kind still standing in the State (being built in 1820), and a modified frame tobacco bam (CT59B) (original construction 1820-1840) that currently serves as the permanent ' Visitors Center and museum. CT-59 was first recorded in the State listings as a historic site in 1967 and later as an archaeological site in 1973. Although to date it has not been nominated for the National Register of Historic Places, the property has important historic value and is an important visitation location at the CCNPP site. All three of the structures have been described and recorded, including Historic American Building l Survey (HABS) level documentation of the house in 1971 before its demolition (Carson 1974a), including measured drawings and photographs. The house foundation and chimneys were stabilized in 1974 (Rose 1974), and limited archaeological testing was conducted along the foundation in conjunction with the stabilization work (Carson 1974b). Nield (1977) described the log bam structure as part of a survey of historical sites along the BGE transmission corridor, and Stone (1978) discussed the frame tobacco bam. The significance of the frame bam that currently serves as the CCNPP Visitors Center has been apparent as it is shown in a 1936 photograph on file at the HABS office in Washington, D.C. (3) CT-154 (Calvert Cliffs Nuclear Power Plant)- The CCNPP has been recorded as a historical property in the Maryland Historical Trust Survey, including a written statement covering its historical and architecturalimportance. (4) Other Sites - Other, as yet unrecorded and unevaluated, historic sites exist on the CCNPP property. Included are standing tobacco bams and Camp Canoy, a currently-used BGE company recreation facility that incorporates an original Boy Scouts of America camp that may have begun to operate as early as the 1930s. Three of about 30 log structures remain from the scout camp era, including two cabins and a larger storage building. Similar to the situation for prehistoric archaeological sites, archaeological contexts from the historic period have not been fully inventoried nor evaluated. Given the lengthy historic occupation of this area, cultural features such as dumps, privies, and other obscured or buried historic activity areas characteristic of fanns may exist on the CCNPP property. Potential impacts to historic sites along the South Circuit transmission corridor were identified and evaluated (Black & Veatch 1992). October 1999 2-50 NUREG-1437, Supplement 1
Plant and the Environment i Ntti:nal Register of Historic Places and Other Listed Properties i i Eight listed historic properties within a 8-km (5-mi) radius of CCNPP are identified in the National Register listing for Calvert County. The closest of these to the plant site are the Middleham Episcopal Ch;pel (CT-60), located in the Calvert Cliffs State Park south of Lusby, the Cove Point Lighthouse (CT-65), along the Bay coastline southeast of CCNPP, and Morgan Hill Farm, southwest of the plant toward the Patuxent River. The National Register-listed Jefferson Patterson Park and Museum, a j Maryland State Museum of History and Archaeology and home to the Maryland Archaeological l Conservation Laboratory, is located west of CCNPP, along the Patuxent River. The Maryland Commission on African American History and Culture maintains an inventory ofimportant sit::s, structures, and settlements. A review of the listing for Calvert County indicates a number of sites of historic importance to African Americans in the Lusby vicinity, located just southwest of the plant site. Inc!Gded among these sites are former slave houses and servant's quarters, churches, schools, and sitti:ments. No such properties are indicated as being located within the CCNPP plant site boundary. 2.2.10 Related Federal Project Activities i The staff reviewed the possibility that activities of other Federal agencies might impact the renewal of l ths operating licenses for the CCNPP. Any such activities could result in cumulative environmental l im;ccts and the possible need for the Federal agency to become a cooperating agency for preparation of the SEIS. Tha staff determined that there were no other Federal project activities in the vicinity of CCNPP that could result in cumulative environmental impacts or that would make it desirable for another Federal egency to become a cooperating agency for preparation of the SEIS. No Federal agencies participated in th3 scoping meetings or submitted written comments during the comment period for the scoping process. Th2 CCNPP withdraws water from the Aquia Aquifer (see Section 4.5.1). The Patuxent River Naval Air Station located in St. Mary's County is another (and more significant) user of this aquifer. Groundwater withdrawal by the Air Station has environmental effects that are cumulative with the withdrawal for l CCNPP. There are numerous other users of the aquifer other than CCNPP and the Naval Air Station. As a result of this large demand, the potentiometric surface in this area has dropped; however, there rrmains approximately 90 m (300 ft) of drawdown still available. The Maryland Department of Natural Resources (MDNR) monitors the status of the aquifer. The MDE issues permits for groundwater appropriation. BGE holds permits to withdraw groundwater for use at CCNPP and is in compliance with j ths terms of the permits. l 2.3 References 10 CFR 20.1301,
- Dose limits for individual members of the public."
NUREG-1437, Supplement 1 2-51 October 1999
PI:nt c:nd th) Environm::nt l 10 CFR Part 20, Appendix B, Table 11, " Annual limits on intake (Alls) and Derived Air Concentrations (DACs) of radionuclides for occupational exposure; effluent concentrations; concentrations for release to sewerage." , 10 CFR Part 50, Appendix 1, " Numerical guides for design objectives and limiting conditions for operation to meet the criterion "as low as is reasonably achievable" for radioactive material in light-water-cooled nuclear power reactor effluents." 10 CFR Part 54, " Requirements for renewal of operating licenses for nuclear power plants." 10 CFR Part 61, " Licensing requirements for land disposal of radioactive waste." 10 CFR Part 71, " Packaging and transportation of radioactive material." 40 CFR 81.321, " Designation of areas for air quality planning purposes: Maryland." 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operations." l 49 CFR Parts 171 through 177. l 62 FR 49611, " Approval and Promulgation of Air Quality implementation Plans; Maryland; 15% Rate of l Progress Plan for the Maryland Portion of the Metropolitan Washington, D.C. Area," September 23, l 1997. l l 63 FR 36578, " Approval and Promulgation of Air Quality implementation Plans; District of Columbia; 15 Percent Plan for the Metropolitan Washington, D.C. Ozone Nonattainment Area," July 7,1998. Abbe. G.R.1988. " Population structure of the american oyster, Crassostrea virginica, on an oyster bar in central Chest.gake Bay: Changes associated with shell planting and increased recruitment." j Joumal of Shellfish Research, Vol. 7, No.1, 33-40. ' Abbe, G.R.1992. " Pollution structure of the eastem oyster, Crassostrea virginica (Gmelin,1791) on two oyster bars in central Chesapeake Bay: Further changes associated with shell planting, recruitment, and disease." Joumal of Shellfish Research, Vol.11, No. 2,421-430. l Achmed, G., and H. J. Hansen. 1997. Hydrogeology, Model Simulation, and Water-Supply Potential of l the Aquia and Piney Point-Najemoy Aquifers in Calvert and St. Mary's Counties, Maryland. Report of l Investigations No. 64. Maryland Geological Survey, Baltimore, Maryland. I Atomic Energy Act of 1954 (AEA), as amended,42 USC 2011-2259, et seq. l Baltimore Gas and Electric (BGE).1970. Environmental Report, Calvert Cliffs Nuclear Power Plant (November 16,1970), Lusby, Maryland. October 1999 2-52 NUREG-1437, Supplement 1
PI:nt cnd ths Environm:nt C^.itimore Gas and Electric (BGE). 1971. Supplement to Environmental Report; Calvert Cliffs Nuclear l t-ower Plant, (November 8,1971) Lusby, Maryland. B ltimore Gas and Electric (BGE).1992. Calvert Cliff's Independent Spent Fuel Storage Installation l (ISFSI) Updated Environmental Report, Volume lli (December 22,1992). Lusby, Maryland. B ltimore Gas ar:d Electric (BGE).1997. Calvert Cliffs Updated Final Safety Analysis Report (UFSAR), R v. 21. Lusby, Maryland. B:ltianore Gas and Electric (BGE). 1998a. Applicant's Environmental Report - Operating License l R:newal Stage - Calvert Cliffs Nuclear Power Plant Units 1 and 2, (April 1998). Lusby, Maryland. B ltimore Gas and Electric (BGE).1998b. RadiologicalEnvironmentalMonitoring Program Annual l R: port January 1 to December 31,1997. Lusby, Marybnd. l B ltimore Gas and Electric (BGE).1998c. Letter from Mr. C. H. Cruse (BGE) to NRC Document l Control Desk, " Response to Request for Additional Information for the Review of the Calvert Cliffs l Nuclear Power Plant (CCNPP) Unit Nos.1 & 2, Environmental Report Associated with License l R::newal, and Errata (TAC Nos. MA1524 and MA1525), November 20,1998, Lusby, Maryland.. l BI ck and Veatch 1992. Assessments ofimpacts on HistoricalProperties along the BGE/PEPCO l 500 kV Transmission Une, Calvert Cliffs to Chalk Point, Calvert and Prince George's Counties, M:ryland. Report prepared for Baltimore Gas and Electric Company, Baltimore, Maryland. C lvert County.1988. Land Preservation and Open Space Plan. ' Department of Planning and Zoning. l C:lvert Count.1994a. Calvert County Land Preservation and Recreation Plan. Department of l Plinning and Zoning. l C:lvert County.1994b. Calvert County Comprehensive Water and Sewerage Plan 1993 Biennial Update. Eeputment of Planning and Zoning. l Chert County.1997a. Calvert County Zoning Ordinance. Crivert County.1997b.1997 Comprehensive Plan, Calvert County, Maryland. C rson, C.1974a. Architectural Analysis of House on Calvert Cliffs, Lusby Vicinity, Calvert County l M:ryland. Report on file at the Maryland Historical Trust, Crownsville, Maryland. Cirson, C.1974b. " Archaeological Observations." Appendix to Architectural Analysis of House on Calvert Cliffs, Lusby Vicinity, Calvert County, Maryland. Report on file at the Maryland Historical Trust, Crownsville, Maryland. l NUREG-1437, Supplement 1 2-53 October 1999
Pl:nt cnd the Environment l Federal Water Pollution Control Act (FWPCA), as amended, 33 USC 1251 et seg. (also known as the l Clean Water Act). l Clean Air Act (CAA), as. amended,42 USC 7401 et seg. l [ l l Coastal Zone Management Act (CZMA), as amended,33 USC 1455 et seg. 1 Davis, T. W., L. Hirrel, T. W. Neumann, Timothy Silva, Kathleen Federline, Justine Woodard, and l Christopher R. Polglase. 1992. Phase II Archaeological Evaluations of Sites 18CV61 and 18CV62, l Calvert County, Maryland. Report prepared by R. Christopher Goodwin & Associates, Inc., for Baltimore Gas and Electric Company, Lusby, Maryland. Davis, T. W. and M. A. Simons.1993. Phase I Archaeological Survey of the Maten'als Storage Yard for l the Proposed Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Station to Chalk Point Power Station 500 kV Transmission Une Corridor, Calvert and Prince George's Counties, Maryland. Technical Addendum prepared by R. Christopher Goodwin & Associates, Inc., for Black & Veatch, Cambridge, Maryland. Davis, T. W. and C. R. Polglase.1992. Archaeological Reconnaissance of Stringing Sites for the Propowd Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Station to Chalk Point Stattun 500 kV Transmission Une Corridor, Calvert County and Prince George's County, Maryland. Technical Addendum prepared by R. Christopher Goodwin and Associates, Inc., for Black & Veatch, Cambridges, Maryland. Delaware Development Office.1995. Delaware Population Consortium. l l Evans, J. 1980. Preliminary Archaeological Reconnaissance of the Proposed 500 kV Transmission Une, Calvert County, Maryland. Technical Report prepared by the Potomac River Archaeological Survey, The American University, for Baltimore Gas and Electric Company, Lusby, Maryland. Goodwin and Associates.1993. ArchaeologicalExamination of Structure Relocations and Access Road Realignments for the Baltimore Gas and Electric Company Calvert Cliffs to Chalk Point 500 kV 1 Transmission Une Corridor- South Circuit, Calvert and Prince George's Counties, Maryland. Report prepared for Black and Veatch Cambridge, Maryland. Greller, A.M.1988.
- Deciduous Forest." North American Terrestrial Vegetation, pp. 287-316.
M.G. Barb (sur and W.D. Billings, eds., Cambridge University Press, New York. l Heck, K.L., Jr. (Ed.) 1987. Ecological Studies in the Middle Reach of Chesapeake Bay, Lecture Notes l on Coastal and Marine Studies. Springer-Verlag - Berlin, Heidelberg, New York. l Hopkins, J. W., Ill, M. D. Collier, and B. R. Fischler. 1992. Phase / Archaeological Survey of the Proposed BGFJPEPCO Calvert Cliffs to Chalk Point 500 kV Transmission Une, Calvert and Prince October 1999 2-54 NUREG-1437, Supplement i
Plant cnd ths Environm:nt 1 i George's Counties, Maryland. Report prepared by Greenhome & O'Mara, Inc., for Baltimore Gas and Electric Company, Lusby, Maryland. M ryland Department of Business and Economic DevelopmeN 1996-1997. Brief Economic Facts, St. ] .M:ry's County, Maryland. M ryland Department of the Environment (MDE).1998. Letter from Mr. Elder A. Ghigiarelli, Jr., Chief l Co stal Zone Consistency, Maryland Department of the Environment, to Ms. Claudia Craig, U.S. Nuclear Regulatory Commission, February 12,1998 and M84611, Washington, D.C. l M ryland Department of Natural Resources (MDNR),1999. Letter from Mr. Richard I. McLean, l M: nager, Nuclear Programs, Power Plant Assessment Division to Chief of Rules Review and Directives Br:nch, U.S. Nuclear Regulatory Commission, May 20,1999, Washington, D.C. M ryland Department of Natural Resources (MDNR).1993. PPRP-CElR-8/2, Maryland Powerplants i cnd the Environment, A Review of Power Plants and Transmission Lines on Maryland's Natural R: sources. Maryland Power Plant Research Program. I M ry Forest Conservation Act.1993. Natural Resources Article Section (NR Art. Sec). 5-1601-5-1613. l l M:ryland Office of Planning.1994. Population Projections for Maryland Subdivisions. Planning Data Services. Miryland Office of Planning.1998a. "Calvert County Demographic and Socioeconomic Outlook." M ryland Office of Planning, Baltimore, Maryland.
'Miryland Office of Planning.1998b. " Charles County Demographic and Socioeconomic Outlook". l Maryland Office of Planning, Baltimore, Maryland.
M ryland Office of Planning.1998c. "St. Mary's County Demographic and Socioeconomic Outlook." l M ryland Office of Planning, Baltimore, Maryland. M ryland Office of Planning.1999.' " Maryland's Population Gain Best in Four Years." Maryland State Data Center Newsletter, April 1999. Maryland Office of Planning, Baltimore, Maryland. McGrath, S. V. and P. J. McGuire, Editors.1992. The Money Crop: Tobacco Culture in Calvert l County, Maryland. Maryland Historical and Cultural Publications, Crownsville, Maryland., and Calvert County Historic District Commission, Prince Frederick, Maryland. National Environmental Policy Act (NEPA) of 1969, ae, amended,42 USC 4321, et seg. NUREG-1437, Supplement 1 2-55 October 1999
Pl:nt end the Environm:nt l National Marine Fisbaries Services (NMFS).1998. Letter from Mr. T.E. Goodger (DOC, NMFS) to Mr. l B.W. Doroshuk (BGE) in response to request for consultation with regard to Section 7 of the Endangered Species Act, February 12,1998, Oxford, Maryland. l The Natural Heritage Network.1999.
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l Maryland Natural Heritage Program. (http://www.heritaae.tnc. ora /nho/us/md/ftolist.html)(accessed July 27,1999). ] l Nield, W. L., !!, 1977. Historic Sites Survey of Proposed Corridors for the Calvert Cliffs-Chalk Point 500kV transmission Line. Report prepared by the Calvert County Historical District Commission, Prince Frederick, Maryland. l Pogue, D. J. and M. A. Smolek.1985. An ArchaeologicalResource Management Plan for the Southem Maryland Region. Maryland Historical Trust Manuscript No. 30. Division of Historical and Cultural Programs, Annapolis, Maryland. Pritchard, D.W.,1967. " Observations of circulation in coastal plain estuaries." In: Lauff, G. (Editor). Estuaries, American Association forthe Advancement of Science: pp 37-44. Washington, D.C. Resource Conservation and Recovery Act,42 USC 6901 et seg. l Rose, C. L.1974. The Conservation of Wooden Foundations of House at Calvert Cliffs. Report on file at Maryland Historical Trust, Crownsville, Maryland. Sandoz, M., and R. Rogers.1944. "The effect of environmental factors on hatching, molting, and l survival of zoea larvae of the blue crab, Callinectes sapidus Rathbum." Ecology 25: 216-226. l Stone, G. W.1978. Frame Tobacco Bam on Calvert Cliffs (Visitors Center): Report on a Preliminary
/nspection. Report on file at the Maryland Historical Trust, Crownsville, Maryland.
Tri-County Council for Southem Maryland. 1993. 1990 Statistical Profiles for Calvert, Charles, and St. Mary's Counties. U.S. Atomic Energy Commission (AEC).1973. Final EnvironmentalStatement Related to Operation of Calvert Cliffs Nuclear Power Plant Units 1 and 2, Docket Nos. 50-317 and 50-318, (April 1973). Washington, D.C. U.S. Bureau of the Census Database: C90STF1A.1990 U.S. Census Data. (http:// venus. census. gov /cdrom/ lookup /917039415) (accessed January 2,1999). U.S. Department of Commerce (DOC). 1991. 1990 Census Population and Housing; Public Law 94-171 Data. Bureau of the Census. Washington, D.C. October 1999 2-56 NUREG-1437, Supplement 1
~ Plant and tha Environmtnt U.S.' Department of Commerce (DOC).1992a. Regional Multipliers: A UserHandbook forthe RegionalInput-Output Modeling system (RIMS II). Economics and Statistics Administration, DOC, W shington, D.C.- U.S. Department of Commerce (DOC). 1992b. 1992 Census of Agriculture, Maryland Summary and __ St te Data, Volume I, Part 20, Bureau of the Census. Washington, D.C. I U.S. Department of Commerce (DOC).1995. Statistical Abstract of the United States. Economics and Statistics Administration, Washington, D.C. U.S. Department of Commerce (DOC).1996. Current Population Reports: Population Projections of ths United States by Age, Sex, Race, and Hispanic Origin: 1995-2050. P25-1130. Economics and Statistics Administiation, Washington, D.C. U.S. Environmental Protection Agency (EPA).1999. " Environmental Profile for: Calvert County, l M1ryland." (http:// tree 2. epa. gov /CEIS/CEIS.NSF/$$All/2442009 AIR) (accessed June 21,1999). l
' U.S. Fish and Wildlife Services (FWS).1998. U.S. Department of the Interior. Letter from John P.
Wdflin, Supervisor, Chesapeake Bay Field Office, to Barth W. Doroshuk, BGE, CCNPP (November 3, 1998). U.S. Nuclear Regulatory Commission (NRC).1996. Generic Environmentallmpact Statement for Lic nse Renewal of Nuclear Powerplants (GEIS), NUREG-1437. Washington, D.C. Virginia Employment Commission.1993. ' Virginia Population Projections, 2010. Economic Information Services Division. W:shington, D.C. Mayor's Office of Planning.1995. Summary ofIntennediate Population Forecasts. W:shington, D.C. I
-_ NUREG-1437, Supplement 1 2-57 October 1999 i
p 3.0 EnvironmentalImpacts of Refurbishment License renewal actions may require refurbishment activities for the extended plant life. These actions m y have an impact on the environment that requires evaluation, depending on the type of action and l i l the plant-specific design. Environmental issues associated with refurbishment that were determined to l be C tegory 1 issues are listed in Table 3-1. l Table 3-1. Category 1 issues for Refurbishment Evaluation l l l ISSUE-10 CFR Part $1, Subpart A, Appendix B, Table B-1 GEIS Sections l l SURFACE-WATER QuAUTY, HYDROLOGY, AND UsE (FoR ALL PLANTS) Impacts of refurbishment on surface-water quality 3.4.1 Impacts of refurbishment on surface-water use 3.4.1 t aquatic ECOLOGY (FoR ALL PLANTS) Refurbishment 3.5
~
GROUNDWATER UsE AND QUALITY l Impacts of refurbishment on groundwater use and quality 3.4.2 LAND UsE Onsite land use 3.2 HUMAN HEALTH Radiation exposures to the public during refurbishment 3.8.1 Occupational radiation exposures during refurbishment 3.8.2 SOctoECoNOMICS Public services: public safety, social services, and tourism and 3.7.4; 3.7.4.3 recreation 3.7.4.4; ? ".4.6 Aesthetic impacts (refurbishment) 3.7.8 l l Environmental issues related to refurbishment considered in the GEIS for which generic conclusiono could not be reached for all plants, or for specifi : classes of plants, are Category 2 issues. These are l li;ted in Table 3-2. i NUREG-1437, Supplement 1 3-1 October 1999 ll 1
R:furbishm:nt Table 3-2. Category 2 issues for Refurbishment Evaluation 10 CFR l lSSUE-10 CFR Part 51, Subpart A, 51.53(c)(3)(ii) Appendix B, Table B-1 GEIS Sections Subparagraph TERRESTRIAL RESOURCES Refurbishment impacts 3.6 E THREATENEc OR ENDANGERED SPECIES (FOR ALL PLANTS) Threatened or endangered species 3.9 E AIR QUALITY Air quality during refurbishment (non-attainment and 3.3 F maintenance areas) SOcloEcoNoMICS Housing impacts 3.7.2 i Public services: public utilities 3.7.4.5 I Public services: education 3.7.4.1 1 Offsite land use 3.7.5 I Public services, transportation 3.7.4.2 J Historic and archaeological resources 3.7.7 K ENvlRONMENTAL JUSTICE Environmentaljustice Not addressed i l The potential environmental effects of refurbishment actions would be identified, and the analysis would l be summarized within this section, if such actions were planned. BGE stated that it "has not identified the need to undertake the major refurbishment activities that the GEIS assumed for license renewal, and no other modifications have been identified that would directly affect the environment or plant l l effluents (BGE 1998 and 1999)." Therefore, refurbishment is riot considered in this SEIS. l \ October 1999 3-2 NUREG-1437, Supplement 1 q l -- -
1 1 l 4.0 EnvironmentalImpacts of Operation i i Environmental issues associated with operation during the renewal term were discussed in the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437 (NRC 1996a). The GEIS included a determination of whether the analysis of the environmental issue could be applied to all plants, and whether additional mitigation measures would be warranted. Issues were then assigned a Category 1 or a Category 2 designation. As set forth in the GEIS, Category 1 l i;:ues are those that meet all of the following criteria: l (1) the environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other specified plant or site characteristics (2) a single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for collective offsite radiological impacts from the fuel cycle and from high-level waste and spent fuel disposal) (3) mitigation of adverse impacts associated with the issue has been considered in the analysis, and it l has been determined that additional plant-specific mitigathn measures are likely not to be sufficiently beneficial to warrant implementation. For issues that meet the three Category 1 criteria, no additional plant-specific analysis is required unless new and significant information is identified. C:tegory 2 issues a e those that do not meet one or more of the criteria of Category 1, and therefore, l , cdditional plant-specific review for these issues is required. l This chapter addresses those issues related to operation during the renewal term that are listed in l 10 CFR Part 51, Subpart A, Appendix B, Table B-1, that are applicable to CCNPP. Section 4.1 l cddresses the Category 1 issues applicable to the CCNPP once-through cooling system, while C tegory 2 issues applicable to the CCNPP cooling system are discussed at greater length in Sections 4.1.1 through 4.1.3. Section 4.2 addresses Category 1 issues related to transmission lines l cnd land use, while Category 2 issues are discussed in Sections 4.2.1 and 4.2.2. Section 4.3 addresses the radiologicalimpacts of normal operation. There are no Category 2 issues related to radiologicalimpacts of normal operation. Section 4.4 addresses the Category 1 issues related to the socioeconomic impacts of normal operation during the renewal term. Category 2 socioeconomic issues era discussed in Section 4.4.1 through 4.4.6. Section 4.5 addresses the Category 1 issues related to groundwater use and quality. Category 2 groundwater use and quality issues are discussed in Section 4.5.1. Section 4.6 diccusses the impacts of renewal-term operations on threatened and endangered species, a Category 2 issue. Section 4.7 addresses an issue, extremophiles, that was raised by the public during scoping. This issue was determined to be new, but not significant. The results of the ! NUREG-1437, Supplement 1 4-1 October 1999
Environm:ntil Impacts of Operation evaluation of environmental issues related to operation during the renewal term are summarized in Section 4.8. Finally, Section 4.9 lists the references for Chapter 4. 4.1 Cooling System l Category 1 issues in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, that are applicable to CCNPP cooling system operation during the renewal term are listed in Table 4-1. BGE stated in its l Environmental Report (ER) that it is unaware of any new and significant information related to these Category 1 issues. No significant new information has been identified by the staff in the review process and in the staffs independent review. Therefore, the staff concludes that there are no impacts related to these issues beyond those discussed in the GEIS. For all of the issues, the GEIS concluded that the impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. A brief description of the staffs review and the GEIS conclusions, as codified in Table B-1, for each of these issues follows.
. Altered current Datterns at intake and discharae structures: Besed on information in the GEIS, the l Commission found that " Altered current pattems have not been found to be a problem at operating nuclear power plants and are not expected to be a problem during the license renewal term." The l staff has not identified any significant new information during its independent review of the BGE ER, l the staffs site visit, the scoping process, its review of public comments on the draft SEIS, or its l evaluation of other available information, including reports of studies of the Chesapeake Bay performed for the Maryland Department of Natural Resources (MDNR). Therefore, the staff concludes that there are no impacts of altered current pattems during the renewal term beyond those discussed in the GEIS.
l . Altered salinity aradients: Based on information in the GEIS, tha Commission found that " Salinity gradients have not been found to be a problem at operating nuclear power plants and are not expected to be a problem during the license renewal term." The staff has not identified any l significant new information during its independent review of the BGE ER, the staffs site visit, the l scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including reports of studies of the Chesapeake Bay performed for the MDNR. Therefore, the staff concludes that there are no impacts of altered salinity gradients during the renewal term beyond those discussed in the GEIS.
. Temperature effects on sediment transport capacity: Based on information in the GEIS, the l Commission found that "These effec's have not been found to be a problem at operating nuclear power plants and are not expected to be a problem during the license renewal term." The staff has l not identified any significant new information during its independent review of the BGE ER, the staffs site visit, the scoping process, its review of public comments on the draft SEIS, or its October 1999 4-2 NUREG-1437, Supplement 1 i
Environmental impac2s of Operation Table 4-1. Category 1 Issues Applicable to the Operation of the CCNPP Cooling System During the Renewal Term ISSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Sections l SURFACE WATER QUALITY, HYDROLOGY, AND UsE (FoR ALL PLANTS) q Altered current pattems at intake and discharge structures 4.2.1.2.1; 4.3.2.2; 4.4.2 l Altered salinity gradients 4.2.1.2.2; 4.2.2 Temperature effects on sediment transport capacity 4.2.1.2.3; 4.4.2.2. Scouring caused by discharged cooling water 4.2.1.2.3; 4.4.2.2 Eutrophication 4.2.1.2.3; 4.4.2.2 Discharge of chlorine or other biocides 4.2.1.2.4; 4.4.2.2 Discharge of sanitary wastes and minor chemical spills 4.2.1.2.4; 4.4.2.2 Discharge of other metals in waste water 4.2.1.2.4;4.3.22;4.4.2.2 Water-use conflicts (plants with once-through cooling systems) 4.2.1.3 AouATic ECOLOGY (FOR ALL PLANTS) Accumulation of contaminants in sediments or biota 4.2.1.2.4; 4.3.3; 4.4.3; 4.4.2.2 Entrainment of phytoplankton and zooplankton 4.2.2.1.1; 4.3.3; 4.4.3 i Cold shock 4.2.2.1.5; 4.3.3; 4.4.3 Thermal plume barrier to migrating fish 4.2.2.1.6; 4.4.3 Distribution of aquatic organisms 4.2.2.1.6; 4.4.3 Premature emergence of aquatic insects 4.2.2.1.7; 4.4.3 Gas supersaturation (gas bubble disease) 4.2.2.1.8; 4.4.3 Low dissolved oxygen in the discharge 4.2.2.1.9; 4.3.3; 4.4.3 Losses from predation, parasitism, and disease among 4.2.2.1.10;4.4.3 organisms exposed to sublethal stresses Stimulation of nuisance organisms 4.2.2.1.11;4.4.3 HUMAN HEALTH Microbial organisms (occupational health) 4.3.6 Noise 4.3.7 evaluation of other available information, including reports of studies of the Chesapeake Bay performed for the Maryland Department of National Resources (MDNR). Therefore, the staff l concludes that there are no impacts of temperature effects on sediment transport capacity during the renewal term beyond those discussed in the GEIS. NUREG-1437, Supplement 1 4-3 October 1999
EnvironmentalImpacts of Operation
. Scourina caused by discharaed coolina water Based on information in the GEIS, the Commission l found that " Scouring has not been found to be a problem at most operating nuclear power plants and has caused only localized effects at a few plants. It is not expected to be a problem during the l license renewal term." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff l concludes that there are no impacts of scouring caused by discharged cooling water during the renewal term beyond those discussed in the GEIS.
l . Eutrophication: Based on information in the GEIS, the Commission found that " Eutrophication has not been found to be a problem at operating nuclear power plants and is not expected to be a prob!em during the license renewal term." The staff has not identified any significant new l information during its independent review of the BGE ER, the staffs site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including plant monitoring data and technical reports. Therefore, the staff concludes that there are no impacts of eutrophication during the r swal term beyond those discussed in the GEIS.
. Discharae of chlorine or other biocides: Based on information in the GEIS, the Commission found l that "F.ffects are not a concern among regulatory and resource agencies, and are not expected to be a problem during the license renewal term." The staff has not identified any significant new l information during its independent review of the BGE ER and the site visit, the scoping process, its l review of public comments on the draft SEIS, and independent evaluation of available informaticJ l including the CCNPP National Pollutant Discharge Elimination System (NPDES) permit. Therefore, the staff concludes that there are no impacts of discharge of chlorine or other biocides during the renewal term beyond those discussed in the GEIS. . Discharae of sanitary wastes and minor chemical soills: Based on information in the GEIS, the l Commission found that " Effects are readily controlled through NPDES permit and periodic modifications, if needed, and are not expected to be a problem during the license renewal term." )
l The staff has not identified any significant new information during its independent review of the BGE ER, the NPDES perrnit for CCNPP, the site visit, scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes the there are no impacts of discharges of sanitary wastes or minor chemical spills during the renewal term beyond those discussed in the GEIS.
. Discharae of other metals in waste water: Based on information in the GEIS, the Commission found l that "These discharges have not been fcend to be a problem at operating nuclear power plants with cooling-tower-based heat dissipation systems and have been satisfactorily mitigated at other plants. 1 They are not expected to be a problem during the license renewal term." The staff has not identified
{ any significant new information during its independent review of the BGE ER, the NPDES permit for CCNPP, the site visit, scoping process, its review of public comments on the draft SEIS, or its October 1999 4-4 NUREG-1437, Supplement 1
EnvironmsntalImpacts of Operation evaluation of other available information. Therefore, the staff concludes that there are no impacts of I discharges of other metals in waste water during the renewal term beyond those discussed in the GEIS. j
. Water-use conflicts (olants with once-throuah coolina systemsk Based on information in the GEIS, the Commission found that "These conflicts have not been found to be a problem at operating l nuclear power plants with once-through heat dissipation systems." The staff has not identified any )
significant new information during its independent review of the BGE ER, the staFs site visit, the l l scoping process, its review of public comments on the draft SEIS, or its evaluation of other available ; information. Therefore, the staff concludes that there are no water-use conflicts during the renewal j term beyond those discussed in the GEIS. j
- Accumulation of contaminants in sediments or biota: Based on information in the GEIS, the Commission found that " Accumulation of contaminants has been a concem at a few nuclear power l plants but has been ssctisfactorily mitigated by replacing copper alloy condenser tubes with those of I another metal. It is not expected to be a problem during the license renewal term." The staff has not identified any significant new information during its independent review of the BGE ER, the l stafs site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including monitoring reports and technical reports.'
Therefore, the staff concludes that there are no impacts of accumulation of contaminants in j sediments or biota during the renewal term beyond those discussed in the GEIS. J
. Entrainmen+ of phytoolankton and zooolankton: Based or information in the GEIS, the Commission found that 'Entrainment of phytoplankton and zooplanktoi has not been found to be a problem at l operating nuclear power plants and is not expected to be a problem during the license renewal term." The staff has not identified any significant new information during its independent review of l the BGE ER, the stafs site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of entrainment of phytoplankton and zooplankton during the renewal term beyond those discussed in the GEIS.
- Cold shock: Based on information in the GEIS, the Commission found that " Cold shock has been l satisfactorily mitigated at operating nuclear plants with once-through cooling systems, has not
' endangered fish populations or been found to be a problem at operating nuclear power plants with cooling towers or cooling ponds, and is not expected to be a problem during the license renewal term.". The staff has not identified any significant new information during its independent review of l the BGE ER, the stafs site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including monitoring reports developed by Academy of Natural Sciences of Philadelphia (ANSP 1980,1981). Therefore, the staff concludes that there are no. impacts of cold shock during the renewal term beyond those discussed in the GEIS.
' NUREG-1437, Supplement 1 4-5 October 1999
Environm:ntalimpacts of Operation i
. Thermal olume barrier to mioratino fish: Bcsed on information in the GEIS, the Commission found l that " Thermal plumes have not been found to be a problem at operating nuclear power plants and are not expected to be a problem during the license renewal term." The staff has not identified any I l significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including monitoring reports developed by ANSP (1980,1981). Therefore, the staff concludes that there are no impacts of thermal plumes during the renewal term beyond those discussed in the GEIS.
l . Distribution of aauatic oraanisms: Based on information in the GEIS, the Commission found that l " Thermal discharge may have localized effects but is not expected to effect the larger geographical l distribution of aquatic organisms." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including monitoring f l reports developed by ANSP (Heck 1987) and Martin-Marietta (Holland 1985). Therefore, the staff concludes that there are no impacts on the distribution of aquatic organisms during the renewal term beyond those discussed in the GEIS. Premature emeraence of acuatic insects: Based on information in the GEIS, the Commission found l that " Premature emergence has been found to be a localized effect at some operating nuclear power plants but has not been a problem and is not expected to be a problem during the license l renewal term." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of premature emergence of aquatic insects during the renewal term beyond those discussed in the GEIS.
. Gas supersaturation (cas bubble disease): Based on information in the GEIS, the Commission l found that " Gas supersaturation was a concem at a small number of operatinf nuclear power plants with once-through cooling systems but has been satisfactorily mitigated. It is has not been found to be a problem at operating nuclear power plants with cooling towers or cooling ponds and is not expected to be a problem during the license renewal term." The staff has not identified any
{ significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of gas supersaturation during the renewal term beyond those discussed in the GEIS. l . Low dissolved oxvoen in the discharae: Based on information in the GE!S, the Commission found l that " Low dissolved oxygen has been a concem at one nuclear power plant with a once-through cooling system but has been effectively mitigated. It has not been found to be a problem at operating nuclear power plants with cooling towers or cooling ponds and is not expected to be a October 1999 4-6 NUREG-1437, Supplement 1
Environm:ntal Impacts of Operation problem during the license renewal term." The staff has not identified any significant new information during its indepent ent review of the BGE ER, the staff's site visit, the scoping process, l its review of public comments on the draft SEIS, or its evaluation of other available information, including monitoring studies conducted by ANSP (Heck 1987). Therefore, the staff concludes that there are no impacts of low dissolved oxygen during the renewal term beyond those discussed in the GEIS.
. Losses from oredation. Darasitism. and disease amona oraanisms exposed to subiethal stresses:
Based on information in the GEIS, the Commission found that "These types of losses have not been l found to be a problem at opersting nuclear power plants and are not expected to be a problem during the license renewal term." The staff has not identified any significant new information during l its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of losses from predation, parasitism, and disease among organisms exposed to sublethat stresses during the renewal term beyond those discussed in the GEIS.
. Stimulation of nuisance oraanisms (e a.. shioworms): Based on information in the GEIS, the l Commission found that " Stimulation of nuisance organisms has been satisfactorily mitigated at the l single nuclear power plant with a once-through cooling system where previously it was a problem. It l has not been found to be a problem at operating nuclear power plants with cooling towers or cooling ponds and is not expected to be a problem during the license renewal term." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's l site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Staff review of available literature (Heck 1987) and information in the l GEIS suggests that the occurrences of periodic episodes of algal blooms, and the recent l appearance of the dinoflagellate Pfisteria piscidida in the Chesapeake Bay are not attributable to the activities of CCNPP. Therefore, the staff concludes that there are no impacts of stimulation of nuisance organisms during the renewal term beyond those discussed in the GEIS. . Microbial oraanisms (occupational health): Based on information in the GEIS, the Commission found that " Occupational health impacts are expected to be controlled by continued application of l accepted industrial hygiene practices to minimize worker exposures." The staff has not identified any significant new information during its independent review of the BGE ER, tne staff's site visit, l the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of microbial organisms during the renewal term beyond those discussed in the GEIS. . Noise: Based on information in the GEIS, the Commission found that " Noise has not been found to l be a problem at operating plants and is not expected to be a problem at any plant during the license renewal term." The staff has not identified any significant new information during its independent l NUREG-1437, Supplement 1 4-7 October 1999
Environm:ntal Impacts of Operation I review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on . the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of noise during the renewal term beyond those discussed in the GEIS. Category 2 issues related to cooling system operation during the renewal term that are applicable to CCNPP are discussed in the sections that follow. These issues are listed Table 4-2. l Table 4-2. Category 2 issues Applicable to the Operation of the l CCNPP Cooling System During the Renewal Term 10 CFR l lSSUE-10 CFR Part S1, Subpart A, Appendix B, 51.53(c)(3)(ii) SEIS Table B-1 GEIS Sections subparagraph Section Aquatic Ecology (for plants with once-through and cooling pond heat dissipation systems) Entrainment of fish and shellfish in early life stages 4.2.2.1.2; 4.4.3 B 4.1.1 Impingement of fish and shellfish 4.2.2.1.3; 4.4.3 8 4.1.2 Heat shock 4.2.2.1.4; 4.4.3 8 4.1.3 4.1.1 Entrainment of Fish and Shellfish in Early Life Stages , l l Entrainment of fish and shellfish in early life stages into cooling water systems associated with nuclear l power plants is considered a Category 2 issue, requiring a site-specific assessment before license renewal. The staff reviewed NPDES Permit No. 92-DP-0187 along with a letter from the Maryland Department of the Environment (MDE) stating that the permit holder is currently in compliance with all conditions of the permit (MDE 1998). The staff also evaluated a compilation of BGE and contractor studies of I entrainment associated with the cooling water intake. BGE submitted a formal report in 1981 (ANSP l 1981) to satisfy the requirements of Section 316 of the Federal Water Po!!ution Control Act (FWPCA), l also known as the Clean Water Act. This report, along with continuing studies and regulatory evaluations of plant impacts, has supported subsequent renewals of the facility's discharge permit. The staff's investigation of entrainment issues centered around the following activities: (1) review of the j susceptibility of "important" fish and shellfish species to entrainment, (2) the economic value of the I species for local or regional commercial fisheries, (3) regional standing stocks of "important" fish and shellfish species potentially aifected by plant operation, and (4) transit time from the intake structure to l the point of discharge to the Chesapeake Bay. "important' refers to species that may be commercially or recreationally important, protected by Federal or State law, or may reside in critical habitats. The October 1999 4-8 NUREG-1437, Supplement 1
Environmental impacts of Operation staff reviewed these issues to determine the environmentalimpact of plant liease renewal on entrainment of fish and shellfish in early life stages. ! Plant-specific studies conducted by BGE personnel and studies conducted b the ANSP provided l' - cvidence of how entrainment of fish and shellfish affects the standing populations of the Chesapeake B:y in the vicinity of the CCNPP. Entrainment studies conducted by ANSP and summarized by Horowitz in Heck (1987) led to the following conclusions: l
- The species composition of the zooplankton community in the vicinity of Calvert Cliffs is typical of estuaries along the Atlantic and southeastem coast, and the planktonic species were typically l entrained in the plant cooling water in densities similar to those of the surrounding waters.
. The five species of zooplankton sufficiently abundant in entrained water to permit statistical study were Neomysis americana, Corophium lacustre, Gammarus mucronatus, Neanthes (Nereis) ;
succinea, and Scolecolepides viridis. None of these species represent larval or early life stage !
. forms of the representative important species (RIS) identified by the State of Maryland, or l l commercially or recreationally important species summarized in Table 2-3.
. Transitory exposure of estuarine zooplankton to the elevated temperatures of CCNPP entrainment ;
and discharge plumes was generally non-lethal. Transit time was estimated to be 4 minutes. i 1
. Entrainment survival of the above species was generally high, ranging from 65 to 100 percent. -
The conclusions were supported by the results of a study by Newman arid Sage (1981), who concluded thit the principal effect of entrainment appears to be " cropping," which is defined as a reduction in species density from intake to discharge. Cropping mortality was described as " minimal." Entrained l ;
' organisms either maintained their structural integrity and survived passage through the plant, or were l ~ fragmented from the mechanical and hydraulic shear forces and were lost. Zooplankton survival, d: fined as the percent of organisms surviving plant passage (number alive at discharge / number alive at intike) were similar to the study described above, with survival ranging from 12 to 100 percent, with a !
median aurvival of 55 percent for all species studied. Anecdotal evidence suggests that mortality is probably due in large part to the mechanical action of pissing through the cooling system rather than to short-term exposure to heated water, as laboratory i
- cxperiments conducted by ANSP suggest a tolerance range for most species above the upper limit set for cooling water. This information also suggests that survival rates were not consistent, but fluctuated ;
hourly, daily, and seasonally. The results of these studies suggest that the planktonic species entrained did not represent biologically, commercially, or recreationally important species. Entrainment of fish and shellfish in early life stages does not commonly occur, cropping rates are generally low, and survival, while variable, is generally NUREG-1437, Supplement 1 4-9. October 1999
EnvironmentalImpacts of Operation high. The larvae of the three species that are considered RIS by the State of Maryland: the blue crab, l Callinectes sapidus; the soft shell clam, Mya arenan'a; and the eastern oyster, Crassostrea virginica; are not susceptible to entrainment by the CCNPP cooling system because the intake is below the zone l in which these zooplankton generally occur. It is unlikely that there are management control procedures that would decrease the likelihood of entrainment of zooplankton based on plant design and ecological ar'd hydrodynamic features of this portion of Chesapeake Bay. The staff has reviewed the available information relative to potential impacts of the cooling water intake system on the site's entrainment of fish and shellfish in early life stages. Based on this review, the staff has concluded that the potential impacts are SMALL, and mitigation is not warranted. 4.1.2 Impingement of Fish and Shellfish Impingement of fish and shellfish into cooling water systems associated with nuclear power plants is considered a Category 2 issue, requiring a site-specific assessment before license renewal. l The staff reviewed the NPDES Permit, No. 92-DP-0187, along with a letter from the MDE stating that l the permit holder is currently in compliance with all conditions of the permit (MDE 1998b). A Federal l Water Pollution Control Act (FWPCA) 316(b) demonstration was conducted by the ANSP (1981) using l the annual studies conducted in 1977 through 1979. A 316(b) demonstration ensures the location, l design, construction, and capacity of cooling water intake structures reflect the best technology l available for minimizing adverse environmental impacts. This information, and subsequent studies and regulatory evaluations of plant operations have supported subsequent renewals of the NPDES permit. l Full, annualimpingement investigations were conducted during the first 21 years of plant operation l An early impingement study conducted by ANSP (ANSP 1981) determined the number of blue crabs and finfish impinged on the traveling screens at CCNPP, and estimated the value of the loss caused by l the impingement based on data from 1977,1978, and 1979. Impingement studies conducted by ANSP l for the years between 1975 to 1983 are compiled and summarized by Horowitz in Heck (1987). The results of these studies form the basis of the decision conceming the effects ofimpingement on important fish and shellfish populations surrounding the CCNPP. The importance of impingement is determined relative to the recreationally or commercially important species listed in Table 2-3. l During the ANSP (1981) 316(b) demonstration (and for a total of 21 years of continuous impingement l monitoring), a collecting net was placed in the screenwash discharge trough through which the l impinged individuals travel back to Chesapeake Bay. The sampling schedule was based on repeating l 6-day cycles to sample each hour of the day with equal frequency over a 365-day period. On each l sampling day, one-hour col!ections were made at each unit. Since data from earlier impingement l survival studies at the CCNPP (see ANSP 1981) had demonstrated greater than 99 percent survival of blue crabs and hogchokers (Trinectes maculatus), these species were not included in this study. October 1999 4-10 NUREG-1437, Supplement 1
Environm:ntalImpicts of Operation Survival data from Burton (1976) were also used to assess potential survival of impinged species and to l ' extrapolate the yearly death toll and subsequent economic loss. The conclusions of the study for the 3 study years were as follows: l l 1977: 43,959 finfish and blue crabs were collected during the study. l Yearly impingement estimates were 1,238,991 individuals. l An estimated 219,861 finfish and blue crabs were killed. Value of killed individuals: $23,453-1978: 50,359 finfish and blue crabs were collected during the study. l l Yearly impingement estimates were 1,576,264 individuals. l-An estimated 299,111 finfish and blue crabs were killed. Value of killed individuals: $23,274 1979: 67,736 finfish and blue crabs were collected during the study. l Yearly impingement estimates were 1,973,692 individuals. l ; An estimated 261,785 finfish and blue crabs were killed. l ! Value of killed individuals: $26,141 I l Thus for the 1977 through 1979 time frame, an annual average of 1,600,000 finfish and blue crabs were l collected on the traveling screens, of which 260,000 did not survive. The expected monetary loss l ; ettributed to the death of finfish and blue crabs due to impingement was $24,000 per year. l In rcsponse to the draft SEIS (February 1999), the MDNR Power Plant Assessment Division provided l cdditional data on the economic evaluation of monetary loss due to impingement at CCNPP (MDNR l 1999). In an attachment to the comment letter, MDNR provided summary tables estimating economic l , losses due to impingement for the years 1993,1994, and 1995. Table 4.3 is derived from these MDNR l l ttbles and summarizes the number of fish and other aquatic species impinged, their survival rate, the l total number killed, and the value of the losses. The estimated number of fish impinged as well as the l cstimated weights were obtained from the ANSP annual impingement studies (Hixon and Breitburg l
-1993,1994,1995). A summary of the information contained in the letter from MDNR to NRC dated May l l 19,1999 follows. I I
Following the methods described above, no value was estimated for species with survival rates greater j thin 99 percent after impingement (Callinectes sapidus and Trinectes maculatus). Because there were j no known survival estimates for three species (Morone americana, Morone saxitilis, and Cynoscion l regalis), the percent survival data presented in Table 4-3 was estimated to be the mean survival for l oth2r speces irnpinged for that year (78 percent for M. americana and M. saxatillis, 82 percent for C. l reg:lis. l 1 NUREG-1437, Supplement 1 4-11 October 1999
Environmental Impacts of Operation l The value column identified as being from MDNR expresses a valuation of individual species using the l AFS valuation factors (AFS 1992). The last column uses factors established in the Code of Maryland j Regulations (COMAR Tltle 08, COMAR Title 26) and an inflated dollar value (1993-1995) based on the l Consumer Price Index (CPI). When the COMAR value varied with the size of the fish, an estimate of l likely mean size was developed by comparing the approximate weight per fish (from estimated weight l and number of fish of each species per unit per year) to known size-weight relationships. The MD NR l believes that the assumptions in this valuation are conservative, thereby potentially overestimating the l value of fish killed each year. ) l Comparison of the 1993-1995 valuation with the 1977-1979 estimates contained in the draft SEIS l suggest that the draft SEIS may have overestimated the monetary value of impingement losses. The l average monetary loss for the years 1977-1979 was $24,289; average losses presented in Table 4-3 l (1993-1995) were $5746 and $8599, respectively. It is probable that management actions to decrease l impingement (described in later portions of this SEIS) contributed to the decrease in monetary losses l associated with this phenomena. l Additional impingement studies conducted by ANSP and summarized by Horowitz in Heck (1987) were performed by collecting fish and shellfish in a nylon net placed in the screen wash discharge troughs of l the CCNPP. One-hour collections were made on randomly selected days during three 8-hour periods l in 1975. The format became more structured after that and continued for 21 years. Experimental designs changed periodically in response to plant expansion to two online reactors, changes to the curtain wall surrounding the intake, and alterations to the traveling screens. During each study, numbers, species, weight, size, and physical condition of impinged individuals were noted. Sublethal effects, such as loss of equilibrium, were also noted, where appropriate. Estimates of variance in survival rate were calculated for species in which greater than 300 individuals were collected. The l number of potential episodes of impingement was estimated based on the number of fish or shellfish impinged per screen per hour. Impingement episodes at the species level were also compared to trawl data to determine if the species impinged on the traveling screens were indicative of the local population distribution, or whether CCNPP was selectively removing certain susceptible species. The results of the studies indicated that the impinged subset did not show the same degree of dominance and consistency in rank abundance as the trawl samples. This probably was reflective of a high variation in the rate of impingement. Much of the total impingement in a month or year occurred in occasional large impingement episodes of schools of one or only a few species. This suggests an episodic nature to impingement, not a constant removal of individuals over time. The particular schooling species varied with the season, environmental conditions, etc., leading to a greater variation j l l l l October 1999 4-12 NUREG-1437, Supplement 1
l Environm:ntalimpacts of Operation Table 4-3. Summary of 1993-1995 Fish Losses Through Impingement l Value of Value of Fish No. Fish % Total Fish Fish Killed Killed Species impinged Survival Killed (MDNR Est.) (COMAR Est.) ) 1993 1 Anchoa mitchilli 416,212 0.68 133,187.8 10,655.03 268.71 Brevoortia tyrannus 9165 0.52 4399.2 197.94 1183.38 Callinectes sapidus 659,220 0.99 NE* - - Gobiesox strumosus 2712 0.93 189.8 15.19 0.38 Leiostomus xanthurus 8674' O.84 1388.3 5.19 448.15 Menidia spp. 18,915 0.54 8700.9 696.07 17.55 Micropogonias undulatus 49,457 0.19 40,060.2 15.82 16,164.28 Syngnathus fuscus 14,215 0.85 2132.3 170.58 4.30 Trinectes maculatus 186,982 0.99 NE - - TOTAL VALUE OF 1993 FISH KILL 11755.62 18086.75 1994 Alosa aestivalis 36,486 0.47 19,549.6 88.81 5376.13 Anchoa mitchilli 21,355 0.68 6833.6 546.69 14.09 Callinectes sapidus 547,626 0.99 NE - - Gasterosteus aculeatus 3606 0.91 324.5 25.96 0.67 Leiostomus xanthurus 10,122 0.84 1619.5 .28.43 534.44 Menidia spp. 14,450 0.54 6647.0 531.70 13.79 Morone americana 2463 0.78 532.6 3.93 219.71 Morone saxatilis 1770 0.78 382.8 45.84 789.45 Syngnathus fuscus 7427 0.85 1114.1 89.12 2.30 Trinectes maculatus 39,415 0.99 NE - - TOTAL VALUE OF 1994 FISH KILL 1271.74 6950.50 1995 Alosa aestivalis 4042 0.47 2142.3 11.62 606.28 Anchoa mitchilli 15,2331 0.58 48,745.9 3899.67 103.46 Callinectes sapidus 1,441,239 0.99 NE - - Cynoscion regalis 5088 0.82 908.6 3.42 542.81 Gobiesox strumosus 3708 0.93 259.6 20.76 0.55 Menidia spp. 13,368 0.84 2138.9 171.11 4.54 Syngnathus fuscus 8611 0.85 1291.7 103.33 2.74 Trinectes maculatus 16,866 0.99 NE - - TOTAL VALUE OF 1995 FISH KILL 4209.91 1360.37
- no estimate NUREG-1437, Supplement 1 4-13 October 1999 I
l.
Environm:ntrlImp:: cts of Operation in the overall catch. The most common species in the impingement samples are listed as follows: Anchoa mitchilli, the bay anchovy Leiostomus xanthurus, the spot Trinectes maculatus, the hogchoker l Brevoortia tyrannus, the Atlantic menhaden Micropogonias undulatus, the croaker Although several of the same species were dominant in both impingement and trawl samples, the impingement samples contained greater numbers of hogchokers, menhaden, and other species. Survival studies showed high survival utes for flounders, cyprinodontids, gobies, and blennies. Herring, anchovies, and silversides typically showed intermediate rates of survival, and perciforms showed variable, but generally low survival after coming in contact with the traveling screens. The blue crab was often impinged on the traveling screens of CCNPP. ANSP has estimated that a total of 5.25 million crabs were impinged on the traveling screens of CCNPP from 1975 to 1982, with annual estimates ranging from 293,000 to over 1.6 million. This correlated well with the annual number of l crabs ANSP caught in pots at various locations in the Bay. Experiments showed that impingement survival of blue crabs exceeded 99 percent (Burton 1976), suggesting that impingement probably has little effect on the total population density of crabs in the area of CCNPP. BGE provided a comprehensive summary of impingement investigations at the CCNPP from 1975-1995 (BGE 1998b). In this report, detailed information is presented that summarizes the number of species and individuals impinged on the traveling screens each year, and estimates mortality based on previous , l study results. In addition to 21 annualimpingement surveys, three studies are discussed: The FWPCA Section 316 Study (ANSP 1981), Ecological Studies in the Middle Reach of the Chesapeake Bay l (Horowitz in Heck 1987), and a 1989 Trends reports developed by ANSP. The results of the BGE report suggest that some impingement episodes may occur due to stressful environmental conditions in the Bay caused by natural phenomena. During these stressful conditions, large numbers of finfish may become debilitated and subsequently impinged on the traveling screens. Plant modifications, including curtain wall panel removal at critical times, have enabled fish to escape the intake area and follow an j oxygen gradient out of the area. BGE presents the following quote from the 1982-1986 ANSP report that summarizes one of their conclusions concerning impingement: Most abundant species were impinged in significantly larger numbers during some years than during others. However, peak years of commercial catches and peak years of impingement did not coincide for any of the abundant species for which commercial catch data are available. Instead, large impingements often resulted from fish kills associated with low dissolved oxygen concentrations. October 1999 4-14 NUREG-1437, Supplement 1
Environm:ntalImp: cts of Operation Tha results of these studies suggest the following: l e Mortality due to impingement is species-dependent: blue crabs, flounders, cyprir odontids, gobies and biennies exhibit high survival after impingement; herring, anchovies, and silversides exhibit intermediate survival; and perciform fish generally do not survive impingement.
. . Losses of finfish and blue crabs to impingement represent only about 0.1 percent of commercial l lindings. If recreational landings of fish and shellfish are included, the impingement losses tssociated with the CCNPP represent approximately 0.05 percent of the total take from this area of
! the Chesapeake Bay. l
- Management actions to reduce impingement have been ongoing since plant construction and have included modification of the intake curtains (including panel removal during episodes of low dissolved oxygen in intake water), traveling screen configuration, and discharge trough design.
. ' Yearly economic losses due to impingement, even after conversion to 1998 dollars, appear to be only a very small fraction of the total vaiue of the resource to commercial and recreational entities. l
. Excessive impingement events appear to be correlated with stressful environmental conditions that are not attributable to CCNPP operations. Warm weather, a thermally stratified bay, and prolonged l west or southwest winds may create low dissolved-oxygen conditions near the plant that debilitate finfish and make impingement more likely.
As described above, the staff has reviewed the available information relative to potentialimpacts of the l L cooling water intake system on the impingement of fish and shellfish, and concludes that the potential imptets are SMALL, and mitigation is not warranted. i [
\
4.1.3 Heat Shock l The cffects of heat shock are listed as a Category 2 issue and require plant-specific evaluation before license renewal. A copy of the NPDES permit, No. 92-DP-0187, along with a letter from the MDE, affirms that the permit l l hold:r is currently in compliance with all conditions of the permit. A 316(a) demonstration (FWPCA) l was conducted'by the ANSP (1981). This information, and subsequent studies and regulatory cvaluations of plant operations, have supported subsequent renewals of the NPDES permit. The staff l
. sytluated the following information:
. a description of the condenser cooling system; its configuration determines which permits must be ccquired, and the potential severity of impacts on particular aquatic organisms or systems
- NUREG-1437 Supplement 1 4-15 October 1999 I'
l Environm:ntalimpacts of Operr. tion
. a temperature-duration-mortality relationship and susceptibility of "important" local species to heat l shock
. estimates of the regional standing stocks for those "important" species potentially affected by cooling system discharge operation
'l . a description of applicable State and Federal (40 CFR Part 423) effluent guidelines and the thermal standards or limitations applicable to the water body to which the discharge is made (including maximum permissible temperature, maximum permissible temperature increase, mixing zones, and maximum rates of increase and decrease), and whether and to what extent these standards or
-l limitations have been approved by the Administrator of the EPA in accordance with the Federal l Water Pollution Control Act, as amended.
The potential effects of heat shock associated with the cooling water discharge from the CCNPP can
' best be determined by understanding the behavior of the thermal plume as it leaves the discharge and l enters the Chesapeake Bay. Bay water enters the CCNPP through the intake channel, and transits through the plant in approximately 4 min, with a resulting maximum allowed temperature change (AT) of l 6.7'C (12*F). After passing through the condensers, the warm effluent is discharged through four l ' 4 x 4 m (12.5 x 12.5 ft), concrete conduits (two for each unit) which rest on the bay bottom. Water is discharged along the 3-m (10-ft) depth contour at 2.7 m/s (700 gal /s) from the conduit system, which is located 260 m (850 ft) offshore (Holland et al.1984).
A number of studies have been conducted to determine plume dimensions and compare the results to the State of Maryland Water Quality Standards (Martin Marietta 1976a, b; ANSP 1980). An overall compilation of studies of plume characteristics may also be found in Ecological Studies in the Middle l ' Reach of Chesapeake Bay, Lecture Notes on Coastal and Estuarine Studies (Heck 1987). These studies represent the most complete analyses of the thermal plume associated with the CCNPP activities to date. l Early studies were conducted to determine plume characteristics during one- and two-unit operation,
' determine relative current speed and direction during tidal cycles via current meters, and determine both near- and far-field effects under varying plant loads. Dye studies were also employed to better understand the dispersive characteristics of the plume. Extensive studies were performed on plume characteristics in 1979, concluding that for a condenser temperature rise of 6.7'C (12*F), the CCNPP full-load plume would comply with all mixing zone requirements for discharges to tidal waters. Further, these studies estimated the area in which the temperature rise exceeded 2*C (3.6*F) at 0.15 km 2 (0.06 mi2) based on a condenser temperature rise of 6.7'C (12*F). These data suggest that under .
most conditions, thermal shock is not expected to occur, based on a target organism's ability to withstand episodic temperature changes of 2*C (3.6*F) or less. i October 1999 4-16 NUREG-1437, Supplement 1
Environmsntal Impacts of Operation L Summary information provided in Heck (1987) suggested the following findings conceming the relative l Aff: cts of the thermal plume associated with cooling water from the CCNPP discharge:
- With a maximum temperature increase of 6.7'C (12*F),9100 m (2.4 million gallons) of water pass through the condensers each minute and transfer a tremendous amount of waste heat into the Bay.
However, dilution is great, mixing is rapid, and the thermal plume is confined to a relatively small trea.
* ' The area in which the temperature rise exceeds 2*C (3.6*F) is estimated to be 0.34 km2 (0.13 mir);
the area in which the temperature rise exceeds 1 *C (1.3*F) is estimated to be 1.00 km2 (0.4 mi2), l E. Three RIS have been identified that may be influenced by the thermal plume created by the CCNPP: the eastern oyster, the soft-shell clam, and the blue crab.
- The eastem oyster is the most important resource that uses the area near the CCNPP for breeding :
I end as a nursery. Entrainment studies by Olson and Sage (1979) and Newman and Sage (1981) showed no entrainment of oyster larvae in the plume. Once oysters have set, they show increased ; growth from the elevated temperature near the CCNPP, based on data from planting efforts conducted by MDNR (Abbe 1988,1992).
'. The soft shell clam has not occurred in sufficient numbers near the CCNPP to support commercial harvesting. The low population densities occurred long before plant operation began in 1975 and appear to be related to the physical and hydrodynamic characteristics of the Chesapeake Bay, l predation, and other factors.
- There is little thermal impact on juvenile and adult crabs, and essentially no effect on larvae, since they are not found in the area.
. Many finfish are found in the area on a seasonal basis or move through the area during spawning runs, but the commercially and recreationally valuable species such as striped bass, weakfish, bluefish, spot, croaker, flounder, or herring do not spawn in the area. Their larvae, therefore, are not susceptible to thermal effects. Since the area of increased temperature is small, it does not block established migratory fish routes.
. .The thermal plume does not support large numbers of overwintering species; therefore, abrupt changes in plant operation are not expected to create adverse conditions for endemic species.
The results of these studies suggest t' hat heat shock and other adverse effects associated with cooling witsr discharge from the CCNPP present little risk of long-term environmental damage. Pursuant to 10 l CFR 51.53(c)(3)(ii)(B), no further assessment of heat shock is required. Therefore, the staff concludes l NUREG-1437, Supplement 1 4-17 October 1999
Environm::ntal Imp; cts of Operation that potential heat shock impacts resulting from operation of the plant's cooling water discharge system to the aquatic environment or in the vicinity of the site are SMALL, and mitigation is not warranted. 4.2 Transmission Lines The CCNPP power transmission system is divided into a North and a South Circuit. The land beneath the lines, about 105 km (65 mi) of 100 to 125-m (350- to 400-ft) wide rights-of-way, is owned by BGE. The lines cross mostly second-growth hardwood and pine forests, pasture, and farmland. The plant is connected to the Southern Maryland Electric Cooperative's substation via a 69-kV underground transmission line. - l. Category 1 issues in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, that are applicable to CCNPP
~
transmission lines are listed in Table 4-4. BGE stated in its ER that it is unaware of any new and significant information related to these Category 1 issues. No significant new information has been identified by the staff in the review process and in the staff's independent review. Therefore, the staff concludes that there are no impacts related to these issues beyond those discussed in the GEIS. For all of those issues, the GEIS concluded that the impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. A brief description of the staff's review and the GEIS conclusions, as codified in Table B-1, for each of these issues follows.
. Power line rioht-of-way manaaement (cuttina and herbicide aoolication): Based on information in
-l the GEIS, the Commission found that "The impacts of right-of-way maintenance on wildlife are expected to be of small significance at all sites." The staff has not identified any significant new l information during its independent review of the BGE ER, the staff's site visit, the scoping process, consultation with MDNR, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of power line right-of-way management during the renewal term beyond those discussed in the GEIS. -l . Bird collision with power lines: Based on information in the GEIS, the Commission found that
" Impacts (of bird collisions with power lines] are expected to be of small significance at all sites."
-l The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information, including the status of the BGE monitoring program, BGE efforts to document collisions, and BGE efforts to, protect species nesting on the power lines. Therefore, the staff concludes that there are no impacts of bird collisions with Nwer lines durir.g the renewal term beyond those discussed in the GEIS. I October 1999 - 4-18 NUREG-1437, Supplement 1
I EnvironmentalImpacts of Operation l l e Impacts of electromaanetic fields on flora and fauna (plants. aaricultural croos. honeybees. wildlife, livestock): Based on information in the GEIS, the Commission found that "No significant impacts of l electromagnetic fields on terrestrial flora and fauna have been identified. Such effects are not expected to be a problem during the license renewal term." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the l scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of electromagnetic fields on flora and fauna during the renewal term beyond those discussed in the GEIS.
- Floodplains and wetland on oower line riaht of way: Based on information in the GEIS, the l.
Commission found that " Periodic vegetation control is necessary in forested wetlands underneath l power lines and can be achieved with minimal damage to the wetland. No significant impact is expected at any nuclear power plant during the license renewal term." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, l the scoping process, consultation with MDNR, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts on floodplains and wetland on power line right-of-way during the renewal term beyond those discussed in the GEIS. Table 4-4. Category 1 issues Applicable to the CCNPP Transmission Lines During the Renewal Term l lSSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Sections l TERRESTRIAL RESOURCES Power line right-of-way management (cutting and herbicide application) 4.5.6.1 Bird collisions with power lines 4.5.6.2 Impacts of electromagnetic fields on flora and fauna (plants, agricultural 4.5.6.3 crops, honeybees, wildlife, livestock) Floodplains and wetland on power line right-of-way 4.5.7 AIR QUALITY Air quality effects of transmission lines 4.5.2 LAND UsE Onsite land use 4.5.3 l Power line right-of-way 4.5.3 NUREG-1437, Supplement 1 4-19 October 1999
Environm:ntal Impacts of Operation
. Air auality effects of transmissien i:nes: Based on information in the GEIS, the Commission found l that " Production of ozone and cxides of nitrogen is insignificant and does not contribute measurably l l to ambient levels of these gases." The staff has not identified any significant new information during l its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public l comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no air quality impacts of transmission lines during the renewal term beyond those discussed in the GEIS.
l . Onsite land use: Based on information in the GEIS, the Commission found that " Projected onsite l land use changes required during . . the renewal period would be a small fraction of any nuclear l power plant site and would involve land that is controlled by the applicant." The staff has not l identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its eva;uation of l other available information. Therefore, the staff concludes that there are no onsite land use impacts l during the renewal term beyond those discussed in the GEIS. l . Power line richt of way and land use: Based on information in the GEIS, the Commission found that l " Ongoing use of power line right of ways would continue with no change in restrictions. The effects of these restrictions are of small significance." The staff has not identified any significant new l information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other avelable information. Therefore, the staff concludes that there are no impacts of restriction on use of power line rights-of-way during the renewal term beyond those discussed in the GEIS. There is one Category 2 issue related to transmission lines and another issue related to transmission lines that is being treated as a Category 2 issue. These issues are listed in Table 4-5. They are discussed n Sections 4.2.1 and 4.2.2. 4.2.1 Electromagnetic Fields-Acute Effects , l The GEIS analysis for electric shock from transmission lines was unable to reach a conclusion on the significance of the electric shock potential because for earlier licensed plants, electric shock was not addressed, some plants may have chosen to upgrade the voltage line, and land use may have l changed. To comply with 10 CFR 51.53(c)(3)(ii)(H), the applicant must provide an assessment of the l potential shock hazard if the transmission lines that were constructed for the specific purpose of . connecting the plant to the transmission system do not meet the recommendations of the National ) l Electric Safety Code (NESC) for preventing electric shock from induced currents. i l In the ER, BGE stated that the South Circuit was designed to be in compliance with the NESC for j electrical shock potential. Calculations of steady-state current for the largest vehicle anticipated under ] the lines result in less than the 5-milliampere (mA) code limit. The North Circuit lines were installed October 1999 4-20 NUREG-1437, Supplement 1
Environmental Impacts of Operation before the NESC was adopted. However, calculations of steady-state current for the largest vehicle l anticipated under the northern lines results in less than the 5-mA code limit. BGE, therefore, concludes (BGE 1998a) that the North Circuit also_ meets the NESC recommendations for preventing electric j shock from induced currents. Table 4-5. Category 2 issues Applicable to the CCNPP Transmission Lines During the Renewal Term i 10 CFR ISSUE-10 CFR Part 51, Subpart A, GEIS 51.53(c)(3)(ii) SEIS l Appendix B, Table B-1 Sections subparagraph Sections HUMAN HEALTH Electromagnetic fields, acute effects (electric shock) 4.5.4.1 H 4.2.1 Electromagnetic fields, chronic effects 4.5.4.2 NA 4.2.2 Based on the above, the staff concludes that the impact of the potential for electrical shock is SMALL cnd mitigation is not warranted. 4.2.2 Electromagnetic Fields-Chronic Effects in the GEIS, the chronic effects of electromagnetic fields from power lines were given a finding of "not l cpplicable" rather than a Category 1 or 2 designation until a scientific consensus is reached on the hsalth implications of these fields. Th3 potential for chronic effects from these fields continues to be studied and is not known at this time. l Tha National Institute of Environmental Health Sciences (NIEHS) directs related research through the U.S. Department of Energy (DOE). A recent report (NIEHS 1999) includes the following paragraph: l l The NIEHS concludes that ELF-EMF (extremely low frequency-electromagnetic field) exposure l cannot be recognized as entirely safe because of weak scientific evidence that exposure may pose l a leukemia hazard. In our opinion, this finding is insufficient to warrant aggressive regulatory l concern. However, because virtually everyone in tne United States uses electricity and therefore is l routinely exposed to ELF-EMF, passive regulatory action is warranted such as a coritinued l emphasis on educating both the public and the regulated community on means aimed at reducing l exposures. The NIEHS does not believe that other cancers or non-cancer health outcomes provide l sufficient evidence of a risk to currently warrant concern. l l l 1 NUREG-1437, Supplement 1 4-21 October 1999 L
Environm:nici Impccts of Operction l This statement is not sufficient to cause ths :taff to change its position with respect to the chro.nic l effects of electromagnetic fields. The staff considers the GEIS finding of "not applicable" still l appropriate and will c emue to follow developments on this issue. 4.3 Radiologicalimpacts of Normal Operations Category 1 issues in 10 CFR 51, Subpart A, Appendix B, Table B-1, that are applicable to CCNPP with regard to radiological impacts are listed in Table 4-6. BGE stated in its ER that it is unaware of any new and significant information related to these Category 1 issues. No significant new information has been identified by the staff in the review process and in the staff's independent review. Therefore, the staff concludes that there are no impacts related to these issues beyond those discussed in the GEIS. For all of those issues, the GEIS concluded that the impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. l Table 4-6. Category 1 Issues App'k " to Radiological impacts of Normal Operations l During the Renewc ' .Tn l ISSUE-10 CFR Part 51, h e adix B, Table B-1 GEIS Sections
.JMAN HEALTH Radiation exposures to public (license renewal team) 4.6.2 Occupational' radiation exposures (license renewal term) 4.6.3 A brief description of the staff's review and the GEIS conclusions, as codified in Table B-1, for each of these issues follows.
l
- Radiation exposures to oublic (license renewal term): Based on information in the GEIS, the l Commission found that " Radiation doses to the public will continue at current levels associated with l normal operations." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's si'a Vsit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff l concludes that there are no impacts of radiation exposures to the public during the renewal term
{ beyond th ise discussed in the GEIS. 1
. Occupational radiation exposures (license ren uai term): Cased on information in the GEIS, the l Commis&n found that " Projected maximum occupational doses during the license renewal term are within the range of doses experienced during normal operations and normal maintenance outages, and would be well below regulatory limits." The staff has not identified any significant new I information during its independent review of the BGE ER, the staff's site visit, the scoping process, j October 1999 4-22 NUREG-1437, Supplement 1
_ _ _ - - - _ - - - - - - - - - - - - - _ - - - - - - - - - - - _ . - - - - - . - - - - - - - - _ - - - - - - _ - _ l
Environm:ntclImp: cts of Operction its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of occupational radiation exposures during the renewal term beyond those discussed in the GEIS. 4.4 Socioeconomic impacts of Plant Operations During the License Renewal Period Category 1 issues in 10 CFR 51, Subpart A, Appendix B, Tsble B-1, that are applicable to socioeconomic impacts during the renewal term are listed in Table 4-7. BGE stated in its ER that it is unaware of any new and significant information related to these Category 1 issues. No significant new information has been identified by the staff in the review process and in the staff's independent review. Therefore, the staff concludes that there are no impacts related to these issues beyond those discussed in the GEIS. For all of those issues, the GEIS concluded that the impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. Table 4-7. Category 1 issues Applicable to Socioeconomics During the Renewal Term l lSSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Sections l SoCloECoNoMICs Public services: public safety, social services, and tourism and 4.7.3; 4.7.3.3; 4.7.3.4; 4.7.3.6 recreation Public services: education (license renewal term) 4.7.3.1 Aesthetic impacts (license renewal term) 4.7.6 Aesthetic irrweis of transmission lines (license renewal term) 4.5.8 A brief description of the staffs review and the GEIS conclusions, as codified in Table B-1, for each of these issues follows.
- Public services: oublic safety. social services. and tourism and recreation: Based on information in the GEIS, the Commission found that " Impacts to public safety, social services, and tourism and l recreation are expected to be of small significance at all sites." The staff has not identified any significant new information during its independent review of the BGE ER, the staffs site visit, the l scoping process or public comments on the draft SEIS , its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts on public safety, social services, and tourism and recreation during the renewal term beyond those discussed in the GEIS.
NUREG-1437, Supplement 1 4-23 October 1999 l
Environm:ntal Impacts of Op: ration l l l
. Public services: education (license renewal term): Based on information in the GEIS, the l Commission found that "Only impacts of small significance are expected." The staff has not identified any significant new information in its review of the BGE ER or through the site visit, the l scoping process or public comments on the draft SEIS, and independent evaluation of available information. Therefore, the staff concludes that there are no impacts on education during the renewal term beyond those discussed in the GEIS.
. Aesthetic imoacts (license renewal term): Based on information in the GEIS, the Commission found l that "No significant impacts are expected during the license renewal term." The staff has not l identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, tne staff concludes that there are no aesthetic impacts during the renewal term beyond those discussed in the GEIS.
. Aesthetic impacts of transmission lines (license renewal term): Based on information in the GEIS, l the Commission found that "No significant impacts are expected during the license renewal term."
l The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no aesthetic impacts of transmission lines during the renewal term beyond those discussed in the GEIS. Table 4-8 lists the Categorv 2 socioeconomic issues, which require plant-specific analysis, and l environmental justice, which was not addressed in the GEIS.) 4.4.1 Housing impacts During Operations in determining housing impacts, BGE chose to follow Appendix C of the GEIS, which presents a population characterization method that is based on two factors, " sparseness" and " proximity" (GEIS l Section C.1.4). Sparseness measures population density and city size within 32 km (20 mi) of the site, while proximity measures population density and city size within 80 km (50 mi). Each factor has l categories of density and size (GEIS Table C.1), and a matrix is used to rank the population category as low, medium, or high (GEIS Figure C.1). CCNPP was selected by the NRC to be evaluated as a l potential socioeconomic case study site. The results of this evaluation, published in the GEIS, classifies the CCNPP population as "high" (GEIS Table C.2). Using the demographic data given in Section 2.2.8, the population density within a 32-km (20-mi) radius of CCNPP is 42 persons /km 2109 persons /mi2), l giving a sparseness Category of 3. The population density within an 80-km (50-mi) radius is 152 persons /km2 (393 persons /mi2), giving the site a proximity Category 4. These values combine to give l (a) The GEIS was originally issued in 1996. Addendum 1 to the GEIS was issued in 1999. All l references to the "GEIS" include the GEIS and its Addendum 1. October 1999 4-24 NUREG-1437, Supplement 1
)
Environm::ntalImp cts of Operation the CCNPP population a category measure of 4.3, within the "high" category, consistent with the GEIS chIracterization. Moreover, forecasted growth in the region from 1998 to 2040 due to causes other thin CCNPP is likely to make the population rating continue to increase. Table 4-8. Category 2 Issues Applicable to Socioeconomics During the Renewal Term l 10 CFR ISSUE-10 CFR Part 51, Subpart A, 51.53(c)(3)(ii) l Appendix B, Table B-1 GEIS Sections subparagraph SEIS Section SOClOECONOMICs Housing impacts 4.7.1 1 4.4.1 Public services: public utilities 4.7.3.5 1 4.4.2 Offsite land use (license renewal term) 4.7.4 1 4.4,3 Public Services, transportation 4.7.3.2 J 4.4.4 l Historic and archaeological resources 4.7.7 K 4.4.5 ENVIRONMENTAL Justice Environmental Justice Not addressed 4.4.6 l I As described in Section 2.2.8, the Tri-County (Calvert, St. Mary's, and Charles) area around CCNPP is not subject to growth control measures that effectively limit housing development, although Calvert County is attempting to steer the growth toward particular locations to preserve the County's rural l l chiracter. The County is also buying development rights to some lands to preserve open space. In i 10 CFR Part 51, Subpart A, Appendix B, Table B-1, NRC found that impacts to housing are expected to be of small significance at plants located in a "high" population area where growth control measures are i not in effect. The applicant states that because CCNPP is located in a high population area and is not I located in an area where growth control measures limit housing development, housing impacts are ; expected to be SMALL. Smill impacts result when no discemable change in housing availability occurs, changes in rentsj rates end housing values are similar to those occurring statewide, and no housing construction or conversion occurs. Although significant housing impacts are expected in all three counties as a result of population , growth, it will be difficult to discern the impact of the additional population that would move to the area l es a result of CCNPP operations during the license renewal period. BGE does not expect to hire l cdditional employees for license renewal, but used the bounding estimate in the GEIS of 60 new l cmployees as the basis for analyzing a bounding case scenario. The maximum impact to area housing l wrs calculated by SGE using the following assumptions: (1) all direct and indirect jobs would be filled NUREG-1437, Supplement 1 4-25 October 1999
Environm:ntalImp cts of Operation by in-migrating residents; (2) the residential distribution of new residents would be similar to the current worker distribution; (3) each new job (direct and indirect) represents one housing unit. As described in l I Section 2.2.8 of this report, the counties that have the most CCNPP workers are Calvert St. Mary's, l and Charles, which, together, account for approximately 93 percent of CCNPP employees. Were the l applicant's maximum impact assumptions to hold true, BGE's bounding estimate of 60 license renewal l employees could generate demand for as many as 223 housing units (60 employees Maryland employment multiplier of 3.997 x 93%). However, the 81,000 housing units in the three counties and a vacancy rate of 7 percent (Tri-County Council for Southem Maryland 1993) together give about 5700 units currently available for occupancy. Although it would add a small amount to any future cumulative l impact on housing from general population change, a decrease in availability of 4 percent (223 units) is not expected on its own to have a discemable effect on housing availability, rental rates, or housing l prices, or to spur housing construction or conversion. The staff reviewed the available information l relative to housing impacts. Based on this review, the staff has concluded that the impact on housing during the license renewal period is SMALL,'and mitigation is not warranted. 4.4.2 Public Services: Public Utility impacts During Operations impacts on public utility services are considered small if little or no change occurs in the ability of the system to respond to the level of demand and, thus, there is no need to add capital facilities, impacts are considered moderate if overtaxing of capacity occurs during periods of peak demand. Impacts are considered large if existing levels of service (e.g., such as water or sewer services) are substantially degraded and additional capacity is needed to meet ongoing demands for services. The GEIS indicates that, absent any new and significant information to the contrary, the only impacts on public utilities that could be significant are impacts on public water supplies. BGE's analysis of new and existing information on public services showed no reason to expect impacts on public services other than water supply. In view of the expected population increase in the three counties, especially Calvert County, there may be reason to add significant public services and infrastructure other than water supply during the next 40 years. However, only a very small fraction of the increase would be due to the impact of a maximum of 60 additional CCNPP workers on the area's population. Analysis of impacts to the public water supply system considered both plant demand and plant-related population growth on local groundwater resources. Section 2.2.2 describes the plant's permitted withdrawal rate and the plant's actual use of groundivater from the Aquia Aquifer for process and domestic uses. Section 4.5.1 presents an analysis of groundwater use conflicts. As described in Section 2.2.8 of this report, the Solomons Island and Lexington Park areas are starting to experience water supply problems. Therefore, BGE focused its water supply analysis on these two l l areas. The estimate of a maximum of 60 additional plant employees could generate a population l increase of up to 643 people in Calvert and St. Mary's Counties (based on 89% the population increase locating in these two counties, a Maryland employment multiplier of 3.997, and an average household size in Maryland of 3.01). To analyze the impact on the water supply situation in Solomons October 1999 4-26 NUREG-1437, Supplement 1 l
r Environmentalimpacts of Operation l I islind/Lexington Park, only the portion of the population increase expected in those two communities should be considered. The current population distribution of the two' counties indicates that about 9 percent of the total population lives in Solomons or Lexington Park communities. (Mitchell and P penfuse 1994; Calvert County Department of Economic Development 1994). Assuming that the sim3 percentage of plant-related population growth would live in this area, a population increase of cbout 58 people could be expected in Solomons/Lexington Park as a result of the renewal of the l CCNPP operating licenses (9 percent of 643). l Th3 incremental impact to the local water supply systems can be determined by calculating the amount of water that would be needed by these additional residents. The average American uses between 200-300 liters per day (Ud) (50 and 80 gallons per day [gpd]) of water for personal use (Fetter 1988). l At this consumption rate, the plant-related population increase would use between 11,000 and 17,600 l cdditional Ud (2900 to 4640 gpd) of water. The Solomons Water Supply system has an average output l of 850,000 Ud (225,000 gpd) of water, and the Lexington Park Water Supply system an average output l of 4,500,000 L (1,203,000 gal), for a total of approximately 5,300,000 L (1,400,000 gal). An additional l 58 rcsidents, drawing an additional 17,600 Ud (4640 gpd), represents less than 1 percent of current l drily output. While expected additional population growth in the next 40 years may double the current population of Calvert and St. Mary's Counties and place significantly greater demands on the groundwater resources (perhaps as much as doubling those demands as well), the impact of plant-r:lited population, while contributing a small portion of this cumulative impact, would be an even smaller portion of the future withdrawal rate, requiring no additional capacity. The staff concludes that tha impact on water supply is SMALL, and that mitigation is not warrante:;L 4.4.3 Offsite Land Use During Operations Land use in the vicinity of a nuclear power plant may change as a result of plant-related population growth.10 CFR Part 51, Subpart A, Appendix B, Table B-1 notes that significant changes in land use m:y be associated with population and tax revenue changes resulting from license renewal. However, S ction 3.7.5 of the GEIS notes that if the plant-related increase in population is less than 5 percent of the study area's total population and if plant total tax payments are small relative to the community's tot:1 revenue, then new tax-driven land-use changes during the plant's license renewal term would be small, especially where the community has pre-established patterns of development and has provided cdequate public services to support and guide development. Th3 cnalysis of offsite land use during the renewal term has two components: population-driven changes in offsite land use, and tax-driven changes in offsite land use. New population-driven changes in 1:nd use during the license renewal term would be small because the projected plant-related population increase is expected to be far less than 1 percent of the current population and is not even a l significant portion of the projected population increase for the study area. Calvert County, which is I expected to experience a plant-related population increase of 502 (based on 69% of the increase in l Calv:rt County alone), would see a less than 1 percent increase in population as a result of license l NUREG-1437, Supplement 1 4-27 October 1999
j I EnvironmsntalImpacts of Operation renewal. Because Calvert County continues to experience high population growth, conversion of agricultural land to residential and commercial uses is likely to continue. However, only a very sni'all fraction (less than 1 percent) of this conversion would be attributable to plant-related population growth. Calvert County is the principal jurisdiction that receives direct tax revenue as a result CCNPP's presence. Because there are no major refurbishment activities and no new construction as a result of license renewal, no new tax payments are expected that could significantly influence land use in Calvert County. However, continued operation of the plant would provide a significant continuing source of tax l revenues to Calvert County. The Final Environmental Statement (FES) related to operations of CCNPP, Section XI.C.1, written by the U.S. Atomic Energy Commission (AEC 1973), estimated that CCNPP would generate $6.5 million annually in county tax revenues, which in 1973 would have represented more than 50 percent of county tax revenue. Using the gross national product implicit price deflators, this would be equivalent to about $20.7 million in 199^ dollars. As shown in Table 4-9, BGE actually paid about $17 million in property taxes to Calvert County in 1994-95, and over $20 million in 1997-98. This payment represented about 21 percent of the county budget and has a substantial, positive impact on the fiscal condition of Calvert County. The applicant estimates that property tax l payments will continue to rise over the license renewal term, reaching approximately $33 million per l year by 2036. l Table 4-9. Calvert County Property Taxes Paid on CCNPP, Selected Years, 1972-1998 Year County Assessment County Revenue 1972-73 $2,736,910 $75,812 1975-76 $267,627,440 $6,824,500 1980-81 $540,090,510 $10,801,810 1985-86 $595,383,600 $11,669,519 1990-91 $631,439,790 $14,081,107 1991-92 $617,390,610 $13,767,811 1992-93 $676,243,340 $15,080,226 1993-94 $690,958,680 $15,408,379 1994-95 $769,330,630 $17,156,073 1995-96 $778,004,610 $17,439,503 1996-97 $877,027,270 $19,557,708 1997-98 $923,819,910 $20,601,184 Source: Data supplied by Calvert County Finance Department October 1999 4-28 NUREG-1437, Supplement 1 j
Environmental Impacts of Operation The staff has determined that the significance of project-related tax payments are moderate if the p:yments to a jurisdiction are between 10 and 20 percent of the total tax revenue of the jurisdiction, and large if the percentage is greater than 20 percent (GEIS). If the tax-related revenues are medium to large relative to the jurisdiction's total revenue, tax-driven land-use changes would most likely be moderate if the community has no pre-established pattems of development (i.e., land use plans or controls), or has not provided adequate public services to guide land-use changes in the past (GEIS). Tho staff defined magnitude of land-use changes as follows: l
. SMALL-Very little new development and minimal changes to the area's land-use pattern. l . MODERATE-Considerable new development and some changes to land-use patterns. . LARGE-Large-scale new development and many changes to land-use pattems.
Using these criteria, CCNPP tax payments, representing around 21 percent of the total Calvert County l budget, are of moderate to large significance. The County also has experienced significant population l growth and moderate to large land-use changes. The growth is not directly related to the presence of ths CCNPP. Other factors such as proximity to Washington, D.C., and Baltimore, Maryland; less d3velopment and lower taxes than those areas; and less stringent land-use, zoning, and development regulations, compared to surrounding counties, clearly play a role. The County has well-established pattems of development due to an established comprehensive plan, including actions by the County to protect open space, and has public services in place to support development, which is being directed toward town centers. In combination, these two factors would be expected to result in SMALL land-use impacts from CCNPP-related taxes. Continuation of Calvert County's tax receipts from CCNPP as a result of license renewal has two offsetting effects on offsite land use. On the one hand, the presence of this major industrial taxpayer knps tax rates below what they otherwise would have to be to fund the County's govemment, and also provides for a higher level of public infrastructure and services than otherwise would be possible. This enhances the county's attractiveness as a place to live and tends to accelerate the conversion of open sp;ce to residential and commercial uses. On the other hand, the availability of CCNPP taxes makes it possible for the County to conduct an aggressive program to preserva open space by buying open-land d:velopment rights, which are then retired. Calvert County also cbtains an indirect monetary benefit from the CCNPP tax base, which helps keep property tax rates low and may add slightly to land conversion due to population growth. Due, in part, to th2 presence of such a large, stable source of tax income, Calvert County enjoys an AAA bond rating, l ons of the highest ratings of any jurisdiction in the state (League of Women Voters of Calvert County 1994). This bond rating indicates that there is minimal risk that Calvert County will default in its timely payment of interest and principal, and it affords the county lower interest rates on borrowed funds. NUREG-1437, Supplement 1 4-29 October 1999 i
Environm::ntilImpacts of Operation License renewal would continue this indirect benefit. Conversely, plant shutdown and the resulting loss l of the property tax base could lower the county bond rating. Based on this review of the issues, the staff concludes that the net impact of plant-related population increases and tax receipts is likely to be SMALL While the tax receipts are large enough to result in moderate impacts on land use, Calvert County has a well-developed plan for land use that will minimize land conversion in the future. In addition, while the relatively low taxes, good bond rating, and high levels of public service afforded by CCNPP-related tax receipts tend to draw population growth to the County, these same receipts make possible programs that favor open space. Additional mitigation does not appear to be warranted. 4.4.4 Public Services: Transportation impacts During Operations l On October 4,1999,10 CFR 51.53(c)(3)(ii)(J) and 10 CFR Part 51, Subpart A, Appendix B, Table B-1 l were revised to clearly state that Public Services: Transportation impacts During Operations is a l Category 2 issue (64 FR 68496). This issue is treated as such in this final SEIS. There is significant population growth expected in all three counties in the study area by 2036, as was j discussed in Section 2.2.8 of this report. However, at most, less than 1 percent of this expected growth will be due directly to increases in employment at CCNPP. It may be argued that the industrial tax base afforded by CCNPP makes the county a more affordable and pleasant place to live and indirectly increases population, but even this indirect impact is likely to be small and difficult to predict. The l additional 60 employees that the plant may require during the renewal period are unlikely to add noticeably to the highway burden. Future general population increase likely will degrade highway level of service at some choke points, but the magnitude of impact of CCNPP on this service degradation is likely to be SMALL and does not require mitigation. l 4.4.5 Historical and Archaeological Resources j Because the BGE license renewal application (BGE 1998a) covering an additional 20 years of operation of the CCNPP does not include plans for future land disturbances or structural modifications j beyond routine maintenance activities at the plant, there would be no identifiable adverse effects to known historic and archaeological resources. Continued operation of the power plant and protection of the natural landscape and vegetation within the site boundaries would have a beneficial effect in that known or undiscovered resources would receive de facto protection for the term of the license renewal period, being located within an undisturbed area with secured access. Similarly, historic resources and buildings would continue to be preserved and interpreted for the public at the CCNPP Visitors Center and Nature Trail area. l Notwithstanding that BGE does not plan future land disturbances or structural modifications beyond l routine maintenance at the plant, there is a possibility that undiscovered or unrecorded prehistoric or October 1999 4-30 NUREG-1437, Supplement 1
Environm:ntalimpacts of Operation historic period archaeological sites remain on the 2300-acre plant site. Accordingly, care should be l l trk:n during normal operations or maintenance to ensure that cultural resources are notEadvertently impacted. These activities may include not only operation of the plant itself, but also land , management-related actions such as farming, recreation, wildlife habitat enhancement, or mrintaining/ upgrading access roads throughout the pl ant site. Tha staff concludes that impacts on historical and archaeological resources is SMALL, and mitigation is l not needed. l 4.4.6 Environmental Justice 1 Environmentaljustice refers to a Fec'eral policy under which Federal actions should not result in disproportionately high and adverse environmentalimpacts on low-income or minority populations. A l j minority population is defined to exist if the percentage of minorities within the census blocks exceeds j th3 percentage of minorities in the entire State of Maryland by 10 percent, or if the percentage of l minorities within the census block is at least 50 percent. For census blocks within the District of ] Columbia and States of Virginia and Delaware, the percentage of minorities is compared to the l percentage of minorities in the respective state. Executive Order 12898 [59 FR 7629) directs Federal l cx:cutive agencies to consider environmental justice under NEPA, and the Council on Environmental i i Qu;lity (CEQ) has provided guidance for addressing environmental justice under NEPA (CEO 1997). l Although it is not subject to the executive order, the Commission has voluntarily committed to undertake l environmental justice reviews. Specific guidance is provided in Attachment 4 to NRR (Office of Nuclear R;;ctor Regulation) Office Letter No. 906, Revision 1: ProceduralGuidance forPreparing Environmental Assessments and Considering EnvironmentalIssues (NRC 1996b). l Th3 scope of the review should include an analysis of impacts on low-income and minority populations, the location and significance of any environmental impacts during operations on those populations that I cra particularly sensitive, and any additional information pertaining to mitigation. The descriptions to be provided by this review should be of sufficient detail to permit subsequent staff assessment and evaluation of specific impacts, in particular whether these impacts are likely to be disproportionately high and adverse, and to evalua'e the significance of such impacts. Air, land, and water resources within about 80 km (50 mi) of CCNPP were examined. Within that area, there are a few potential environmental impacts that could affect human populations; all of these were considered SMALL. These include: I
. groundwater use conflicts . electric shock . microbial organisms e accident scenarios.
NUREG-1437, Supplement 1 4-31 October 1999 {
EnvironmnntilImp cts of Operation To decide whether any of these impacts could be disproportionate, the staff examined the geographic distribution of low-income and minority populations recorded during the 1990 Census (DOC 1991), supplemented by field inquiries to the local p!anning departments in Calvert, St. Mary's, and Charles Counties, and to social service agencies in the three counties. The staff focused this portion of the review on the geographic areas most likely to experience the impacts discussed above, i.e., the three closest surrounding counties. This area is referred to as the study area. Generally speaking, minority populations are a small, dispersed, and declining proportion of the study l area's population. Figure 4-1 (taken from the ',990 Census (DOC 1991) shows the geographic l distribution of minority populations with the 80 km (50 mi) radius. Figure 4-1 generally shows that l minority populations are concentrated in northern Virginia, near Richmond and near Washington, D.C. l However, there are three census block groups with higher percentages of minority residents, one in a l generally south south-westerly direction from CCNPP, near Lusby, and the other two slightly to the l west-northwest, near Broomes Island, Maryland. Generally, however, minority populations are either well-mixed into the majority population, or concentrations of minority individuals are too small to be caught in the Census detail. This is consistent with the results of field interviews. There is a small low-income, mainly Hispanic, population concentration at Broome's Island in Calvert County and a small concentration of a mixed-race (Piscataway-African American-white) minority group (locally called "Wesorts") near Benedict ir St. Mary's County. Low-income populations are well-scattered throughout the three-county area. Some of these individuals are known to be watermen or ex-sharecroppers l effectively engaged in subsistence agriculture. Figure 4-2 shows concentnations of low-income l population in the Washington, D.C. area, with other, mainly scattered pockets throughout the 50-mile l region (DOC 1991). The cross-hatched census blocks show areas where the percentage of l households below the poverty levelis 10 percent or more greater than the percentage of households l below the poverty level in the entire State of Maryland for those censis blocks within the State of l Maryland. It also includes census blocks where the percentage of households below the poverty level l exceeds 50 percent. For census blocks within the District of Columbia and the States of Virginia or l Delaware, the percentage of households below the poverty level is compared to the percentage of l households below the poverty levelin the corresponding state. Low-income housing tends to be concentrated in the Prince Frederick area. St. Mary's County shows concentrations of low-income population in the vicinity of Hillville-Hollywood-Lexington Park area and at Leonardtown. These are also the locations of low-income housing. l The low-income populations in the Lexington Park area might be adversely affected by groundwater conflicts due to , copulation growth; nowever, the marginal effect of CCNPP on this problem is at most SMALL. Examination of the various environmental pathways by which low-income and minority j populations could be disproportionately affected reveals no unusual resource dependencies or { practices through which these populations could be disproportionately affected. Specifically, no I pathways were found through which fisheries or subsistence agriculture were significantly affected. l Therefore, the impact is SMALL, and no special mitigation actions are warranted. October 1999 4-32 NUREG-1437, Supplement 1
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Environm:nt:1 Imp; cts of Operation 4.5 Groundwater Use and Quality A Category 1 issue in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, is applicable to CCNPP l groundwater use and quality and is listed in Table 4-10. BGE stated in its ER that it is unaware of any nLw and significant information related to this Category 1 issue. No significant new information has be:;n identified by the staff in the review process and in the staff's independent review. Therefore, the stiff concludes that there are no impacts related to this issue beyond those discussed in the GEIS. For this issue, the GEIS concluded that the impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. Tcble 4-10. Category 1 issues Applicable to Groundwater Use and Quality During the Renewal Term l lSSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Section l GROUNDWATER UsE AND QuAUTY Ground-water quality degradation (saltwater intrusion) 4,8.2.1 A brief description of the staff's review and the GEIS conclusions, as codified in Table B-1, for the issue follows.
. Ground-water cuality dearadation (saltwater intrusion): Based on information in the GEIS, the Commission found that " Nuclear power plants do not contribute significantly to saltwater intrusion." j
.The staff has not identified any significant new information during its independent review of the BGE j ER, the staff's site visit, the scoping process, its review of public comrnents on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts on groundwater quality from saltwater intrusion during the renewal term beyond those discussed in l the GE;S l Th:re is one Category 2 issue related to groundwater use and quality. That issue is listed in Table 4-11 and discussed in Section 4.5.1. l Tcble 4-11. Category 2 issues Applicable to Groundwater Use and Quality During the Renewal Term l 10 CFR ISSUE-10 CFR Part 51, Subpart A, Appendix GEIS 51.53(c)(3)(ii) SEIS l B, Table B-1 Sections subparagraph Section GROUNDWATER UsE AND QUAUTY Ground-water use conflicts (potable and service 4.8.1.1; C 4.5.1 water, and dewatering; plants that use > 100 gpm) 4.8.2.1 NUREG-1437, Supplement 1 4-35 October 1999
Environmrntal imp; cts of Operation 4.5.1 Groundwater Use Conflicts (Potable and Service Water) 8 l With both units operating, CCNPP withdraws an eserage of 0.018 m /s (284 gpm or 409,000 gpd) (BGE l 1998b). This is a Category 2 issue because this flow exceeds the 0.006 m /s (100 gpm) limit in the GEIS for a Category 1 issue. The groundwater withdrawal is in compliance with a groundwater appropriation permit issued by MDE. CCNPP withdraws water from the Aquia Aquifer. The drawdown of the water in the Aquia Aquifer in the, vicinity of CCNPP is a result of the combined withdrawals of CCNPP and other users. Average withdrawals from the Aquia Aquifer in 1995 were about 0.16 m8 /s (3.7 million gpd) in Calvert County and 0.21 m /s (4.7 million gpd) in St. Mary's County (see Table 2-8). The U.S. Geological Survey and the MDNR maintain a joint monitoring program of the Aquia Aquifer. The program has tracked and reported on water levels in the Aquia Aquifer since 1975 (Achmad and Hansen 1997). Water levels at a monitoring well located at the CCNPP site have dropped from 4.6 m (15 ft) below mean sea level (MSL) in 1978 to 18 m (60 ft) below MSL in 1994. In Maryland, water level declines are permitted up to 80 percent of the available drawdown, a distance measured from the estimated prepumping water level to the top of the aquifer. This regulation permits the water level to drop to 109 m (358 ft) below MSL, a far greater depth than has been observed or calculated based on regional growth projections. l The incremental drawdown, based on the maximum permitted withdrawal, resulting from pumpage l continuing for the renewal period was estimated to be less than 2 m (5 ft) at 5000 ft from the withdrawal l wells. Although continued operation of CCNPP will continue the existing drawdowns caused by the 1 l site's groundwater withdrawal wells, and these drawdowns will be further exacerbated by the l superimposition of drawdowns associated with the impact of growing regional groundwater use, the l impact is considered SMALL, and does not require mitigation. 4.6 Threatened or Endangered Specias Threatened or endangered species is listed as a Category 2 issue in Table B-1 of Appendix B of 10 CFR 51, Subpart A. The issue is listed in Table 4-12. This issue requires consultation with appropriate agencies to determine whether threatened or i endangered species are present and whether they would be adversely affected. Consultation under Section 7 of the Endangered Species Act was initiated on October 23,1997, with the U.S. Fish and 4 Wildlife Service (FWS), and on October 9,1997, with the National Marine Fisheries Service (NMFS). l FWS identified three Federally protected species under theirjurisdiction as occurring on the CCNPP October 1999 4-36 NUREG-1437, Supplement 1
l l l Environm:ntalImpacts of Operation l l Table 4-12. Category 2 issues Applicable to Threatened or Endangered Species l During the Renewal Term l 10 CFR ISSUE-10 CFR Part 51, Subpart A, GEIS 51.53(c)(3)(ii) l Appendix B, Table B-1 Sections Subparagraph SEIS Sections THREATENED oR ENDANGERED SPECIES (FoR AL.L PLANTS) Threatened or endangered species 4.1 E 4.6 sit)(see Section 2.2.6). In addition, the NMFS identified the shortnose sturgeon and the loggerhead turtle as potentially occurring in the vicinity of the CCNPP site (see Section 2.2.5). The response letters from FWS and NMFS are included in Appendix E. FWS concluded that no adverse impacts to listed species would be likely under conditions of license l r;n:wal. FWS also recommended a number of conservation measures that have been implemented by l BGE. The Nature Conservancy is allowed escorted foot access to the beach below the CCNPP so that l censuses of tiger beetles can be conducted. BGE has placed constraints on activities in the vicinity of l tetive bald eagle nests: no nonroutine human activities (e.g., construction, timber harvest, or heavy l m chinery operation) are allowed within 0.4 km (1/4 mile) of active bald eagle nests during the nesting l ssison (December 15 to June 15) without coordination and approval from MDNR and FWS. BGE has l clso agreed to initiate consultation with the FWS whenever activities are planned that would result in l significant habitat changes within the OA km (1/4 mile) radius of active bald eagle nests, regardless of l tims of the year. l An cdditional potential impact on threatened or endangered species is the regulation control and related I disturbances associated with routine maintenance of transmission line corridors. The staff has l ex mined the potential impacts on the species listed in Section 2.2.6 and concludes that there is little l likilihood that adverse impacts on endangered or threatened species will occur as a result of routine l transmission line corridor maintenance activities during the 20-year period of license renewal. l Tha NMFS concluded that CCNPP license renewal would not adversely affect either the shortnose sturgeon or the loggerhead turtles because the CCNPP discharge / intake does not lie within the areas normally used by either species. There is no evidence that the thermal effects of the CCNPP cooling wit:r discharge would influence periodic migration of the shortnose sturgeon to and from river systems, nor have either the shortnose sturgeon or the loggerhead turtles been found impinged on the intake screen during the 21 years of monitoring data summarized in the BGE impingement study. Thus, operating license renewal should not affect the viability of either of these species or result in further l d: cline. NUREG-1437, Supplernent 1 4-37 October 1999
Environmsntal imp; cts of Operation The staff has completed consultation with NMFS and FWS relative to potential impacts to listed and proposed threatened or endangered species or critical habitats from operations during the renewal term. Based on this consuitation, the staff concludes that the impact is SMALL, and mitigation beyond l the measures recommended by the FWS and implemented by BGE is not needed. 4.7 Evaluation of Potential New and Significant information on impacts of Operations During the Renewal Term The staff has not identified new and significant information on environmental issues related to operation l during the renewal term listed in 10 CFR Part 51, Subpart A, Appendix B, Table B-1. The staff reviewed the discussion of environmental impacts associated with operation during the renewal term in the GEIS l and has conducted its own independent review, including the public scoping meetings, to identify issues with significant new information. During the CCNPP site visit in July 1998, BGE staff stated that l l measurements of channelintake depths indicated that siltation has occurred since the channel was I constructed. BGE indicated that it has no plans to dredge the channel. If conditions changed and l maintenance dredging became necessary, an application for a dredging permit, including environmental l review of methods of redredging and spoil disposal, would be submitted to the applicable permitting agencies at the appropriate time. This new information is not considered a significant ecological concem relative to CCNPP operation during the renewal term. The review process &.lso would identify environmental issues that have not been evaluated. During a scoping meeting, a member of the public raised an issue regarding the release to the Chesapeake Bay of microorganisms that may live in extreme heat in spent fuel pools, and the potential threat posed by such a release. This issue is discussed in the following section. l 4.7.1 Microorganisms That Live in High Radiation, Extreme Heat Conditions During the July 1998 scoping meeting, one member of the public referred to an article that had been published in the May 23,1998, issue of Science News (Volume 153, "Something's Bugging Nuclear Fuer) and expressed concems regarding the potential for microorganisms that can live under extreme heat conditions and be exposed to nuclear radiation (such as within the spent fuel pool) within nuclear power plants. The commenter asked that this issue be considered as part of the scoping process, and specifically that consideration be given to the types of organisms that could live under these conditions, the possibility for mutation, and the consequences of these microorganisms escaping from the plant into the Chesapeake Bay. October 1999 4-38 NUREG-1437, Supplement 1
Environm:ntalimp cts of Operation In r;sponse, the staff investigated and talked with microbiologists that specialized in research on microorganisms that live in extreme heat conditions. The following is a summary of the information that w:s obtained from the specialists: Many types of organisms can live quite comfortably in the temperature range of the pools (100 to 150*F or 38 to 65'C). Some organisms (hyperthermophiles) can thrive at temperatures as high as 110*C (230*F) near ocean vents. Thermophilic bacteria have been extensively studied (Alfredsson and Kristjannson 1995). Bacteria in the genus Thermus are common inhabitants of hot water tanks, piping, and hot springs, such as those in Yellowstone National Park. Some bacteria are also fairly l radiation resistant; Deinococcus radiodurans can recover from doses of ionizing radiation as great as 20 kGy. Although most microbes would not be able to exist in the radiation fields near the fuel assemblies, they would be able to survive in the lower radiation fields found at the surface and , against the walls of the spent fuel pool. There is a potential for mutation in all living organisms, but microbes that have high levels of radiation resistance also have developed extremely efficient repair systems. These repair systems have a remarkably high degree of fidelity and would reduce the potential for mutation. Bacteria already thrive in many extreme environments, and while mutations do occur, it is difficult to detect changes in the morphology or physiology of such mutated organisms. Organisms that are associated with thermal waters of the spent fuel pool are likely to die if they are transferred into much colder waters, such as those of the Chesapeake Bay. If the organisms are l truly adapted to thermal conditions, they would not likely be able to survive and compete with the indigenous microbiota of the relativeny cold waters of the Chesapeake Bay. Although some bacteria can survive in a dormant state for long periods of time, bacteria in a microbially-active system such as the Chesapeake Bay likely will have a much shorter lifespan due to factors such as predation ; and competition. l B: sed on this information, the staff concludes that microorganisms that may inhabit high-radiation, high-tsmperature environments (such as the spent fuel pool) have little potential for a significant increase in l number in the environment, and would not have a deleterious effect on public health as a result of the continued operation of CCNPP during a 20-year license renewal term. l 4.8 Summary of impacts of Operations During the Renewal Term ) N:ither BGE or the staff is aware of significant new information related to any of the applicable C tegory 1 issues associated with the CCNPP operation during the renewal term. Consequently, the , I staff concludes that the environmentalimpacts associated with these issues are bounded by the impacts described in the GEIS. For each of these issues, the GEIS concluded that the impacts would be SMALL and that " plant-specific mitigation measures are not likely to be sufficiently beneficial to w:rrant implementation." NUREG-1437, Supplement 1 4-39 October 1999 l
Environm nt:1 imp; cts of Operation Plant-specific environmental evaluations were conducted for 13 Category 2 issues applicable to l CCNPP operation during the renewal term and for environmentaljustice. for 12 issues and l environmental justice, the staff concluded that the potential environmental impact of renewal term operations of CCNPP would be of SMALL significance in the context of the standards set forth in the l l GEIS and that mitigation would not be warranted. The staff also concluded that the potential impacts of CCNPP operating license renewal would be of SMALL significance on threatened or endangered l species. Mitigation measures beyond those identified by the FWS and implemented by BGE are not warranted. In addition, the staff determined that a consensus has not been reached by appropriate Federal health agencies that there are adverse health effects from electromagnetic fields. 4.9 References l 10 CFR 51.53, "Postconstruction environmental reports." 10 CFR Part 51, Subpart A, Appendix B," Environmental Effect of Renewing the Operating License of a Nuclear Power Plant." 40 CFR Part 423, " Steam Electric Power Generating Point Source Category." Abbe, G. R.1988. " Population structure of the American oyster, Crassostrea virginica, on an oyster bar in central Chesapeake Bay: Changes associated with shell planting and increased recruitment." Joumal of Shellfish Research, Vol. 7, No.1, 33-40. 1 ] Abbe, G. R.1992. " Population structure of the eastem oyster, Crassostrea virginica (Gmelin,1791) on two oyster bars in central Chesapeake Bay: Further changes associated with shell planting, recruitment, and disease." Joumal of Shellfish Research, Vol.11, No. 2,421-430. Academy of Natural Sciences of Philadelphia (ANSP) and Edinger JW Associates Inc.1980. Calvert Cliffs Nuclear Power Plant Thermal Plume Dye Studies: April and August 1979, and Analysis of Plume Sites. Report No. 80-10. Academy of National Sciences, Philadelphia.122 pp. Academy of Natural Sciences of Philadelphia (ANSP).1981. Assessment of Thermal, Entrainment, and Impingement Impacts on the Chesapeake Bay in the Vicinity of the Calvert Cliffs Nuclear Power Plant. Report No. 81-10. Prepared for Baltimore Gas and Electric Company. 298 pp. Achmad, G. and H. J. Hansen. 1997. Hydrogeology, Model Simulation, and Water-Supply Potential of the Aquia and Piney Point-Najemoy Aquifers in Calvert and St. Mary's Counties, Maryland. Report of Investigations No. 64. Maryland Geological Survey, Baltimore, Maryland. October 1999 4-40 NUREG-1437, Supplement 1
i l Environm:ntal Impacts of Operation Am:rican Fisheries Society.1992. Investigation and Valuation of Fish Kills. American Fisheries l Society Special Publication 24. Bethesda, Maryland. l Biltimore Gas and Electric Company (BGE).1998a. Applicant's Environmental Report-Operating Lic:nse Renewal Stage Calvert Cliffs Nuclear Power Plant Units 1 and 2, Docket Nos. 50-317 and 50-318. Lusby, Maryland. Bittimore Gas and Electric Company (BGE).1998b. Letter from Mr. C.H. Cruse (BGE) to NRC Documents Control Desk,
- Investigations ofImpingement of Aquatic Organisms at the Calvert Cliffs NuclearPowerPlant, 1975-1995. Response to Question Number 23 of the Request for Additional Inf:rmation for the Review of the Calvert Cliffs Nuclear Power Plant, Unit Nos.1&2, Environmental R: port Associated with License Renewal (TAC Nos. MA1524 and MA1525)," December 3,1998.
Lusby, Maryland. Burton, D. T.1976. " Impingement studies: 11: Qualitative and quantitative survival estimates of impinged fish and crabs." In: Semi-annual environmental monitoring report for the Calvert Cliffs NuclearPowerPlant, March 1976. Baltimore, Maryland Crivert County Department of Economic Development.1994. Demographic Information for Solomons, Mrryland and the Surrounding Area, Calvert County Department of Economic Development, Prince Frederick, Maryland, March 26,1994. COMAR (Code of Maryland Regulations) Title 08, Subtitle 02, Chapter 09, Section 01 - Monetary Value l of Tidal Water and Non-Tidal Water Aquatic Animals. l l COMAR (Code of Maryland Regulations) Title 26, Subtitle 08, Chapter 03, Section 05 - Cooling Water l Intike Structures. l
- - - l Council on Environmental Quality (CEQ).1997. EnvironmentalJustice: Guidance Under the National Environmenta/ Policy Act, Council on Environmental Quality, Executive Office of the President, Wnhington, D.C.
Ex;cutive Order 12898, " Federal Actions to Address Environmental Justice in Minority and Low-income Populations.' 59 FederalRegister7629-7633 (1994). Federal Water Pollution Control Act (FWPCA), as amended, 33 USC 1251-1387 (also known as the l Clean Water Act [ CWA]). l Fctter, C. W.1988. Applied Hydrology, Second edition, Macmillan Publishing Company. NUREG-1437, Supplement 1 4-41 October 1999
Environment:1 ImpIcts of Oparation Heck, K. L., Jr. (Ed.).1987. Ecological Studies in the Middle Reach of Chesapeake Bay, Lecture Notes on Coastal and Marine Studies. Springer-Verlag - Berlin, Heidelberg, New York. l Hixon, J. H. Ili, and D. L. Breitburg, 1993. 1993 Impingement Studies at Calvert Cli/fs Nuclear Power l Plant for Baltimore Gas and Electric Company. Estuarine Research Center, St. Leonard, Maryland, of l The Academy of Natural Sciences, Philadelphia, Pennsylvania. Report No. 94-28.
- l l Hixon, J. H.111, and D. L. Breitburg. 1994. 1994 Impingement Studies at Calvert Cliffs Nuclear Power l Plant for Baltimore Gas and Electric Company. Estuarine Research Center, St. Leonard, Maryland, of l The Academy of Natural Sciences, Philadelphia, Pennsylvania. Report No. 95-13.
g l 'Hixon, J. H. lll, and D. L. Breitburg. 1993. 1995 Impingement Studies at Calvert Cliffs Nuclear Power l Plant for Baltimore Gas and Electric Company. Estuarine Research Center, St. Leonard, Maryland, of .l The Academy of Natural Sciences, Philadelphia, Pennsylvania. Report No. 96-12. Holland,-A. F.1985. "Long-term variation of macrobenthos in a mesohaline region of Chesapeake Bay." . Estuaries 8:98-113. League of Women Voters of Calvert County.1994. Know Your County-Living in Calvert County, Maryland.' Martin Marietta Corporation.1976a. Calvert Cliffs Chemical Thermometer ThermalPlume Study.
. PPMP Technical Note 76-1. Prepared for Maryland Department of Natural Resources Power Plant Siting Program, Baltimore, Maryland.
Martin Marietta Corporation.1976b. Calvert Cliffs ThermalPlume Survey, Septemberand November 1975. PPMP Technical Note 76-2. Prepared for Maryland Department of Natural Resources Power Plant Siting Program, Baltimore, Maryland. Maryland Department of the Environment (MDE).1998. Letter from Edwal Stone, Chief, Industrial l Discharge Permits Division to Claudia Craig, U.S. Nuclear Regulatory Commission (October 13,1998). l Maryland Department of Natural Resources (MDNR).1999. Letter from Richard McLean, Manager, l Nuclear Programs to Chief, Rules Review and Directives Branch, U.S. Nuclear Regulatory Commission l: (May 19,1999). Mitchell, R. D. and E. C. Papenfuse.1994. " Maryland -The Old Line State," contributed by World Book > Encyclopedia, World Book, Inc. l October 1999 4-42 NUREG-1437, Supplement 1 I
I 1 l Environm:ntalImp cts of Operation l l N:tional Institute of Environmental Health Sciences (NIESH).1999. NIESH Report on Health Effects l from Exposure to Power Line Frequency Electric and Magnetic Fields. NH Publication No. 99-4493. l National Institutes of Health, Research Triangle Park, North Carolina. l Newman, E. M. and L. E. Sage.1981. "Entrainment Studies: Zooplankton." In: Assessment of Th:rmal, Entrainment and Imaingement Impacts on the Chesapeake Bay in the Vicinity of the Calvert Cliffs NuclearPowerPlant. / .demy of Natural Sciences, Philadelphia, Pennsylvania. Report I No. 81-10. April 8,1981. l Olson, M. and L. E. Sage.1979. " Zooplankton entrainment." In: Non-radiological environmental monitoring report, Calvert Cliffs Nuclear Power Plant, January-December 1978. Baltimore, Maryland. B ltimore Gas and Electric Company: pp 12.2-1 to 12.2-57. Science News.1998. "Something's Bugging Nuclear Fuel." Volume 153, May 23,1998. Tri-County Council for Southern Maryland. 1993. 1990 Statistical Profiles for Calvert, Charfes, and St. Mary's Counties, Tri-County Council for Southem Maryland, February 1993. U.S. Atomic Energy Commission (AEC).1973. FinalEnvironmental Statement Related to Operation of Calv:rt Nuclear Power Plant Units 1 and 2, Docket Nos. 50-317 and 50-318. (April 1973), Washington, D.C. U.S. Department of Commerce (DOC). 1991. 1990 Census of Population and Housing; Public Law 94-171 Data, Bureau of the Census, U.S. Govemment Printing Office, Washington, D.C. , U.S. Nuclear Regulatory Commission (NRC).1996a. Generic Environmentallmpact Statement for Lic:nse Renewal of Nuclear Plants (GEIS), NUREG-1437. Washington, D.C. l U.S. Nuclear Regulatory Commission (NRC).1996b. Procedural Guidance for Preparing Environmental Assessments and Considering EnvironmentalIssues, Attachment 4 to NRR Office Letter No. 906, Revision 1. Washington, D.C. l U.S. Nuclear Regulatory Commission (NRC).1999. Generic Environmental /mpact Statement for l License Renewal of Nuclear Plants, Main Report, Section 6.3-Transportation, Table 9.1, Summary of l Findings on NEPA issues forlicense renewalof nuclearpowerplants. NUREG-1437, Volume 1, l Add:ndum 1. Washington, D.C. l l l j NUREG-1437, Supplement 1 4-43 October 1999 i
5.0 EnvironmentalImpacts of Postulated Accidents l Environmental issues associated with postulated accidents were discussed in the Generic l EnvironmentalImpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437 (NRC l 1996). The GEIS included a determination of whether the analysis of the environmental issue could be l cpplied to all plants, and whether additional mitigation measures would be warranted. Issues were then l cssigned a Category 1 or a Category 2 designation. As set forth in the GEIS, Category 1 issues are j those that meet all of the following criteria: l (1) the environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other specified plant or site characteristics (2) e single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except l for collective offsite radiological impacts from the fuel cycle and from high-level waste and spent fuel l disposal) l l (3) mitigation of adverse impacts associated with the issue has been considered in the analysis, and it l has been determined that additional plant-specific mitigation measures are likely not to be l sufficiently beneficial to warrant implementation. For issues that meet the three Category 1 criteria, no additional plant-specific analysis is required l unless new and significant information is identified. Crtegory 2 issues are those that do not meet one or more of the criteria of Category 1, and therefore, l rdditional plant-specific review for these issues is required. This chapter describes the environmental impacts from postulated accidents that might occur during the l license renewal term. The generic potentialimpacts from postulated accidents have been described in l the Generic EnvironmentalImpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG- l 1437 (NRC 1996a). l 5.1 Postulated Plant Accidents A C tegory 1 issue in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, is applicable to CCNPP l postulated accidents and is listed in Table 5-1. BGE stateC in its Environmental Report (ER) (BGE l 1998a) that it is unaware of any new and significant information related to this Category 1 issue. No significant new information has been identified by the staff in the review process and in the staff's ind: pendent review. Therefore, the staff concludes that there are no impacts related to this issue NUREG-1437, Supplement 1 5-1 October 1999
Postulated Accid:rts beyond those discussed in the GEIS. For this issue, the GEIS concluded that the impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. A brief description of the staff's review and the GEIS conclusions, as codified in Table B-1, for the issue follows. l Table 5-1. Category 1 issues Applicable to Postulated Accidents During the Renewal Term l ISSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Sections POSTULATED ACCIDENTS l Design Basis Accidents (DBA) 5.3.2; 5.5.1 l Desian Basis Accidents: Based on information in the GEIS, the Commission found: that "The NRC staff has concluded that the environmental impacts of design basis accidents are of small significance l for all plants." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of DBAs beyond those discussed in the GEIS. A Category 2 issue related to postulated accidents that is applicable to CCNPP is discussed in Table 5-2. Table 5-2. Category 2 issues Applicable to Postulated Accidents ( l ISSUE-10 CFR Part 51, 10 CFR 51.53(c)(3)(ii) { Subpart A, Appendix B, Table B-1 GEIS Sections Subparagraph SElS Sections POSTULATED ACCIDENTS Severe Accidents 5.3.3; 5.3.3.2; L 5.2 5.3.3.3; 5.3.3.4; 5.3.3.5; 5.4; 5.5.2 Severe Accidents: Based on information in the GEIS, the Commission found the following: that "The l probability weighted consequences of atmospheric releases fallout onto open bodies of water, releases I to ground water, and societal and economic impacts from severe accidents are small for all plants. However, alternatives to mitigate severe accidents must be considered for all plants that have not considered such attematives." The staff has not identified any significant new information with regard to the consequences from severe accidents in its review of the BGE ER (BGE 1998a), the BGE Final l Safety Analysis Report (FSAR) (BGE 1998b), the site visit, the scoping process, its consideration of October 1999 5-2 NUREG-1437, Supplement 1
Postulat d Accidents public comments, or in its independent evaluation of the available information. Therefore, the staff l concludes that there are no impacts of severe accidents beyond those discussed in the GEIS. However, in accordance with 10 CFR 51.53(c)(3)(ii)(L), the staff has reviewed severe accident j mitigation attematives (SAMAs) for CCNPP. The results of its review are discussed in Section 5.2. l 5.2 Severe Accident Mitigation Alternatives it is required in 10 CFR 51.53(c)(3)(ii)(L) that license renewal applicants provide a consideration of l cit:matives to mitigate severe accidents if the staff has not previously considered SAMAs for the applicant's plant in an EIS or related supplement or in an environmental assessment. The purpose of this consideration is to ensure that plant design changes with the potential for improving severe cccident safety performance are identified and evaluated. SAMAs have not previously been considered for CCNPP; therefore, the remainder of Chapter 5 addresses those attematives. 5.2.1 Introduction BGE submitted an initial assessment of SAMAs for CCNPP in the ER. This assessment was based on an updated version of the CCNPP Individual Plant Examination (IPE) for intemal events (BGE 1993), an updated version of the CCNPP Individual Plant Examination for Extemal Events (IPEEE) (BGE 1997), s M supplementary analyses of offsite consequences and economic impacts. BGE concluded that l
,.s of the candidate SAMAs identified and evaluated were cost-effective for CCNPP. However, BGE was still evaluating three proposed changes at the time the license renewal application was submitted. l 1
B: sed on a review of the SAMA submittal, the staff issued an RAI to BGE by letter dated September 9, [ 1998 (NRC 1998b). Major issues concemod the inclusion of averted onsite costs (AOSCs) in BGE's l value impact analysis, the effects of uncertainties in risk and cost estimates on the identification of cost-beneficial SAMAs, and the results of BGE's evaluation of the three remaining SAMAs. BGE submitted additionalinformation by letter dated December 3,1998 (BGE 1998c). One SAMA, l which involves installing a watertight door between the service water pump room and the adjacent fan room to reduce risk from intemal flooding, is being considered under BGE's modification process. l S:veral additional SAMAs were also shown to have a positive net value when evaluated in accordance
]
with NRC's regulatory analysis handbook (i.e., when AOSCs are included as benefits). However, BGE concluded that none of these additional SAMAs warrant implementation. > I The staff's assessment of SAMAs for CCNPP, which included review of the BGE process and ) independent staff analysis, follows. NUREG-1437, Supplement 1 5-3 October 1999 1
Po:tulated Accidents 5.2.2 Estimate of Risk for CCNPP A description of BGE's estimates of the offsite risk at CCNPP is summarized below. The summary is followed by the staff's review of BGE's risk estimates. 5.2.2.1 BGE Risk Estimates The Calvert Cliffs Probabilistic Risk Assessment (CCPRA) model, which forms the basis for the SAMA analysis, is a Level 3 risk analysis (i.e., it includes treatment of core damage frequency, containment performance, and offsite consequences). The model, which BGE refers to as Update 2, consists of an intemal events portion, based on an updated version of the IPE, and an extemal events portion, based on an updated version of the IPEEE. Major changes in the analysis since the IPE submittal are described in BGE's December 3,1998, RAI response (BGE 1998c). Changes in the Level 1 (core darnage frequency [CDF]) portion of the analysis following the IPE submittal include improved treatment of success criteria for anticipated transient without scram events, reactor coolant pump (RCP) seal loss of coolant accidents (LOCAs), and low pressure feed; common cause failure of inverters and transformers; and human action dependencies and recovery actions. Some changes resulted in risk reduction and others in risk increase. The net impact of the changes on CDF is small despite the significance of some of these changes due to the offsetting effect of the risk increase and decrease. The BGE SAMA analysis is based on the Unit 1 model, but the impact of the differences between units was considered in the screening and value/ impact analysis. The Level 2 (also called containment performance) portion of the CCPRA model, including the plant damage state descriptors, the Containment Performance Event Tree, and the source term binning ana containment release categories, is essentially the same as the IPE Level 2 analysis. The offsite (or ; Level 3) consequence analyses were carried out using the NRC-developed Melcor Accident l Consequence Code System (MACCS), Version 1.5.11.1 (Chanin et al.1990), and site-specific data for meteorology, population, and evacuation modeling. BGE estimated the total CDF for intemally and extemally initiated events to be 3.3x10" per reactor-year, and the offsite risk to the population within 80 km (50 mi) of the CCNPP site to be about 0.68 l person-sievert (person-Sv) (68 person-rem) per reactor-year. The breakdown of the Unit 1 CDF is provided in Table 5-3. It shows that transients are a dominant contributor to CDF, followed by fire and LOCAs. The breakdown of containment release frequency and population dose by release category is given in Table 5-4. Among the CCNPP conditional containment failure probabilities, early containment failure is about 7 percent, with isolation failure the primary contributor; late containment failure is about 49 percent, with containment over-pressure the primary contributor; and containment bypass is about 2 percent, with steam generator tube rupture the primary contributor. The containment remains intact October 1999 5-4 NUREG-1437, Supplement 1
Postulat d Accid nts i l Table 5-3. Calvert Cliffs CDF Profile
% of Total (Total CDF =
Accident Category 3.3x10d/ reactor-year) Transients 48 Fire 22 LOCAs 20 Intemal Flood 5 Earthquake 4 Wind 1 42 percent of the time. These results differ from the values reported in the original IPE due to the Level 1 model updates described later. Early containment failure accounts for approximately 94 percent of the population dose, with containment bypass and late containment failures contributing about 3 l percent and 2 percent, respectively. Tcble 5-4. Contribution of Containment Release Category to Release Frequency and Population Dose Containment Release Contribution to Containment Contribution to I Category Release Frequency (%)('8 Population Dose (%)N Intact Containment 42 1 l Late Containment Failure 49 2 4 Early Containment Failure 7 94 Containment Bypass 2 3 (a) Total release frequency = 3.3x10d/ reactor-year (b) Total population dose = 0.686 person-Sv (68.6 person-rem) per reactor-year 5.2.2.2 Review of BGE Risk Estimates BGE's estimate of offsite risk at CCNPP is based on the following three major elements of analysis: (1) the Level 1 and 2 risk models for CCNPP that form the bases for the December 1993 IPE submittal 4 (BGE 1993) and the August 1997 IPEEE submittal (BGE 1997) (2) the major modifications to the IPE model subsequent to December 1993 (BGE 1998c) (3) the extension of the Level 2 Probabilistic Risk Assessment (PRA) model to a Level 3 assessment. NUREG-1437, Supplement 1 5-5 October 1999
r Postulated Accid:nts
- The staff reviewed each of these analyses / processes to determine the acceptability of BGE's risk l estimates for the SAMA analysis. The results of this analyses follow.
The staffs review of the CCNPP IPE is described in an evaluation report dated April 16,1996 (NRC 1996b). In that review, the staff evaluated the methodology, models, data, and assumptions used to - estimate CDF and characterize containment performance and fission product releases. The staff j concluded that BGE's analysis met the intent of Generic Letter 88-20 (NRC 1988); that is, the IPE 1 results are reasonable considering the design, operation, and experience of the plant, together with the contributions from initiators and the failure of frontline safety and support systems. The staff also found l that the CCNPP IPE compares reasonably with other Combustion Engineering plants, but is highest in l CDF, The staff did not identify major shortcomings associated with the licensee's IPE, and further enhancements have since been made to the IPE. The CCNPP IPE identified seven vulnerabilities in the following areas: (1) loss of electrical switchgear room cooling (2) loss of main feedwater following a plant trip (3) loss of auxiliary feedwater (AFW) if valves are inoperable (4) loss of pressurizer spray during a steam generator tube rupture because of proceduralized trip of RCPs (5) significant challenges to operators following an inadvertent engineered safeguards feature, reactor protection system, and AFW system actuation resulting from failure of two 120V AC buses t (6) RCP seal LOCA resulting from loss of component cooling water seal cooling (7) common cause or maintenance failure of both turbine-driven AFW pumps. Corrective actions have been implemented that address these vulnerabilities except for the RCP seal LOCA, for which BGE determined no actions are required. The staff notes that the BGE SAMA analysis considered potential modifications in RCP seal LOCAs. Therefore, the staff concludes that the internal events portion of CCPRA provides an acceptable platform for assessing the risk reduction potential of SAMAs. The staffs review of the licensee's IPEEE is currently underway. The preliminary results did not identify any significant shortcomings or deficiencies. A cursory review of the BGE submittal finds that the overall method, scope, and level of detail are generally comprehensive. The staff also notes that the BGE IPEEE has been subjected to both intemal and extemal peer reviews. In the IPEEE, BGE identified several plant improvements from external events, and these have been implemented or are October 1999 54 NUREG-1437, Supplement i
Postulated Accidents pl:nned and being tracked for resolution. These improvements address / include switchgear room ventilation recovery during a hurricane, smoke infiltration into the control room via ventilation intake, inidvertent isolation of switchgear room and cable spreading room ventilation, fire barrier inspections, end control of transient ignition sources in the cable chases. The BGE SAMA analysis is based on the updated version of the IPEEE. The applicant stated (BGE 1998c) that the updated version, CCPRA, is slightly different from the IPEEE (BGE 1997). Based on these findings, the staff concludes that the ext: mal events portion of CCPRA provides an acceptable platform for assessing the risk reduction pottntial of SAMAs. The changes to the IPE resulting from incorporating the PRA modifications previously discussed were l not extensively evaluated as part.of the present review. However, the staff notes that BGE made an i extensive effort to update and maintain the CCPRA to reflect the as-built and as-operated condition of the plant, and that the CDF and risk estimates are the results of a detailed PRA model, which has been subjected to both staff and peer reviews. Furthermore, because the principal role of the CCPRA is to screen potential SAMAs, precise CDF and risk estimates are not critical to the analysis. Therefore, the staff concludes tat the results of the CCPRA are adequate for purposes of meeting the SAMA evaluation requirement. Tna staff revie'wed the process used by BGE to extend the containment performance (Level 2) portion of the IPE to the offsite consequence (Level 3) assessment. This included consideration of the source terms used to characterize fission product releases for each containment release category and the major input assumptions used in the MACCS analyses. This information is provided in Section F.1 of ths ER and in BGE's responses to requests for additional information. BGE used the Modular Accident Analysis Program code to analyze postulated accidents and develop radiological source terms for each of six containment release categories: intact containment, late containment failure, early containment failure (which is also further divided into large and small), and containment bypass (which is also further divided into large and small). These source terms were incorporated within the MACCS analysis as either a single puff release or split into two plume segments with different release times to represent the time variation in the releases. The staff reviewed BGE's source term estimates for the major release categories and found these predictions to be in reasonable agreement with estimates of NUREG-1150 (NRC 1990a) for the closest corresponding release scenarios. The staff concludes that the assignment of source terms is acceptable. Tha MACCS input used site-specific meteorological data processed from measurements taken during 1993. Data from 1993 were used because they were the most readily available data in 1995 when the l offsite consequence (Level 3) analysis was performed. BGE indicates that a review of the 1993 data show that they are well within the normal trend for meteorology at the CCNPP site. Therefore, the staff l considers this data representative of the climate for the site. I l ! NUREG-1437, Supplement 1 5-7 October 1999 l m-
Postul:ted Accid:nts The population distribution around the CCNPP site was based on the projected permanent resident population for the year 2030. This projection was based on 1990 census data, based on county population projections provided by various State planning agencies. These were the most current I population projections at the time the consequence analysis was performed. More recent population l projections indicate slight (less than 10 percent) increases in some counties and decreases in other counties relative to the projections on which the SAMA evaluation was based (NRC 1999). The net change is a 0.2 percent decrease in the projected total popubtion within a 80-km (50-mi) radius of the plant. Thus, the popuiation projections used in the SAMA analysis remain valid. l Site-specific economic data were used in the MACCS code. Land-use statistics, including farmland l values, farm product values, and other factors were provided on a County-wide and State-wide basis for l distances out to 80 km (50 mi). The majority of these data were taken from the MACCS Users Manual l or NUREG-1150 and are considered by the staff to provide a reasonable representation of the estimated offsite costs of a severe accident. Evacuation modeling is based on site-specific evacuation studies carried out by BGE. It was assumed that only 95 percent of the people within the plume exposure pathway emergency planning zone would participate in the evacuation. The remaining 5 percent are assumed to be unable or unwilling to evacuate, and are assumed to go about their normal activities for 24 hours. This assumption is conservative relative to the NUREG-1150 study, which assumed evacuation of 99.5 percent of the pcpulation within the emergency planning zone. The staff concludes that the methodology used by BGE to estimate the Cff and offsite consequences for CCNPP provides an acceptable basis from which to proceed with an < assment of risk reduction potential for candidate SAMAs. Accordingly, the staff based its assessment of offsite risk on the CDF and offsite doses reported by BGE. 5.2.3 Potential Design improvements The process for identifying potential design improvements, the staffs evaluation of this process, and the design improvements evaluated in detail by BGE are discussed in this section. 5.2.3.1 Process for Identifying Potential Design improvements BGE identified an initial list of 158 potential design improvements through a process consisting of the following steps: (1) consideration of significant plant issues that contributed to large numbers of sequences, and of issues that indicated a higher likelihood of being risk-beneficial. This is based mainly on the risk insights from the extensive PRA knowledge and experience of the BGE personnel. , October 1999 5-8 NUREG-1437, Supplement 1 i
Postulat:d Accidents (2) review of insights from other plant-specific risk studies and from generic containment improvement studies. This included insights from the IPE program presented during a public workshop on the iPE and documented in NUREG-1560 (NRC 1997a), and design improvements for large dry pressurized water reactor containments identified through the NRC Containment Performance Improvement Program (NRC 1990b). (3) review of plant improvements evaluated in previous severe accident mitigatien design alternative analyses for other operating nuclear piants (Watta Bar [NRC 1995a], Comanche Peak [NRC 1989a), j and Limerick [NRC 1989b]), and for advanced light water reactor designs (ABB-CE System 80+ [NRC 1994] and Westinghouse AP600 [NRC 1998c]). As a preliminary screening, BGE eliminated any SAMAs that are not applicable to CCNPP (e.g., enhancements applicable only to boiling water reactors), already implemented at CCNPP (e.g., cutomatic transfer to containment sump recirculation), or related to RCP seal injecuon. Improvements to RCP injection were eliminated because CCNPP, like other Combustion Engineering plants, does not l h ve an RCP sealinjection system. However, SAMAs to reduce the frequency of sequences involving RCP seal LOCA and a . CAMA to replace the existing RCP seal system with a seal injection system were ritzined in the evaluation. Based on the preliminary screening, BGE designated 97 of the original SAMAs for further study. Several SAMAs are multiple-part and effectively add 8 more SAMAs, bringing l th3 total number of SAMAs identified for further study to 105. These SAMAs address the spectrum of contributors to containment release for CCNPP. As a final screening, BGE eliminated additional SAMAs, based on a preliminary value-impact analysis. l As a first step, BGE redefined the conceptual SAMAs in terms of CCNPP-specific design , improvements. Based on the more specific SAMA description, a number of potential SAMAs were , screened out because they are already addressed in the current design. The benefits and costs l cssociated with the remaining SAMAs were estimated as described later. BGE then eliminated those SAMAs whose cost was expected to exceed the maximum attainable benefit (estimated by BGE to be
$2.3 million) and those hardware items having an estimated monetized benefit of less than $40,000. j On the basis of this screening, BGE identified 26 SAMAs for further analysis. This includes three l SAMAs that were still under review by BGE at the time the ER was submitted.
BGE did not include several factors in the treatment of onsite economic costs. Specifically, the onsite j property damage costs associated with cleanup and decontamination were not included on the basis l that such costs are covered by property damage insurance. Also, BGE did not include replacement l power costs as an onsite economic cost on the basis that such costs are unlikely to be incurred by the l utility in a deregulated energy market. In view of the significant impact of AOSCs on both the estimated l benefit for each SAMA and the maximum attainable benefit (i.e., the benefit associated with eliminating cli core damage events), the staff reqJested that BGE include AOSCs in the estimation of benefits for j c ch affected SAMA, update the value for the maximum attainable benefit based on inclusion of AOSCs, and update the SAMA screening accordingly. l NUREG-1437, Supplement 1 5-9 October 1999
Postulat:d Accid *:nts l In the response to the RAI, BGE updated the benefit estimates for all SAMAs and updated the l maximum attainable benefit (from $2.4 million to $8.6 million) to account for inclusion of AOSCs. BGE re-screened the SAMAs using these revised benefit estimates. BGE compiled a list of the 10 SAMAs with the highest calculated net values and compared these SAMAs with a similar list based on their l original screening (which did not include AOSCs). The revised list includes 9 of the 26 SAMAs l identified by BGE in its ER and the following SAMA that was previously excluded because of a high cost of enhancement: " Install high capacity power operated relief valves (PORVs) such that a single PORV j is capable of providing adequate decay heat removal (SAMA 77)." BGE included this additional l improvement along with the 9 other SAMAs identified for further analysis. { 5.2.3.2 Staff Evaluation BGE's effort to identify an initial list of potential SAMAs focused primarily on areas associated with internal initiating events. The initiallist of SAMAs generally coincide with accident categories that are dominant CDF contributors or with issues that tend to have a large impact on a number of accident sequences at CCNPP. Though BGE did not fully take advantage of the CCPRA and the capabilities of l the detailed model, it made a reasonable effort to search for potential SAMA candidates, using the knowledge and experience of its PRA personnel, reviewing insights from other plant-specific studies, and reviewing plant improvements in previous SAMA analyses. The staff also finds that the CCNPP IPEEE has identified several plant improvements. These have been implemented or are planned and being tracked for resolution. It is also noted that none of the previous SAMA analyses for operating plants included an explicit search for SAMAs associated with extemal initiating events. Additionally, BGE uses both its internal and extemal event PRA model for estimating risk benefit of SAMAs that are screened in for further evaluation. Therefore, the staff concludes that BGE's effort to search for potential SAMAs is reasonable. 1 The staff reviewed the set of potential enhancements resulting from BGE's preliminary screening process (listed in Appendix F.2 of BGE's ER). The SAMAs include improvements oriented toward reducing the CDF and risk from major contributors specific to CCNPP; improvemerts identified as part of the NRC containment performance improvement program; several accident management strategies identified by NRC in Generic Letter 88-20, Supplement 2 (NRC 1990c); and improvements identified in previous severe accident mitigation design altematives (SAMDA) reviews for Watts Bar, Comanche Peak, and Limerick that would be applicable to CCNPP. The staff notes that while many of the SAMAs involve major modifications and significant costs, less expensive design improvements and procedure changes that provide similar levels of risk reduction are also included. The SAMAs also include a filtered containment vent and flooded rubble bed core retention device, which are cited specifically in NUREG-0660 (NRC 1980) for evaluation as part of Three Mile Island Task Action Plan item II.B.8. The staff concludes that the set of potential SAMAs considered by BGE is reasonably complete and comprehensive. October 1999 5-10 NUREG-1437, Supplement 1
i l l Postulated Accidents As mentioned previously, BGE performed a final screening by eliminating those SAMAs whose cost exceeded the maximum attainable benefit (estimated by BGE to be $2.3 million), and those hardware it ms having an estimated monetized benefit less than $40,000. AOSC were omitted in the original scrz:ning process (documented in the ER), but the impact of AOSCs was subsequently evaluated by l BGE in response to a staff request. The screening process and criteria appears reasonable. Th3 staff confirmed BGE's SAMA identification process by performing an independent screening of thos2 SAMAs remaining following BGE's preliminary screening, as described in Section 5.2.6. The staff's screening did not identify any hardware changes that were not already included within the 27 SAMAs identified by BGE. This includes the original 23 SAMAs identified by BGE, the three additional l SAMAs still under review by BGE at the time the ER was submitted, and the previously excluded SAMA l l r:l;ted to the installation of the PORVs (SAMA 77). Several SAMAs involving procedure improvements wara indicated to be cost-beneficial through the staffs screening. These SAMAs had been separately ! considered by BGE and eliminated in the final screening because (1) the improvement beyond the l curr2nt plant procedures assumed in the analysis is not realistically achievable, or (2) in the case of flood mitigation procedures, the procedure change would need to be re-evaluated following disposition of SAMA 66b (implement hardware modifications to prevent flood propagation). Elimination of these . SAMAs for the reasons provided by BGE appears reasonable. l 1 i Tho staff concludes that BGE has used a systematic and comprehensive process for identifying pot ntial design improvements for CCNPP, and that the set of potential design improvements identified by BGE and supplemented based on inclusion of AOSCs, is reasonably comprehensive and, therefore, l ccceptable.
> 5.2.3.3 Design improvements Evaluated in Detail by BGE A brief summary of the 27 improvements evaluated further by BGE and the anticipated benefits of each is provided in the discussion below. The numbers in parentheses correspond to the SAMA number in BGE's submittal. l Improvements Related to RCP Seal LOCAs (Loss of Component Coolina Water or Saltwate_r.)
. Modify the plant such that, during emergency conditions, the saltwater, service water, and component cooling water pumps automatically start when the operating pump fails (1a)- This would increase the time before the loss of component cooling in the loss of essential raw cooling water sequences and reduce the potential fv. RCP seal failure.
. Modify the plant such that, during normal operating conditions, the saltwater, service water, and component cooling water pumps automatically start when the operating pump fails (1b)- This would increase the time before the loss of component cooling water in the loss of essential raw cooling water sequences and reduce the potential for RCP seal failure. l NUREG-1437, Supplement 1 5-11 October 1999 l
Postul:ted Accid:nts
. Modify fire protection system piping to the ccmponent cooling water system to provide alternate cooling for the shutdown cooling heat exchangers, the safety injection pump, and RCP seals (5) -
This would reduce the impact of a loss of component cooling by providing a means to maintain the l reactor coolant pump seals after a loss of component cooling water.
)
. Implemen' procedures to stagger high-pressure safety injection pump use after a loss of saitwater l (96)- This would allow extended use of high-pressure safety injection after the Saltwater System ,
l loss, whica causes the emergency core cooling system (ECCS) pump room coolers to be lost. l Imorovements Related to Heatina. Ventilation. and Air Conditionina
. Install a redundant and diverse AFW pump room ventilation system that automatically starts on high l temperature (7) - This would improve the reliability of AFW when room cooling is lost.
Imorovements Related to Ex-Vessel Accident Mitiaation/ Containment Phenomena
. Install containment spray pump header automatic throttle valves (8) - This would extend the tiine over which water remains in the refueling water storage tank, when full spray flow is not needed.
l . Install a passive hydrogen ignition system (15) - This would reduce the potential for hydrogen detonations without requiring electric power.
. Upgrade the fire protection system and hard-pipe a connection to the containment spray system, such that the fire protection system can serve as a back-up source for containment spray (23) - This would provide a redundant source of water for containment spray, at a lower cost than a dedicated ,
system. lmorovements in Altematina Current (AC)/ Direct Current (DC) Power Reliability and Availability l Provide additional DC battery capability (31) - This would extend the availability of DC power when l battery charging is lost, thereby reducing the frequency of long-term station blackout core melt l sequences and other losses of 125V DC power core melt sequences. j . Use fuel cells instead of lead-acid batteries (32)- This would extend the availability of DC when l battery charging is lost, thereby reducing the frequency of long-term station blackout core melt l sequences and other losses of 125V DC power core melt sequences.
. Implement automatic cross-tie capability between 4kV buses 11 and 14 (33a). This would ensure that either bus experiencing an under-voltage condition would be fed automatically from the other bus, thereby improving AC power reliability.
October 1999 5-12 NUREG-1437, Supplement 1
)
Postulated Accid:nts e implement automatic cross-tie capability between 4kV buses 21 and 14 (33b). This would ensure that either bus experiencing an under-voltage condition would be fed automatica:!y from the other bus, thereby improving AC power reliability.
- Modify the plant such that a portable generator could be used to directly feed each of the four 125V DC buses (34) - This would reduce the likelihood of battery depletion, thereby reducing the frequency of long-term station blackout core melt sequences and other losses of 125V DC power l core melt sequences. l
= Replace batteries with a more reliable model (36)- This would improve DC power reliability, thereby reducing the frequency of station blackout core melt sequences and other losses of 125V DC power l core melt sequences. I
- Double the capacity of the fuel oil day tanks (38b)- This would extend the operability of the diesel generators, thereby reducing the frequency of long-term station blackout core melt sequences.
- Make the service water-cooled emergency diesel generators air-cooled (44) - This would eliminate the dependency of diesel generators on cooling water support systems, thereby reducing the frequency of station blackout core melt sequences.
- Use the fire protection system as a back-up source for diesel cooling (45) - This would provide a redundant source for diesel generator cooling, thereby reducing the frequency of station blackout core melt sequences.
) e Convert undsr-voltage, auxiliary feedwater actuation signal (AFAS), and reactor protective system high pressurizer pressure actuation signals to 3-out-of-4 logic (48a) - This would reduce the risk associated with 2/4 inverter failure, which was found to be a significant contributor to core damage frequency in the CCPRA.
- Operate with the power-operated relief valve block valves shut (48b)- This modification would increase the demands on the safety relief valves; however, the PORVs would be less likely to spuriously open and would still be available for feed-and-bleed.
- Add an automatic bus transfer feature that would automatically transfer the 120V vital AC bus from the online unit to the standby unit upon failure of the operating inverter (49) - This would eliminate the manual action currently required to place the standby unit online, thereby reducing the frequency of spurious safety system actuation sequences (SSSAs). l NUREG-1437, Supplement 1 5-13 October 1999
Postulated Accid:nts Imorovements in identifyino/Cooino with Containment Bvoass l e Install additional instrumentation for detecting intersystem LOCAs (59) - Installing pressure or leak monitoring instruments between the first two pressure isolation valves on low-pressure injection i lines, residual heat removal suction lines, and high-pressure safety injection lines, would reduce the potential for interfacing system LOCA events. Imorovements to Reduce Intemal Floodino Freauency l
. Implement intemal flood prevention and mitigation enhancements (e.g., watertight doors) to prevent l flood propagation (66b) - Installing a watertight door between the service water pump room and the adjacent fan room would prevent floods from propagating out of the service water pump room, as well as floods from passing into this room, and wou'd eliminate a significant portion of the risk from plant flooding.
Imorovements in Feedwater/ Feed-and-Bleed Reliability and Availability
- Install separate accumulators for the AFW cross-connect and block valves to separate this equipment from the constant bleed equipment (e.g., AFW flow control valves) (68) - This would enhance the operator's ability to operate the AFW cross-connect and block valves following a loss of airsupport.
l = Increase the capccity of Condensate Storage Tank (CST) 12 to contain 24 hours of AFW inventory for both units (69) - This would permit the operation of secondary side cooling for an extended l period, thereby reducing the frequency of long-term loss of feedwater core damage sequence, and < l other core damage sequences.
. Provide a means to cool the turbine-driven AFW pumps in a station blackout event (70) - This would permit the operation of AFW for an extended period, thereby reducing the frequency of long-term station blackout core melt sequences.
l . Automate demineralized water make-up to CST 12 (74)- Automating this function and providing a dedicated diesel generator for this purpose would permit continued inventory make-up to the CST l during a loss of offsite power, thereby reducing the frequency of long-term loss of feedwater core l melt sequences, as well as enhancing Service Water and Component Cooling Water System make-l up capabilities. Install high-capacity PORVs such that a single PORV is capable of providing adequate decay heat removal (77) - This would permit successful feed-and-bleed with operation of just one of the two PORVs, thereby improving the availability of feed-and-bleed. October 1999 5-14 NUREG-1437, Supplement 1
r l Postulated Accidnnts L l 5.2.4 Risk Reduction Potential of Design improvements l l The process used by BGE to determine the risk reduction potential for each enhancement is described l in Section 4.1.17.4 of the ER. This process involved determining the approximate effect that the design
- ch;nge would have on top events on the related event tree, reflecting that impact by modifying the j s
- ved sequences, and calculating a new value of CDF and total risk (expressed in terms of offsite population dose, offsite economic costs, onsite dose, and onsite economic costs). A spreadsheet was ured to total the plant damage states resulting from the various sequences, transfer the plant damage stita frequency to the appropriate release categories, and translate the release category frequencies into cach of the four risk impacts (offsite population dose, offsite economic costs, onsite dose, and onsita economic costs). The resulting risk impacts were subtracted from the base case risk imoacts to calculate the " averted" risk.
l BGE evaluated the risk reduction potential for each SAMA in a bounding fashion, i.e., each SAMA was tssumed to completely eliminate all sequences that the specific enhancement was intended to address. i A bounding approach was taken to reflect the generic nature of the initial SAMA concepts and to allow each SAMA benefit to be calculated using " saved sequences" rather than requantifying the CCPRA. As a result of these bounding approximations, the benefits are generally overestimated. A more detailed evaluation of a specific enhancement may result in a significant reduction in the estimated benefit. BGE's basis for estimating the risk reduction for each design improvement is given in BGE (1998a). Th3 corresponding risk reduction estimates (core damage frequency reduction and offsite dose l r; duction) are listed in Table 5-5. l l The staff has reviewed BGE's bases for calculating the maximum risk reduction for the various design ! improvements. The staff notes that BGE used judgment in assessing the impact of each design change l with regard to estimating averted offsite risk on the CCNPP risk profile. However, the rationale and ) essumptions on which the risk reduction estimates are based are reasonable and generally l conservative. Accordingly, the staff based its estimates of averted risk for the various SAMAs on BGE's risk reduction estimates. I 5.2.5 Cost impacts of Candidate Design Improvements BGE's method for determining costs for each potential design enhancement is described in Section 4.1.17.3 of the ER. The cost analyses for specific SAMAs are documented in Appendix F.4 of the ER. Revised cost estimates for several SAMAs are provided in the response to the NRC request l for cdditional information (RAI), and in the presentation materials provided during a January 7,1999, l meeting with BGE (NRC 1999). BGE developed cost estimates for each implementation option from either a site-specific cost estimate, cstimates from other licensee submittals, or through application of engineering judgement. The sits-specific estimates consider seven major cost categories (BGE labor, labor burden, material, NUREG-1437, Supplement 1 5-15 October 1999
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r Postulated Accidents l mit: rial handling, equipment maintenance, indirect supervision and engineering, and allowance for funds used during construction) with subcategories defined by the requirements of the proposed enh ncement (e.g., development of training, nuclear regulatory matters, equipment qualification). To provide common grounds for comparison with the monetized benefits values, implementation cost estimates were calculated based on a single-unit implementation basis. The costs did not include the cost of replacement power during extended outages required to implement the modifications and did not g:nerally include contingency costs associated with unforeseen implementation obstacles. Estimates based on modifications that were implemented or estimated in the past were presented in t:rms of dollar values at the time of implementation (or estimation) and were not adjusted to present-day dollars. Th3 staff notes that a number of simplifying assumptions appear to have been employed in developing ths cost estimates. On balance, however, the staff detected no systematic bias in the resulting cost l estimates due to reliance on these assumptions. For example, failure to include replacement energy costs, contingencies, and present-day dollars would tend to understate costs, whereas, calculations bas d on a single-unit implementation basis are likely to overstate the actual per-unit cost. l Tha costs for several SAMAs were singled out for review based on the estimated net value, and the pot:ntial for significant risk reduction for these SAMAs, specifically SAMAs 45,48a,49, and 77. For l certain improvements, the staff also compared BGE's cost estimates with estimates developed cis where for similar improvements, even though the bases for some of these cost estimates were d;fferant. The staff considered the cost estimates developed as part of the evaluation of design improvements for operating reactors (Watts Bar, Comanche Peak, and Limerick) and for the evolutionary advanced light-water reactors. In general, BGE's cost estimates are judged to reflect valid bases and assumptions, and their accuracy is considered sufficient to provide a reasonable and appropriate basis for the SAMAs analyses, given 1 the uncertainties surrounding the underlying cost estimates and the level of precision necessary considering the greater uncertainty inherent on the benef,t side, with which these costs were compared. . Accordingly, the staff adopted BGE's cost estimates for the various candidate improvements. l l 5.2.6 Benefit-Cost Comparison Th3 benefit-cost comparison as evaluated by BGE and the staffs evaluation of the benefit-cost analysis ara d scribed in the following sections. 5.2.6.1 BGE Evaluation l i The methodology used by BGE to perform the CCNPP MMA analysis was based primarily on NRC's guidance for performing benefit-cost analysis, i.e., NUREG/BR-0184, Regulatory Analysis Technical Evaluation Handbook. In accordance with the guidance, BGE estimated the " net value" added by each October 1999 l NUREG-1437, Supplement 1 5-17
Po:tulat:;d Accidents SAMA to determine whether any of the SAMAs would be cost-beneficial. The net value is the sum of the dollar equivalents for each severe accident impact (offsite population exposure, offsite economic costs, onsite dose, and onsite economic costs) minus the cost of implementing the SAMA. If the net value of a SAMA is negative, the cost of implementing the SAMA is larger than the benefit associated ) with the SAMA and is not considered cost-beneficial. i BGE calculated the net value for each SAMA using the following formula: Net Value = (APE + AOC + AOE + AOSC) - COE where APE = present value of averted public exposure ($) AOC = present value of averted offsite property damage costs ($) l AOE = present value of averted occupational exposure ($) l AOSC = present value of averted onsite costs ($) COE = cost of enhancement ($) The derivation of each of these factors is discussed below. Averted Public Exoosure APE costs were calculated using the following formula: APE = Annual reduction in public exposure risk (Aperson-rem / reactor-year) x monetary equivalent of unit dose x present value conversion factor l BGE estimated the annual reduction in public exposure risk for each SAMA. The reduction in public l exposure (person-rem per year) was converted to a monetary equivalent by applying NRC's conversion factor of $2000 per person-rem, and then discounting the monetary equivalent to present value. A 20-year period for the license renewal period and a 7 percent real discount rate was assumed, resulting in a present value conversion factor of 10.76 for the base case. As stated in NUREG/BR-0184, it is important to note that the monetary value of public health risk after discounting does not represent the expected reduction in public health risk due to a single accident. Rather, it is the present value of a stream of potential losses extending over the remaining lifetime (in l this case, the renewal period) of the facility. Thus, it reflects the expected annual loss due to e single accident, the possibility that such an accident could occur at any time over the renewal period, aed the , effect of discounting these potential future losses to present value. I October 1999 5-18 NUREG-1437, Supplement 1
l Postulit:d Accid:nts l Aserted Offsite Property Damaae Costs '- l AOCs were calculated using the following formula: AOC = E{ [ Release category frequency with SAMA - release category frequency without SAMA]
. x offsite economic costs associated with release category}
x present value conversion factor BGE determined the offsite economic costs for each containment release category using the'MACCS code. AOCs are the product of the change' the release category frequency and the offsite economic l costs for each release class, summed over all release categories. Calculated values for offsite . cconomic costs were discounted to present value in the same manner as for public exposure. Averted Occustional Exoosure AOE was calculated using the following formula: AOE = Annual CDF reductit.n x occupational exposure per core-damage event x present value conversion factor BGE derived the values for averted occupational exposure based on inforr.ation provided in Section 5.7.3 of NUREG/BR-0184. Immediate occupational dose (3300 person-rem) and long-term , occupational dosc (20,000 person-rem over a 10-year cleanup period) were used for best estimate l l p vilues. The present value of these doses was calculated using equations provided in the handbook, in l conjunction with a monetary equivalent of unit dose of $2000 per person-rem, a real discount rate of 7 percent, and a time period of 20 years to represent the license renewal period. Averted Onsite Costs AOSCs include averted cleanup and decontamination costs, and averted power replacement costs. l l BGE derived the values for AOSCs based on information provided in Section 5.7.6 of the regulatory [ entlysis handbook. Averted cleanup costs (ACC) are calculated using the following formula-l ACC = Annual CDF reduction x present value of cleanup costs per core-damage event x present value conversion factor
' Th3 net present value for cleanup and decontamination of a severe accident is given as $1.1 billion in NUREG/BR-0184 (discounted over 10 years). ' Use of a discount factor of 10.76 to account for the 20-year license renewal period yields an integrated cleanup cost of $12 billion. This value was i
NUREG-1437, Supplement 1 5-19 October 1999
Postulated Accidents l 1 multiplied by the annual reduction in core damage frequency to obtain the averted cleanup costs portion l of the AOSCs. l Long-term replacement power costs (Ung) are calculated using the following formula: Unp = Annual CDF reduction x present value of replacement power for a single event x fa'ctor to account for remaining service years for which replacement power is required x reactor power scaling factor in accordance with guidance provided in Section 5.7.6.2 of NUREG/BR-0184, BGE estimated the net present value of replacement power for a single event to be $9.73x108, based on a real discount rate of 7 percent end a 20-year license renewal period. This value was multiplied by a factor of 8.1 to obtain a summation of the single-event costs over the entire license renewal period. After applying a correction factor to account for CCNPP's size relative to that of the generic reactor described in NUREG/BR-0184, l the Unp were determined to be $7.3 billion. This value was multiplied by the annual reduction in core l damage frequency to obtain the averted replacement costs portion of the AOSCs. l Although BGE calculated AOSCs, they chose to omit AOSCs as a benefit in the original screening and value-impact analysis submitted in the ER. Onsite property damage costs associated with cleanup and decontamination were not included on the basis that such costs are covered by property damage insurance. Replacement power costs were not included as an onsite economic cost on the basis that such costs are unlikely to be incurred by the utility in a deregulated energy market. None of the SAMAs l were found to have a positive net value when AOSCs are omitted. To explore the sensitivity of the results to changes in the discount rate, BGE also recalculated the net value of the 10 most promising l SAMAs (those having the highest net values) using a 3-percent discount rate in place of the 7-percent discount rate used in the base case analysis. Reducing the discount rate increases the net value of potential SAMAs and reorders their ranking, but the net value for each of the top 10 SAMAs remained negative even at the lower discount rate. l In response to a staff request, BGE provided a subsequent reassessment in which AOSCs were included as benefits. This information is described in the response to the RAI, and supplemented in the presentation materials from the January 7,1999, meeting with BGE (NRC 1999a). BGE reviewed each 1 of the 23 SAMAs identified in Table 4-3 of the ER to determine the revised net values when AOSCs are included as benefits. Additionally, BGE revisited the benefit estimates for all SAMAs that were screened out from consideration because the cost of enhancement exceeded the maximum possible benefit. Revised cost estimates were also developed for several SAMAs. An updated list of the 10 SAMAs with highest net values was developed. The updated list includes 9 of the 23 SAMAs identified in Table 4-3 of the ER, plus 1 SAMA originally excluded because of a high implementatioa cost. ' October 1999 5-20 NUREG-1437, Supplement 1
Postulated Accidents Fivs of the top 10 SAMAs have a positive net value when AOSC are included and bounding risk l reduction benefits are assumed. The remaining 5 SAMAs have a negative net value, even after including these conservative factors. Consequently, BGE performed a more-detailed evaluation of the ben: fits associated with these SAMAs. This evaluation attempted to (1) remove some of the conservatism in the bounding analysis by establishing a best-estimate benefit; (2) account for the impact of several changes to the CCNPP plant model that were recommended based on a contractor r: view of the model, but not implemented in the CCPRA used for the SAMA analysis; and (3) account for design differences between Unit 1 and Unit 2 with regard to emergency diesel generator support syst:ms. For each SAMA, a lower bound CDF estimate, representing the minimum benefit that could be expected, was established quantitatively using the saved sequences. (The upper bound CDF sstimate was based on the bounding estimate used in the original SAMA analysis.) The best estimate risk reduction value was qualitatively established based on consideration of the degree of conservatism built into the lower-bound and upper-bound estimates. The best-estimate benefits were also adjusted to account for possible changes in the economic and evacuation time assumptions used in the MACCS analysis. Specifically, the estimates of averted offsite costs were doubled to bound possible changes to ths economic input data due to inflation, and the estimates of averted public exposure were doubled to bound increased evacuation times resulting from increased population. The three SAMAs that were still being reviewed by BGE at the time the ER was submitted were not included within the set of SAMAs discussed above. The results of BGE's further evaluation of the three SAMAs was provided in BGE (1998c). BGE has determined that one of these SAMAs may be cost- l ben:ficial when evaluated under the assumptions used in the ER, i.e., neglecting AOSCs. This SAMA l (66b), which involves installing a watertight door between the service water pump room 'and the adj cent fan room to reduce risk from internal flooding, is being considered under CCNPP's I modification process. A second SAMA (49), which involves adding an automatic bus transfer feature, ! was found to be cost-beneficial when AOSCs are included, and was further evaluated under best- l cstimate assumptions. BGE concluded that based on the small positive net value and the fact that the l estimated benefits are conservative when applied to this SAMA, this SAMA is not risk-beneficial. The remaining SAMA (96), which involves a procedure change to stagger high-pressure safety injection i l pump operation after a loss of saltwater cooling, was eliminated based on adverse safety impacts. l BGE's estimates of the net values for the top 10 SAMAs are presented in Table 5-5 for both bounding and best-estimate risk reduction values, and with and without AOSCs. Information related to the three l additional SAMAs evaluated by BGE is also included. All SAMAs have a negative net value when i AOSCs are not included. When AOSCs are included, SAMAs 34,36,48a,49,74, and 77 were found to l be cost-beneficial under bounding risk reduction assumptions. Under best-estimate assumptions, the n:t value remains positive for only SAMAs 36,48a, and 74, but SAMA 68 also becomes cost-beneficial. The net value for certain SAMAs (including SAMA 68) is greater under best-estimate assumptions than und:r bounding assumptions due to the combined effect of doubling APE and AOC benefits and accounting for modeling changes and Unit 1/ Unit 2 differences in the best-estimate case. NUREG-1437, Supplement 1 5-21 October 1999
Postulated Accidents l BGE dispositioned certain SAMAs based on their net values under the best-estimate assumptions. BGE concluded that implementation of SAMAs 7, 34, 38b,45,48b,49, and 77 is not justified under best-estimate assumptions since these SAMAs have a negative net value irrespective of whether l AOSCs are included. SAMAs 36,48a,68, and 74, which were found to have a positive net value when l AOSCs were included, were dispositioned on the basis of other considerations. SAMA 36, " Replace batteries with a more reliable model," was judged to be not feasible, based on the reliability record of modern lead-acid batteries, and the unproven reliability of other battery designs. SAMA 48a, " Convert under-voltage, AFAS block, and high pressurizer pressure logic to 3-out-of-4 logic," was judged to have a negative net value when all of the costs of the regulatory aspects of the modification are taken into account. (Some, but not all regulatory costs were included in BGE's cost estimate.)
. SAMA 68, " Install separate accumulators for the AFW cross-connect and AFW block valves," has a .
l positive net value only when AOSCs are included in the analysis. BGE's position is that replacement power costs and insured onsite property costs are not appropriate considerations for a NEPA analysis, such as the SAMA analysis.
. SAMA 74, " Automate demineralized water (DW) make-up to condensate storage tank," has a l positive net value only when AOSCs are included in the analysis. BGE's position is that replacement power costs and insured onsite property costs are not appropriate considerations for a NEPA analysis, such as the SAMA analysis.
Based on the above factors, BGE has decided not to pursue any of these SAMAs further. The staff independently considered these SAMAs further as discussed in the next section. l 5.2.6.2 Staff Evaluation The methodology used by BGE to perform the CCNPP value-impact analysis was based primarily on NUREG/BR-0184 (NRC 1997b). The only noted difference in BGE's analysis concemed omission of l AOSCs in the SAMA analysis contained in the ER. The NRC's regulatory analysis guidelines in NUREG/BR-0184 consider a societal perspective in the performance of regulatory analyses and state that AOSCs, including cleanup and decontamination costs and replacement power costs, should be treated as benefits in the value impact analysis. The Commission reaffirmed the NRC staff treatment of AOSCs in regulating analyses by an SRM to SECY-99-169 (NRC 1999b). According to the regulatory analysis guidelines, insurance payments are transfer payments that do not involve consumptive use of real resources, and therefore are not a relevant basis for excluding AOSC. Similarly, NUREG/BR-0184 states that replacement power costs should be included as impacts. This handbook also states that l where consideration of AOSCs is expected to alter or significantly affect results, the results should be October 1999 5-22 NuREG-1437, Supplement 1
Postulated Accid:nts calculated with and without AOSCs, so that the decisionmaker is fully aware of its overall effect on the l ; benefit and cost considerations of the altematives. In view of the significant impacts of AOSCs, the staff l ] his chosen to display SAMA results both with and without AOSCs. l Th3 staff confirmed BGE's SAMA identification process by performing an independent screening of those SAMAs remaining following BGE's preliminary screening. The staff estimated the net value for each SAMA with and without AOSCs. In accordance with the regulatory analysis guidance, the staff l c::umed a present worth discount rate of 7 percent for the base case, and performed a sensitivity case casuming a 3 percent discount rate. The staff relied on BGE's bounding estimates of core damage frequency and offsite consequence reduction (provided in BGE 1998a), BGE's cost estimates for each SAMA (provided in BGE 1998a and 1998c), and the handouts from the January 7,1999 (NRC 1999a), public meeting with BGE. The staff used bounding risk reduction estimates to account for uncertainties in the analysis because BGE did not submit documentation on the process and assumptions used to l d velop best-estimate values. The staff included adjustment factors provided by BGE to account for difftrences in risk contributors between Unit 1 and Unit 2 because these factors led to significantly l greater benefits for Unit 2 for certain SAMAs (i.e., those involving improvements to the emergency l diesel generators (EDGs) and their support systems). The staff determined these values based on the l cost information provided by the applicant (BGE 1998a and 1998c). The staff did not double the benefits associated with APE and AOC, as assumed in BGE's analysis, since these benefits were found to be small relative to other benefits, particularly AOSCs. Procedure improvements were included in l tha screening and conservatively assigned a zero cost of implementation. The staff identified those SAMAs having a positive net value greater than $100,000 and compared them to the 13 SAMAs id:ntified by BGE (the 10 having greatest net benefit, plus the three that were still under evaluation at th3 time the ER was submitted).
- The staff's screening identified the same six SAMAs that BGE found cost-beneficial under bounding risk reduction assumptions, and did not identify any hardware changes that were not already included within tha set of SAMAs identified by BGE. However, several SAMAs involving procedure improvements were indicated to be cost-beneficial through the staffs screening. These were SAMA 35 - Increase / improve DC bus load shedding.
SAMA 41 - Develop a severe weather conditions procedure. SAMA 66a - Enhance procedures to improve flood mitigation guidance. SAMA 71 - Enhance procedures for local-manual operation of AFW. SAMA 80 - Implement a refueling water storage tank make-up procedure. SAMA 82 - Ensure that the plant air compressors are diesel generator backed. l These SAMAs had been separately considered by BGE and eliminated in the final screening because (1) the intent of the SAMA is already addressed by current plant procedures, (2) the improvement assumed in the bounding analysis is not realistically achievable, (3) changes to some of these
. procedures could increase risk from other contributors, or (4) in the case of flood mitigation procedures, NUREG-1437, Supplement 1 5-23 October 1999 l
Postul ted Accid':nts the procedure change would need to be re-evaluated following disposition of SAMA 66b (implement hardware modifications to prevent flood propagation). The staff notes that the risk reduction values assumed for these SAMAs in the bounding evaluation were extremely conservative and that the risk reduction that can realistically be achieved is minimal, given that plant procedures are already in place at CCNPP in each of the above areas. The material provided during the January 7,1999, meeting with BGE (NRC 1999a) documents additional information l regarding the current procedures that address these areas. BGE has indicated that the need to modify l flood mitigation procedures will be re-evaluated following disp ~osition of SAMA 66-b and revision of the FLOOD module of the CCPRA. Elimination of the other procedure-related SAMAs for the reasons provided by BGE appears reasonable. Based on review of the screening resuits, the staff notes the following:
. AOSCs are the single most important factor in the analysis. No SAMAs are cost-beneficial when AOSCs are not included, but several SAMAs are cost-beneficial when AOSCs are included in the analysis in accordance with NUREG/BR-0184.
l . Onsite cleanup and decontamination costs typically account for about two-thirds of the total AOSCs, with replacement power costs accounting for the balance. Although replacement power costs l represent only one-third of the AOSCs, these costs are still substantial (typically, several hundred thousand dollars after adjustment for frequency for possible cost-beneficial SAMAs). As mentioned l above, six SAMAs become cost beneficial when AOSCs (both onsite cleanup and decontamination costs and replacement power costs) are included in the analysis, if only the onsite cleanup and l decontamination component of AOSCs is included in the analysis, and replacement power costs are neglected, the net value for several of these SAMAs would remain negative. However, several SAMAs would continue to be cost beneficial under bounding assumptions (SAMA 34,36,48a,49) and best estimate assumptions (SAMA 36,48a).
. Use of a 3 percent discount rate increases net values, but does not lead to identification of any cost-beneficial SAMAs beyond those already identified by BGE.
. The effect of implementing the SAMA in the near term rather than delaying implementation until the start of the license renewal period (i.e., use of a 35-year rather than a 20-year period in the value impact analysis) is bounded by the sensitivity study that assumed a 3-percent discount rate.
The staff assessed in more detail the six potentially cost-beneficial SAMAs, recognizing the uncertainties inherent in the benefit / cost analysis and the screening nature of the analysis. A summary of this assessment, which was based on both probabilistic and deterministic considerations, follows. October 1999 5-24 NUREG-1437, Supplement 1
Postulat:d Accid:nts
' Incorporate an Altemate Batterv Charaina Capab'lity i (34)
' This proposed enhancement involves providing a portable diesel-driven generator that could be used to provide battery charging during station blackout conditions. The generator would be connected using the cxisting plant switchgear for the battery charger via temporary cables; a breaker would be racked out, the power feed to the battery charger would be disconnected, and the diesel generator connected in its place. With implementation of this enhancement, all long-term battery functions would be enhinced if the short-term functions are successful.
B: sed on the bounding risk-reduction estimate, BGE estimated that this enhancement would result in a 4 percent (1.5x10 4/ reactor-year) reduction in total CDe, and a 3 percent (2 person-rem / reactor-year) reduction in offrite dose. This assumes that the 125V bus will be available for 24 hours, given that the l 125VDC batteries operate in the short term; loss of offsite power events in excess of 4 hours are climinated; the likelihood of the 480 VAC buses experiencing common cause failure is significantly reduced; and the benefit is reduced by 20 percent to account for the possible failure of operators to
. r: cognize the failure of the installed battery chargers and to manually connect the portable chargers to s the effected bus. The licensee's best-estimate risk reduction is approximately half of the bounding vilue.
Tha staff agrees that a portable diesel-driven battery charger would significantly enhance the availability
- of DC power for a longer time. However, batteries alone do not ensure the ability to cope with a long-t:rm station blackout. The continued availability of condensate inventory, compressed air, heating, v:ntilation, and air conditioning and reactor inventory would also need to be ensured. These aspects would not generally be accounted for in the approach used by BGE to estimate risk reduction, i.e., use of saved sequences. The actual risk reduction would be significantly less than the bounding estimate, and the net value for this SAMA becomes negative when these factors are considered. The staff concludes that this improvement is not warranted because of the practical limitations on the cffectiveness of this design improvement, and the relatively small estimated risk reduction that would be cchieved under more realistic modeling assumptions.
Reolace Batteries with a More Reliable Model_(36) This proposed enhancement involves replacing the existing batteries at CCNPP with new batteries, which are more reliable. With more reliable 125 VDC batteries, the frequency of station blackout and ov;rcli plant risk can be reduced.' B: sed on the bounding risk-reduction estimate, BGE estimated that this enhancement would result in a 9 percent (2.8x10 4/ reactor-year) reduction in total CDF, and a 5 percent,0.036 person-Sv (3.6 person-rcm)/ reactor-year reduction in offsite dose. This assumes that all short-term battery failures and all 125 VDC bus failures at power are eliminated. The applicant's best-estimate risk reduction is approximately NUREG-1437, Supplement 1 5-25 October 1999
Postulated Accidents 75 percent of the bounding value. BGE noted that lead-acid batteries have been proven to be one of the most reliable large storage cell designs available; high specific gravity round cells installed at some plants have not proven to be more reliable than lead-acid batteries; and BGE's current requirements for weekly, quarterly, and biennial surveillance ensure an acceptable level of battery reliability. The staff acknowledges that BGE's risk reduction estimates for this SAMA are appreciable, and that the SAMA has a positive net value under both bounding and best-estimate risk reduction assumptions l when AOSCs are included. However, the level of risk reduction assumed in the analysis does not j appear to be achievable, given that there are no obvious options that have proven to be more reliable than the currently installed lead-acid batteries. The actual risk reduction may be significantly less than the bounding estimate when these factors are taken into consideration. The staff concurs with BGE's
~
arguments concerning this enhancement, and concludes that implementation of the improvament for license renewalis not warranted because of the practical limitations on its effectiveness and the relatively small estimated risk reduction that would be achieved under more realistic modeling assumptions. Chanae Under-voltaae. AFAS Block. and Hiah Pressurizer Pressure Actuation Sianals to 3-out-of-4 Loaic (48a) This proposed enhancement involves modifying the logic of the Under-Voltage, AFAS block, and High l Pressurizer Pressure Actuation signals. The existing engineered safety features actuation system, AFAS, and Pressurizer Pressure logic modules, which are based on 2-out-of-4 logic, would be replaced I with new modules based on 3-out-of-4 logic. This modification would prevent an SSSA, which is one of the most risk-significant contributors in the CCPRA model. The change to a 3-out-of-4 logic offers an advantage of preventing a spurious actuation upon failure of 2 channels in the tripped condition, but has the disadvantage of preventing actuation if 2 channels failin the untripped condition. In either case, the system will perform correctly with a single failure. I The staff notes that the current CCNPP design meets the single failure criteria and that licensed operators at CCNPP have received training (including simulator training) in the appropriate response to l an SSSA event. However, based on the bounding risk-reduction estimate, BGE estimated that this l enhancement would result in a 30 percent (9.1E-5/ reactor-year) reduction in total CDF, and a 17 l percent,0.11 person-Sv (11 person-rem)/ reactor-year reduction in offsite dose. This estimate conservatively assumes that all failures of 120V vital AC panels,125 VDC buses, and operator actions l to align inverters to back-up power are eliminated. The licensee's best-estimate risk reduction is approximately one-third of the bounding value. The SAMA has a positive net value under both l bounding and best-estimate risk reduction assumptions when AOSCs are included. Although predicted to offer a significant risk reduction, the implementation of the SAMA may reduce the ability of the trip system to respond correctly with two failures, or a bypass and a failure. BGE appears to have considered this concern, as indicated by their statement that the risk benefit to be achieved by October 1999 5-26 NUREG-1437, Supplement 1
Postulated Accidents preventing this event from occurring exceeds the risk benefit to be expected from modifying the actuation logic, but further review would be required. The NRC would require additionaljustification and regulatory review to ensure that this change in logic will not unacceptably reduce the ability l of the trip system to respond correctly. BGE notes that implementation of this change is expected to involve a 10 CFR 50.59 evaluation, an Unreviewed Safety Question submittal (USQ), and a revision to the CCNPP l tschnical specifications. An estimate of the regulatory costs ($100,000) was included in the estimated cost of th:s SAMA, but the actual costs could vary significantly. Although this SAMA appears to be cost beneficial, it does not relate to adequately managing the effects of aging during the period of extended operation and therefore, will not need to be implemented as pa of license renewal pursuant to 10 CFR Part 54. Add Automatic Bus Transfer Feature to Transfer Between Either the Back-uo Bus or the Standby inverter on the Failure of the Operatino inverter (49) Upon failure of two 120 VAC vital panels, all engineered safety features actuation system, AFAS, and reactor protection system actuation modules trip. Tripping of these modules could lead to the risk-significant SSSA scenario d4 cussed above This SAMA involves the addition of an automatic transfer switch (ATS) feature that would automatically transfer between either the back-up bus or the standby inverter upon the failure of the operating inverter. This would minimize the potential for loss of power from a 120 VAC vital panel, and thereby reduce the frequency of the SSSA scenario. While an ATS feature minimizes the loss of power to two 120 VAC vital panels, thereby reducing the CDF from SSSA scenarios, it also has some disadvantages. One disadvantage of an ATS feature is if failure of the operating inverter is caused by a fault on the bus or on the bus load side circuitry, pla the back-up inverter on the same bus could result in damage or failure of the back-up inverter. Another disadvantage is the potential for a failure of the ATS feature that could result in loss of both inverters. Measures must be taken for the circuitry and hardware designs along with the installation of an ATS feature to ensure that these disadvantages are adequately addressed. l l The staff notes that the current CCNPP design meets the single-failure criteria and applicable } regulations regarding loss of vital AC, and that loss of power from two 120 VAC vital panels is beyond l the design and licensing bases for the plant. Furthermore, the licensed operators at CCNPP have received training in the appropriate response to an SSSA event. ! I BGE estimated the risk reduction potential for SAMA 49 using the same assumptions used for l evaluating SAMA 48a, since both SAMAs address the same scenario (i.e., an SSSA scenario). Use of l benefit estimates for SAMA 48a is conservative since these benefit estimates do not accou ! potential failure mechenisms for the ATS. Under bounding assumptions, this enhancement would result in a 30 percent (9.1x10~5/ reactor-year) reduction in total CDF, and a 17 percent,0.11 l person-Sv (11 person-rem)/ reactor-year reduction in offsite dose. Under best-estimate assumptions, the risk reduction NUREG-1437, Supplement 1 5-27 ! October 1999
Postulated Accid:nts l is approximately one-third of the bounding value. When AOSCs are included, the SAMA has a positive net value under bounding risk reduction assumptions, but a negative net value under best-estimate risk reduction assumptions. (in the latter case, the net value for Unit 2 is slightly positive, but is offset by a larger negative net value for Unit 1.) Based on the above, implementation is not warranted. Automate Demineralized Water Make-Up to Condensate Storace Tank (74) l This proposed enhancement involves modifying the DW make-up to CST 12 such that it automatically makes up on the low water level in the tank, and providing a dedicated non-safety related electric diesel generator, which would automatically start and supply power to the make-up pump and associated control valves. This enhancement will improve the reliability of make-up to the service water and component cooling water head tanks (by making the demineralized water transfer pumps diesel-backed), and eliminate operator actions to align a long-term AFW supply (by designing the demineralized water make-up to automatically open on low water level in CST 12). < l Based on the bounding risk-reduction estimate, BGE estimated that this enhancement would result in a 5 percent (1.7x10-5/ reactor-year) reduction in total CDF, and a 3 percent, 0.02 person-Sv (2 person-rem)/ reactor-year reduction in offsite dose. This conservatively assumes that long-term AFWwater supply, as well as service water and component cooling water head tank make-up, are always successful. The licensee's best-estimate risk reduction is approximately 60 percent of the bounding value. This SAMA has a positive net value under both bounding and best-estimate risk reduction assumptions when AOSCs are included. l The staff acknowledges that this enhancement has a positive net value; however, it does not relate to adequately managing the effects of aging during the period of extended operation and therefore, will not need to be implemented as part of license renewal pursuant to 10 CFR Part 54. Increase PORV Size So That Only One PORV is Reauired for Successful Feed-and-Bleed (77) This proposed enhancement involves replacing the existing PORVs, block valves, and associated discharge piping, such that only a single PORV is required to provide adequate decay heat removal. This would substantially improve the reliability of feed-and-bleed cooling since only 1-of-2 rather than 2-of-2 PORVs would be required for success. A similar modification was made to the Palisades plant in 1989, at a cost of $2.7 million, and was used as the basis for BGE's cost estimates for this SAMA. Based on the bounding risk-reduction estimate, BGE estimated that this enhancement would result in a 46 percent (1.5x10"/ reactor-year) reduction in total CDF, and a 45 percent,0.31 person-Sv (31 person-rem)/ reactor-year reduction in offsite dose. This benefit is based on the conservative assumption that all AFW hardware and human-action-related failures are eliminated. The licensee's best-estimate risk reduction is approximately half of the bounding value. October 1999 5-28 NUREG-1437, Supplement i
l Postulated Accidents i pr venting this event from occurring exceeds the risk benefit to be expected from modifying the cctuation logic, but further review would be required. The NRC would require additional justification and rcgulatory review to ensure that this change in logic will not unacceptably reduce the ability of the trip l
]
system to respond correctly. BGE notes that implementation of this change is expected to involve a 10 CFR 50.59 evaluation, an Unreviewed Safety Question submittal (USQ), and a revision to the CCNPP l ; t:chnical specifications. An estimate of the regulatory costs ($100,000) was included in the estimated cost of this SAMA, but the actual costs could vary significantly. Although this SAMA appears to be cost beneficial, it does not relate to adequately managing the effects of aging during the period of extended operation and therefore, will not need to be implemented as part - of license renewal pursuant to 10 CFR Part 54. Add Automatic Bus Transfer Feature to Transffr Between Either the Back-up Bus or the Standby Inverter on the Failure of the Operatino invertel(49) Upon failure of two 120 VAC vital panels, all engineered safety features actustion system, AFAS, and rarctor protection system, actuation modules trip. Tripping of these modules could lead to the risk-significant SSSA scer.Mo discussed above. This SAMA involves the addition of an automatic transfer switch (ATS) feature that would automatically transfer between either the back-up bus or the standby I inv:rter upon the failure of the operating inverter. This would minimize the potential for loss of power from a 120 VAC vital panel,gnd thereby reduce the frequency of the SSSA scenario. (4 While an ATS feature minimaes the loss of power to two 120 VAC vital panels, therety reducing the CDF from SSSA scenarios, it also has some disadvantages. One disadvantage of an ATS feature is if failure of the operating inverter is caused by a fault on the bus or on the bus load side circuitry, placing ths back-up inverter on the same bus could result in damage or failure of the back-up inverter. Another disadvantage is the potential for a failure of the ATS feature that could result in loss of both inverters. M:asures must be taken for the circuitry and hardware designs along with the installation of an ATS feature to ensure that these disadvantages are adequately addressed. l Tha staff notes that the current CCNPP design meets the single-failure criteria and applicable regulations regarding loss of vital AC, and that loss of power from two 120 VAC vital panels is beyond ths design and licensing bases for the plant. Furthermore, the licensed operators at CCNPP have received training in the appropriate response to an SSSA event. l BGE estimated the risk reduction potential for SAMA 49 using the same assumptions used for evaluating SAMA 48a, since both SAMAs address the same scenario (i.e., an SSSA scenario). Use of l benefit estimates for SAMA 48a is conservative since these benefit estimates do not account for pot:ntial failure mechanisms for the ATS. Under bounding assumptions, this enhancement would result in a 30 percent (9.1 x104 / reactor-year) reduction in total CDF, and a 17 percent,0.11 person-Sv (11 l person-rem)/ reactor-year reduction in offsite dose. Under best-estimate assurnptions, the risk reduction l NUREG-1437, Supplement 1 5-27 October 1999 l
Postul:t d Accidents l is approximately one-third of the bounding value. When AOSCs are included, the SAMA has a positive net value under bounding risk reduction assumptions, but a negative net value under best-estimate risk , reduction assumptions. (in the latter case, the net value for Unit 2 is slightly positive, but is offset by a l larger negative net value for Unit 1.) Based on the above, implementation is not warranted. I Automate Demineralized Water Make-Uo to Condensate Storaoe Tank (74) l l This proposed enhancement involves modifying the DW make-up to CST 12 such that it automatically makes up on the low water level in the tank, and providing a dedicated non-safety related electric diesel generator, which would automatically start and supply power to the make-up pump and associated control valves. This enhancement will improve the reliability of make-up to the service water and component cooling water head tanks (by making the demineralized water transfer pumps diesel-backed), and eliminate operator actions to align a long-term AFW supply (by designing the demineralized water make-up to automatically open on low water level in CST 12). Based on the bounding risk-reduction estimate, BGE estimated that this enhancement would result in a 5 percent (1.7x10'5/ reactor-year) reduction in total CDF, and a 3 percent,0.02 person-Sv (2 person-rem)/ reactor-year reduction in offsite dose. This conservatively assumes that long-term AFW water supply, as well as service water and component cooling water head tank make-up, are always successful. The licensee's best-estimate risk reduction is approximately 60 percent of the bounding value. This SAMA has a positive net value under both bounding and best-estimate risk reduction assumptions when AOSCs are included. l The staff acknowledges that this enhancement has a positive net value; however, it does not relate to adequately managing the effects of aging during the period of extended operation and therefore, will not need to be implemented as part of license renewal pursuant to 10 CFR Part 54. Increase PORV Size So That Only One PORV is Reouired for Successful Feed-and-Bleed (77) This proposed enhancement involves replacing the existing PORVs, block valves, and associated discharge piping, such that only a single PORV is required to provide adequate decay heat removal. This would substantially improve the reliability of feed-and-bleed cooling since only 1-of-2 rather than 2- f of-2 PORVs would be required for success. A similar modification was made to the Palisades plant in 1989, at a cost of $2.7 million, and was used as the basis for BGE's cost estimates for this SAMA. Based on the bounding risk-reduction estimate, BGE estimated that this enhancement would result in a i 46 percent 1.5x10d/ reactor-year) reduction in total CDF, and a 45 percent,0.31 person-Sv (31 person-
$ I rem)/ reactor-year reduction in offsite dose. This benefit is based on the conservative assumption that I l all AFW hardware and human-action-related failures are eliminated. The licensee's best-estimate risk reduction is approximatdy half of the bounding value.
October 1999 5-28 NUREG-1437, Supplement 1 l
Postulated Accidents Tha SAMA has a positive net value under bounding risk reduction assumptions when AOSCs are included. However, the level of risk reduction assumed in the bounding case does not appear to be cchievable, given that all AFW hardware and human-action-related failures would not realistically be climinated through this change. In this regard, BGE's best estimate of risk reduction appears more representative of the level of risk reduction that might be achieved. Under best-estimate risk reduction assumptions, the SAMA has a negative net value, even when AOSCs are included. 5.2.7 Conclusions BGE completed a comprehensive effort to identify and evaluate potential cost-beneficial plant enhancements to reduce the risk associated with severe accidents at CCNPP.. As a result of this assessment, BGE identified and committed to pursue one enhancement in accordance with the CCNPP modification process. This involves the installation of a watertight door between the service water pump room and the adjacent fan room to reduce the likelihood of core damage from intemal flooding events. BGE also committed to further evaluate the adequacy of CCNPP procedures regarding response to int:rnal floods following resolution of the hardware flooding enhancement. BGE concluded that no additional mitigation alternatives are cost-beneficial and warrant implementation at CCNPP. Based on the staff's review of SAMAs for CCNPP, several SAMAs appear to be cost-beneficial when evaluated using the guidance in NUREG/BR-0184 (NRC 1997b). Three SAMAs (36,48a, and 74) have a positive net value ui e both bounding and best-estimate risk reduction assumptions when AOSCs l are included. The mo a risk-significant enhancement, SAMA 48a, has a CDF reduction of approximately 30 percent under bounding assumptions, and 10 percent under best-estimate assumptions. All remaining SAMAs have either a very small negative net value, or offer minimal risk l rsduction (i.e., a reduction of only a few percent) under best estimate risk reduction assumptions. Although a limited number of SAMAs (four) appear to be cost beneficial and to offer a level of risk reduction, those SAMAs do not relate to adequately managing the effects of aging during the period of extended operation. Therefore, they need not be implemented as part of license renewal pursuant to ' 10 CFR Part 54. 5.3 References 10 CFR 50.59, " Changes, tests, and experiments." 10 CFR Part 51, " Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions." 10 CFR 51.53, "Postconstruction environmental reports." l l NUREG-1437, Supplement 1 5-29 October 1999
Postulated Accidents l 10 CFR Part 51, Subpart A, Appendix B, Table B-1, " Environmental effect of renewing the operating l license of a nuclear power plant." l l 10 CFR Part 54, " Requirements for renewal of operating licenses for nuclear power plants." Baltimore Gas and Electric (BGE).1970. EnvironmentalReport, Calvert Cliffs NuclearPower Plant (November 16,1970), Baltimore, Maryland. Baltimore Gas and Electric (BGE).1971. Supplement to EnvironmentalReport; Calvert Cliffs Nuclear Power Plant, (November 8,1971) Baltimore, Maryland. Baltimore Gas and Electric (BGE).1993. Letter from R.E. Denton, BGE, to U.S. NRC. Summary Report ofIndividual Plant Examination (IPE) Results (Generic Letter 88-20). Baltimore Gas and Electric (BGE).1997. Letter from C.H. Cruse, BGE to U.S. NRC. IndividualPlant Acc/ dent Vulnerabilities. IPEEE, August 28,1997. Baltimore Gas and Electric (BGE).1998a. Applicant's EnvironmentalReport - Operating License Renewal Stage - Calvert Cliffs Nuclear Power Plant, Units 1 and 2, (April 1998). Baltimore, Maryland. Baltimore Gas and Electric (BGE). 1998b. CCNFP Updated Final Safety Analysis Report, various revisions. Baltimore, Maryland. Baltimore Gas and Electric (BGE).1998c. Response to Request for Additional Information (RAl) l Submittal. Calvert Cliffs Nuclear Power Plant Unit Nos.1 and 2 Severe Accident Mitigation Altematives, l December 3,1998, Baltimore, Maryland. Chanin, D. l. et al.1990. Melcor Accident Consequence Code System (MACCS), Vol.1, User's Guide. NUREGICR-4691, SAN 86-1562, Sandia National Laboratories, Albuquerque, New Mexico. U.S. Atomic Energy Commission (AEC).1973. FinalEnvironmental Statement Related to Operation of Calvert Cliffs Nuclear Power Plant Units 1 and 2, Docket Nos. 50-317 and 50-318, (April 1973). Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1978. Final Environmental Statement Related to the Operation I of Watts Bar Nuclear Plant Units Nos. I and 2, NUREG-0498. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1980. NRC Action Plan Developed As a Result of TM/-2 Accident, NUREG-0660. Washington, D.C. October 1999 5-30 NUREG-1437, Supplernent 1
i Postulatsd Accidsnts U.S. Nuclear Regulatory Commission (NRC). 1988. Generic Letter 88-20, " individual Plant Ex mination for Severe Accident Vulnerabilities." November 23,1988. U.S. Nuclear Regulatory Commission (NRC). 1989a. Supplement Final Environmental Statement Rzlated to the Operation of Comanche Peak Steam Electric Station, Units I and 2, NUREG-0775. Wnhington, D.C. U.S. Nuclear Regulatory' Commission (NRC).1989b. Letter from S. A. Varga, U.S. NRC, to G. A. Hunger, Jr., Philadelphia Electric Company. August 16,1989.
Subject:
Supplement to the Final Environmental Statement - Limerick Generating Station, Units 1 and 2. U.S. Nuclear Regulatory Commission (NRC).1990a. Severe Accident Risks.- An Assessment for Five U.S. NuclearPower Plants, NUREG-1150.' Washington, D.C. U.S. Nuclear Regulatory Commission (NRC) 1990b. Generic Letter 88-20, Supplement 3.
" Completion of Containment Performance improvement Program and Forwarding Insights for Use in the Individual Plant Examination for Severe Accident Vulnerabilities." Washington, D.C.
U.S. Nuclear Regulatory Commission (NRC).1990c. Letter from J. G. Partlow, U.S. NRC, to All Holders of Operating Licenses and Construction Permits for Nuclear Power Reactor Facilities. April 4, 1990.
Subject:
Accident Management Strategies for Consideration in the Individual Plant Examination Process - Generic Letter 88-20, Supplement No. 2. U.S. Nuclear Regulatory Commission (NRC). 1994. Final Safety Evaluation Report Related to the Certification of the System 80+ Design. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1995a. . Final Environmental Statement Related to the Opsration of Watts Bar Nuclear Plant, Units 1 and 2, NUREG-6498, Supp.1. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1995b. Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission, NUREG/BR-0058, Revision 2. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1996a. Generic Environmentallmpact Statement for Liasisse Renewal of Nuclear Plants (GEIS), NUREG-1437. Washington, D.C.
. U.S. ' Nuclear Regulatory Commission (NRC).' '1996b. Letter from U.S. NRC, to BGE. Staff Evaluation R: port for the Calvert Cli/fs IPE.
U.S. Nuclear Regulatory Commission (NRC).1997a. IndividualPlant Examination Program: Perspectives on Reactor Safety and Plant Performance, Vol. 2, NUREG-1560. Washington, D.C. NUREG-1437, Supplement 1 - 5-31 October 1999 l 1
p Postulited Accidents-1 U.S. Nuclear Regulatory Commission (NRC).1997b. Regulatory Analysis Technical Evaluation Handbook, NUREG/BR-0184. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1998a. Environmentallmpact Statement Scoping Process: Summary Report-Calvert Cliffs Nuclear Power Plant, Lusby, Maryland. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1998b. Letter from U.S. NRC to BGE. Request for
. AdditionalInformation (RAI). September 9,1998.
U.S. Nuclear Regulatory Commission (NRC). 1998c. AP600 Final Safety Evaluation Report Related to the Certification of the AP600 Design, Section 19.4, Consideration of Potential Design Improvements UnderRequirements of 10 CFR 50.34(f), NUREG-1512. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1999a. Summary of January 7,1999, meeting with BGE. January 28,1999. U.S. Nuclear Regulatory Commission (NRC).1999b. Memorandum from J. S. Walker, Acting Secretary to W. D. Travers, Executive Director for Operations. July 19,1999.
Subject:
Staff Requirements - Secy-99-169 -Treatment of Averted Onsite Costs in Regulating Analyses. October 1999 = 5-32 NUREG-1437, Supplement 1
6.0 EnvironmentalImpacts of the Uranium Fuel Cycle and i Solid Waste Management l Environmental issues associated with the uranium fuel cycle and solid waste management were di: cussed in the Generic EnvironmentalImpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437 (NRC 1996). The GEIS included a determination of whether the analysis of the environmentalissue could a applied to all plants, and whether additional mitigation measures would be wirranted. Issues were then assigned a Category 1 or a Category 2 designation. As set forth in the l I GEIS, Category 1 issues are those that meet all of the following criteria: l (1) the environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other specified plant or site characteristics i (2) a single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except I for collective offsite radiological impacts from the fuel tycle and from high-level waste and spent fuel l disposal) I (3) mitigation of adverse impacts associated with the issue has been considered in the analysis, and it l has been determined that additional plant-specific mitigation measures are likely not to be sufficiently beneficial to warrant implementation. For issues that meet the three Category 1 criteria, no additional plant-specific analysis is required unl;ss new and significant information is identified. C tegory 2 issues are those that do not meet one or more of the criteria of Category 1, and therefore, l cdditional plant-specific review for these issues is required. l This chapter addresses those issues that are related to the uranium fuel cycle and solid wac m:nagement during the license renewal term, listed in 10 CFR Part 51, Subpart A, Appe ,cx B, Table l B-1, and are applicable to CCNPP. The generic potential radiological a,id non-radiologie" l cnvironmentalimpacts of the uranium fuel cycle and transportation of nuclear fuel and was'es are tscribed in detail in the GEIS based on the generic impacts provided in 10 CFR 51.51(b), Table S-3, l ,
"Tcble of Uranium .':uel Cycle Environmental Data," and in 10 CFR 51.52(c) Table S-4, " Environmental Impact of Transpodation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power R;rctor." The GEIS also addresses the impacts from radon and technetium. With the exception of tran:portation of high-level waste, all aspects of the impacts from the uranium fuel cycle ani miid waste m nagement are Category 1 issues.
l NUREG-1437, Supplement 1 6-1 October 1999
Fuel Cycle l 6.1 The Uranium Fuel Cycle l Category 1 issues in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, that are applicable to CCNPP uranium fuel cycle and solid waste management are listed in Table 6-1. BGE stated in its l Environmental Report (ER) that it is unaware of any noty r.n ' @nificant information related to these j Table 6-1. Category 1 issues Applicaole tc de Uq... tom Fuel Cycle and Solid Waste Management l ISSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Sections URANIUM FUEL CYCLE AND WASTE MANAGEMENT Offsite radiological i.npacts (individual effects from other than 6.1; 6.2.1; 6.2.2.1; 6.2.2.3; 6.2.3; the disposal of spent fuel and high level waste) 6.2.4; 6.6 Offsite radiological impacts (collective effects) 6.1; 6.2.2.1; 6.2.3; 6.2.4 Offsite radiological impacts (spent fuel and high level waste 6.1; 6.2.2.1; 6.2.3; 6.2.4 disposal) Nonradiologicalimpacts of the uranium fuel cycle 6.1; 6.2.2.6; 6.2.2.7; 6.2.2.8; 6.2.2.9; 6.2.3; 6.2.4; 6.6 Low-level waste storage and disposal 6.1; 6.2.2.2;6.4.2; 6.4.3; 6.4.3.1; 6.4.3.2; 6.4.3.3; 6.4.4; 6.4.4.1; 6.4.4.2; 6.4.4.3; 6.4.4.4; 6.4.4.5; 6.4.4.5.1; 6.4.4.5.2; 6.4.4.5.3; 6.4.4.5.4; 6.4.4.6 t/bcod waste storage and disposal 6.4.5.1; 6.4.5.2; 6.4.5.3; 6.4.5.4; 6.4.5.5; 6.4.5.6; 6.4.5.6.1; l 6.4.5.6.2; 6.4.5.6.3; 6.4.5.6.4 On-site spent fue! 6.1; 6.4.6; 6.4.6.1; 6.4.6.2; 6.4.6.3; 6.4.6.4; 6.4.6.5; 6.4.6.6; [ 6.4.6.7, 6.6 Nonradiological waste 6.1; 6.5; 6.5.1; 6.5.2; 6.5.3; 6.6; Transportation 6.1; 6.3.1; 6.3.2.3; 6.3.3; 6.3.4; 6.6 October 1999 6-2 NUREG-1('7, Supplement 1
Fu:1 Cycle Category 1 issues. No significant new information has been identified by the staff in the review process end in the staff's independent review. Therefore, the staff concludes that there are no impacts related to these issues beyond those discussed in the GEIS.* For all of those issues, the GEIS concluded that l thm impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. I A brief description of the staffs review and the GEIS conclusions, as codified in Table B-1, for each of these issues follows.
- Offsite radiolooical imoacts (individual effects from other than the disposal of soent fuel and hioh level waste): Based on information in the GEIS, the Commission found that "Off-site impacts of the l uranium fuel cycle have been considered by the Commission in Table S-3 of this part
[10 CFR 51.51(b)]. Based on information in the GEIS, impacts on individuals from radioactive l gaseous and liquid releases including radon-222 and technetium-99 are small." The staff has not l identified any significant new information during its independent review of the BGE ER, the staffs site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no offsite radiological l impacts of the uranium fuel cycle during the renewal ters beyond those discussed in the GEIS.
. Offsite radiolooical imoacts (collective effects): Based on information in the GEIS, the Commission found that "The 100 year environmental dose commitment to the U.S. population from the fuel cycle, l high level waste and spent fuel disposal is calculated to be about 14,800 person rem (148 person l Sv), or 12 cancer fatalities, for each additional 20-year power reactor operating term. Much of this, l especially the contribution of radon releases from mines and tailing piles, consists of tiny doses summed over large populations. This same dose calculation can theoretically be extended to include many tiny doses over additional thousands of years as well as doses outside the U.S. The result of such a calculation would be thousands of cancer fatalities from the fuel cycle, but this result tssumes that even tiny doses have some statistical adverse health effect which will not ever be l mitigated (for example, no cancer cure in the next thousand years), and that these doses projected l over thousands of years are meaningful. However, these assumptions are questionable. In particular, science cannot rule out the possibility that there will be no cance: 3talities from these tiny doses. For perspective, the doses are very small fractions of regulatory limits, and even smaller fractions of natural background exposure to the same populations. Nevertheless, despite all the l uncertainty, some judgement as to the regulatory NEPA implications of these matters should be made and it makes no sense to repeat the same judgement in every case. Even taking the l uncertainties into account, the Commission concludes that these impacts are acceptable in that these impacts would not be sufficiently large to require the NEPA conclusion, for any plant, that the option of extended operation under 10 CFR Part 54 should be eliminated. Accordingly, while the l
l (a) The GEIS was originally issued in 1996. Addendum 1 to the GEIS was issued in 1999. All l references to the "GEIS" include the GEIS and its Addendum 1. l NUREG-1437, Supplement 1 6-3 October 1999
Fuel Cycle
)
l l Commission has not assigned a single level of significance for the collective effects of the fuel cycle, this issue is considered Category 1." l The staff has not identified any significant ne a mformation during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no collective impacts of the uranium fuel cycle during the renewal term beyond those discussed in the GEIS. l . Offsite radioloaical imoacts (spent fuel and hiah level waste disposa0: Based on information in the l GEIS, the Commission found that "For the high level waste and spent fuel disposal component of l the fuel cycle, there are no current regulatory limits for offsite releases of radionuclides for the current candidate repository site. However, if we assume that limits are developed along the lines of the 1995 National Academy of Sciences (NAS) report, "TecNal Bases for Yucca Mountain l Standards [lNS 1995]," and that in accordance with the Commisson's Waste Confidence Decision, 10 CFR 51.23, a repository can and likely will be developed at some site which will comply with such limits, peak doses to virtually all individuals will be 100 millirem [1 mSv] per year or less. However, while the Commission has reasonable confidence that these assumptions will prove correct, there is considerable uncertainty since the limits are yet to be developed, no repository application has been completed or reviewed, and uncertainty is inherent in the models used to evaluate possible pathways to the human environment. The NAS report indicated that 100 millirem [1 mSv] per year should be considered as a starting point for limits for individual doses, but notes that some measure of consensus exists among national and intemational bodies that the limits l should be a fraction of the 100 millirem [1 mSv] per year. The lifetime individual risk from 100 millirem [1 mSv] annual dose limit is about 3 x 10 "
" Estimating cumulative doses to populations over thousands of years is more problematic. The likelihood and consequences of events that could seriously compromise the integrity of a deep geologic repository were evaluated by the Department of Energy in the " Final Environmental Impact l Statement: Management of Commercially Generated Radioactive Waste [ DOE 1980]," October 1980. The evaiuation estimated the 70-year whole-body dose commitment to the maximum individual and to the regional population resulting from several modes of breaching a reference repository in the year of closure, after 1,000 years, after 100,000 years, and after 100,000,000 years. Subsequently, the NRC and other federal agencies have expended considerable effort to develop models for the design and for the licensing of a high level waste repository, especially for l the candidate repository at Yucca Mountain. More meaningful estimates of doses to population may be possible in the future as more is understood about the performance of the proposed Yucca Mountain repository. Such estimates would involve very great uncertainty, especially with respect to cumulative population doses over thousands of years. The standard proposed by the NAS is a limit on maximum individual dose. The relationship of the potential new regulatory requirements, based on the NAS report, and cumulative population impacts has not been determined, although the report articulates the view that protection of individuals will adequately protect the population for a October 1999 6-4 NUREG-1437, Supplement 1 I
I l
1 i I Fu:1 Cycle l l l repository at Yucca Mountain. However, EPA's generic repository standards in 40 CFR Part 191 l l generally provide an indication of the order of magnitude of cumulative risk to population that could result from the licensing of a Yucca Mountain repository, assuming the ultimate standards will be within the range ci standards now under consideration. The standards in 40 CFR Part 191 protect j the population by imposing " containment requirements" that limit the cumulative amount of radioactive material released over 10,000 years. Reporting performance standards that will be required by EPA are expected to result in releases and associated health consequences in the range between 10 and 100 premature cancer deaths with an upper limit of 1,000 premature cancer deaths worldwide for a 100,000 metric tonne (MTHM) repository." - 1 I
"Nevertheless, despite all the uncertainty, some judgement as to the regulatory NEPA implications !
l of these matters should be made and it makes no sense to repeat the same judgement in every case. Even taking the uncertainties into account, the Commission concludes that these impacts are ccceptable in that these impacts would not be sufficiently large to require the NEPA conclusion, for any plant, that the option of extended operation under 10 CFR Part 54 should be eliminated. l l Accordingly, while the Commission has not assigned a single level of significance for the impacts of l j spent fuel and high level waste disposal, this issue is considered Category 1." l l The staff has not identified any significant new information during its independent review of the BGE j ER, the staffs site visit, the scoping process, its review of public comments on the draft SEIS, or its j evaluation of other available information. Therefore, the staff concludes that there are no impacts of spent fuel and high level waste disposal during the renewal term beyond those discussed in the GEIS.
. Nonradioloaicalimpacts of the uranium fuel cycle: Based on information in the GEIS, the Commission found that "The nonradiological impacts of the uranium fuel cycle resulting from the l l renewal of an operating license for any plant are found to be SMALL." The staff has not identified l any significant new information during its independent review of the BGE ER, the staffs site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other j available information. Therefore, the staff concludes that there are no nonradiological impacts of i the uranium fuel cycle during the renewal term beyond those discussed in the GEIS. !
- Low-level waste storaae and disposal: Based on information in the GEIS, the Commission found l that "The comprehensive regulatory controls that are in place and the low public doses being l achieved at reactors ensure that the radiological impacts to the environment will remain small during l the term of a renewed license. The maximum additional on-site land that may be required for low- l level waste storage during the term of a renewed license and associated impacts will be small.
Nonradiological impacts on air and water will be negligible. The radiological and nonradiological environmental impacts of long-term disposal of low-level waste from any individual plant at licensed sites are small. In addition, the Commission concludes that there is reasonable assurance that sufficient low-level waste disposal capacity will be made available when needed for facilities to be NUREG-1437, Supplement 1 6-5 October 1999
Fu:1 Cycia l decommissioned consistent with NRC decommissioning requirements." The staff has not identified l any significant new information during its independent review of the BGE ER, the staff's site visit, i the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of low-level waste ' storage and disposal associated with the renewal term beyond those discussed in the GEIS. j { l . Mixed waste storaae and disposal: Based on information in the GEIS, the Commission found that I "The comprehensive regulatory controls and the facilities and procedures that are in place ensure proper handling and storage, as well as negligible doses and exposure to toxic materials for the public and the environment at all plants. License renewal will not increase the small, continuing risk to human health and the environment posed by mixed waste at all plants. The radiological and nonradiological environmental impacts of long-term disposal of mixed waste from any individual plant at licensed sites are small. In addition, the Commission concludes that there is reasonable assurance that sufficient mixed waste disposal capacity will be made available when needed for facilities to be decommissioned consistent with NRC decommissioning requirements." The staff has
] not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of mixed waste storage and disposal associated with the renewal term beyond those discussed in the GEIS.
l . Onsite spent fuel: Based on information in the GEIS, the Comm!ssion found that "The expected increase in volume of spent fuel from an additional 20 years of operation can be safely accommodated on site with small environmental effects through dry or pool storage at all plants if a permanent repository or monitored retrievable storage is not available." The onsite spent fuel impacts were determined to be SMALL. The staff has not identified any significant new information l during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of onsite spent fuel associated with license renewal beyond those discussed in the GEIS. l . Nonradioloaicalwaste: Based on information in the GEIS, the Commission found that "No changes to generating systems are anticipated for license renewal. Facilities and procedures are in place to ensure continued proper handling and disposal at all plants. The nonradiological waste impacts l were determined to be SMALL. The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no nonradiological waste impacts during the renewal term beyond those discussed in the GEIS. l October 1999 6-6 NUREG-1437, Supplement 1
Funi Cycle l l
. Transportation: Subsequent to the issuance of the draft SEIS, the Commission promulgated a final l rule to amend the regulations goveming the transportation issues of the environmental review l requirements for renewal of nuclear power plant operating licenses. This transportation issue had l been considered a Category 2 issue and was discussed in Section 6.1.1 of the draft SEIS. It is no l longer considered a Category 2 issue and, therefore, Section 6.1.1 has been deleted. Based on [
information contained in the GEIS, the Commission found that "The impacts of transoorting spent [ fuel enriched up to 5 percent uranium-235 with average bumup for the peak rod to current levels l cpproved by NRC up to 62,000 mwd /MTU and the cumulative impacts of transporting high-level l waste to a single repository, such as Yucca Mountain, Nevada, are found to be consistent with the l l impact values contained in 10 CFR 51.52(c), Summary Table S-4-Environmental Impact of l l Transportation of Fuel and Waste to and from One Light-Water-Cooled Nuclear Power Reactor. If l fuel enrichment or bumup conditions are not met, the applicant must submit an assessment of the l implications for the environmental impact values reported in @51.52." l 1 The transportation impacts were determined to be SMALL if fuel enrichment and bumup conditions l set forth in the Addendum 1 to the GEIS are met. CCNPP meets the fuel enrichment and bumup l conditions. The staff has not identified any significant new information during its independent review l l of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft l SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are l no impacts of transportation associated with license renewal beyond those discussed in the GEIS. l 6.2 References 10 CFR 51.23, " Temporary storage of spent fuels after cessation of reactor operation-saneric dst:rmination of no significant environr,.entalimpact." 10 CFR 51.51(b), Table S-3, " Table of Uranium Fuel Cycle Environmental Data." l 10 CFR 51.52(c), Table S-4, " Environmental Impact of Transportation of Fuel and Waste to and from Ons Light-Water-Cooled Nuclear Power Reactor." 10 CFR Part 51, Subpart A, Appendix B, Table B-1, " Environmental effects of renewing the operating l license of a nucle.ar power plant." l 10 CFR Part 54, " Requirements for Renewal of Operating Licenses for Nuclear Power Plants." 40 CFR Part 191, " Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste." National Academy of Sciences (NAS).1995. TechnicalBases for Yucca Mountain Standards. l Washington, D.C. NUREG-1437, Supplement 1 6-7 October 1999
Fuel Cycle U.S. Department of Energy (DOE). ^ 1980. FinalEnvironmentalImpact Statement: Management of Commercially Generated Radioactive Waste. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1996. ' Generic Environmentallmpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1999. Generic Environmentallmpact Statement for License Renewal of NuclearPlants Main Report, Section 6.3--Transportation, Table 9.1 Summary of findings on NEPA issues forlicense renewalofnuclearpowerplants. NUREG-1437, Volume 1, Addendum 1. Washington, D.C. 4 October 1999 - 6-8 NUREG-1437, Supplement 1
7.0 EnvironmentalImpacts of Decommissioning i Environmental issues associated with decommissioning resulting from continued plant operation during the renewal term were discussed in the Generic EnvironmentalImpact Statement for License Renewal of NuclearPowerPlants (GEIS), NUREG-1437 (NRC 1996). The GEIS included a determination of whether the analysis of the environmental issue could be applied to all plants, and whether additional mitigation measures would be warranted. Issues were then assigned a Category 1 or a Category 2 designation. As set forth in the GEIS (GEIS), Category 1 issues are those that meet all of the following l crit:ria: (1) the environmental impacts associated with the issue have been determined to apply either to all plants or, for some issues, to plants having a specific type of cooling system or other specified plant or site characteristics (2) e single significance level (i.e., small, moderate, or large) has been assigned to the impacts (except for collective offsite radiological impacts from the fuel cycle and from high-level waste and spent fuel) (3) mitigation of adverse impacts associated with the issue has been considered in the analysis, and it l has been determined that additional plant-specific mitigation measures are not likely to be sufficiently beneficial to warrant implementation. For issues that meet the three Category 1 criteria, no additional plant-specific analysis is required uni ss new and significant information is identified. C:tegory 2 issues are those that do not meet one or more of the criteria of Category 1, and therefore, l additional plant-specific review for these issues is required. Category 1 issues in 10 CFR Part 51, Subpart A, Appendix B, Table B-1, that are applicable to CCNPP l d: commissioning following the renewal term are listed in Table 7-1. BGE stated in its Environmental l R; port (ER) that it is unaware of any new and significant information related to these Category 1 issues. l No significant new information has been identified by the staff in the review process and in the staff's ind: pendent review. Therefore, the staff concludes that there are no impacts related to these issues beyond those discussed in the GEIS. For all of those issues, the staff concluded in the GEIS that the l impacts are SMALL, and plant-specific mitigation measures are not likely to be sufficiently beneficial to be warranted. A brief description of the staff's review and the GEIS conclusions, as codified in Table B-1, for each of l tha issues follows. NUREG-1437, Supplement 1 7-1 October 1999 l
Decomn'issioning Table 'T-1.' C'ategory 1 issues Applicable to the Decommissioning l l of the CCNPP Following the Renewal Term l lSSUE-10 CFR Part 51, Subpart A, Appendix B, Table B-1 GEIS Sections DEColMilssioNING Radiation doses - 7.3.1; 7.4 Waste management 7.3.2; 7.4 Air quality 7.3.3; 7.4 Water quality 7.3.4; 7.4 Ecological resources 7.3.5; 7.4 Socioeconomic impacts 7.3.7; 7.4 1.
~l
- Radiation doses: Based on information in the GEIS, the Commission foLad that " Doses to the public will be well below applicable regulatory standards regardless of which decommissioning l method is used. Occupational doses would increase no more than 1 man-rem [0.01 person-Sv]
caused by buildup of long-lived radionuclides during the license renewal term." The staff has not j identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no radiation doses associated with decommissioning following license renewal beyond those discussed in the GEIS. l
. Waste manaaement: Based on information in the GEIS, the Commission found that
" Decommissioning at the end of a 20-year license renewal period would generate no more solid wastes than at the end of the current license term. No increase in the quantities of Class C or greater than Class C wastes would be expected." The staff has not identified any significant new l information during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of public comments on the draft SElS, or its evaluation of other available information.
Therefore, the staff concludes that there are no impacts of solid waste associated with decommissioning following the license renewal term beyond those discussed in the GEIS. l = Air auality: Based on information in the GEIS, the Commission found that " Air quality impacts of decommissioning are expected to be negligible either at the end of the current operating term or at the end of the license renewal term," The staff has not identified any significant new information
- l. during its independent review of the BGE ER, the staff's site visit, the scoping process, its review of I
public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of license renewal on air quality during decommissioning beyond those discussed in the GEIS. ! October 1999 7-2 NUREG-1437, Supplement 1 I
l Decommissioning l
- e Water auality
- Based on information in the GEIS, the Commission found that "The potential for l significant water quality impacts from erosion or spills is no greater whether decommissioning occurs after a 20-year license renewal period or after the original 40-year operation period, and
- mrasures are readily available to avoid such impacts." The staff has not identified any significant n
- w information during its independent review of the BGE ER, the staff's site visit, the scoping l process, its review of public comments on the draft SEIS, or its evaluation of other available information. Therefore, the staff concludes that there are no impacts of the license renewal term on water quality during decommissioning beyond those discussed in the GEIS.
. Ecoloaical resources: Based on information in the GEIS, the Commission found that l
" Decommissioning after either the initial operating period or after a 20-year license renewal period is not expected to have any direct ecological impacts." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, l its review of public comments on the draft SEIS, or its evaluation of other available information.
l Therefore, the staff concludes that there are no impacts of the l'. cense renewal term on ecological j rssources during decommissioning beyond those discussed in the GEIS.
. Socioeconomic Imoacts: Based on information in the GEIS, the Commission found that l
" Decommissioning would have some short-term socioeconomic impacts. The impacts would not be l increased by delaying decommissioning until the end of a 20-year relicense period, but they might l be decreased by population and economic growth." The staff has not identified any significant new information during its independent review of the BGE ER, the staff's site visit, the scoping process, l its review of public comments on the draft SEIS, or its evaluation of other available information.
Therefore, the staff concludes that there are no impacts of license renewal on the socioeconomic impacts of decommissioning beyond those discussed in the GEIS. 7.1 References 10 CFR Part 51, Subpart A, Appendix B, " Environmental Effect of Renewing the Operating License of a Nuclsar Power Plant." U.S. Nuclear Regulatory Commission (NRC).1996. Generic Environmentallmpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437. Washington, D.C. NUREG-1437, Supplement 1 7-3 October 1999
r 1 l l l 8.0 EnvironmentalImpacts of Alternatives to License i j Renewal , 1 Th3 planning for electric power generation in Maryland is accomplished by three groups interacting with l cach other (1) power generators (such as BGE), (2) the Maryland Public Service Commission (PSC), j cnd (3) the Maryland Power Plant Research Program within the Maryland Department of Natural I R: sources (MDNR). The Public Service Commission regulates electric power rates and other practices l of the individual utilities under their purview. The Power Plant Research Program is required by State 1:w to review and evaluate the impacts to Maryland's environment from the construction and operation of electric power generation and transmission systems (MDNR 1999a). The Power Plant Research l Program summarizes these impacts biennially and advises the PSC on the environmental impacts of l utility proposals. l This chapter examines the potential environmental impacts associated with denying a renewed license
)
(i.e., the No-Action attemative); the potential environmental impacts from electric generating sources { other than nuclear license renewal; the potential impacts from instituting additional conservation m=sures to reduce the total demand for power; and the potential impacts from power imports. The l i imp cts are evaluated using a three-level standard of significance-small, moderate, or large-based l on Council on Environmental Quality (CEQ) guidelines. These significance levels are l , I SMALL: Environmental effects are not detectable or are so minor that they will neither destabilize l l nor noticeably alter any important attribute of the resource. l l l l MODERATE: Environmental effects are sufficient to alter noticeably, but not to destabilize important l tttributes of the resource. l I LARGE: Environmental effects are clearly noticeable and are suf*icient to destabilize important l l rttributes of the resource. l 8.1 No-Action Alternative For license renewal, the No-Action attemative refers to a scenario in which NRC would not renew the l CCNPP operating licenses, and the applicant would then decommission CCNPP when plant operations l cerse. Replacement of CCNPP electricity generation capacity would be met either by demand-side l m;nagement and energy conservation (perhaps supplied by an energy service company), imported power, or by some in-State generating attemative other than CCNPP. However, due to the influence of the ongoing deregulation of the retail market, BGE may not be the ultimate supplier of power. I NUREG-1437, Supplement 1 8-1 October 1999 l 1
Alt:mitiv s to License R:n;wal l In April 1999, the Maryland General Assembly approved the Electric Customer Choice and Competition l Act of 1999, signed into law by the governor shortly thereafter. During the past year, BGE and other l parties (including DNR) have been litigating a transition to retail competition. l l Restructuring means that CCNPP will no longer be required to serve its Maryland customers (except l perhaps in the early years of restructuring when BGE retains a " default" of Standard Offer obligation). l As a general matter, in a restructured world, CCNPP will serve the regional, mid-Atlantic market. l However, due to transmission constraints for imports into Maryland, if CCNPP were to be retired, either l some of the replacement capacity must be sited in Maryland, or transmission intertie transfer capacity l must be expanded to allow more imports. Although Maryland would need either replacement capacity l or expanded transmission capability if CCNPP is retired, the 'ew resources need not be sited in l Southem Maryland (i.e., near the present CCNPP site). This is because there is already substantial l generation in Southem Maryland at Potomac Electric Power Company's (PEPCO) Morgantown and l Chalk Point Plants. Maryland load centers are primarily north of the CCNPP site. Ultimately the l retirement of CCNPP will necessitate replacement resources in the form of new generation and/or l transmission in Maryland; it will be supplied by the market, not necessarily BGE (MDNR 1999b). l l BGE will be required to comply with NRC decommissioning requirements whether or not the licenses are renewed. If the CCNPP operating licenses are renewed, decommissioning activities may be postponed for up to an additional 20 years. If the licenses are not renewed, then BGE would begin decommissioning activities when plant operations cease, beginning in 2014 or perhaps sooner. The l impacts of decommissioning will occur concurrently with the imp 5 cts of supplying replacement power. l The GEIS (NRC 1996), and the Final Generic Impact Statement on Decommissioning of Nuclear Facilities, NUREG-0586 (NRC 1988) provide a description of decommissioning activities. l The environmental impacts associated with decommissioning under the No-Action alternative would be bounded by the discussion of impacts in Chapter 7 of the GEIS, Chapter 7 of the SEIS, and NUREG-0586. The impacts of decommissioning after 60 years of operation generally would not be significantly different from those occurring after 40 years of operation. When CCNPP ceases operation, there will be a decrease in employment and tax revenues associated with the closure. This impact would be concentrated in Calvert County, and to a lesser degree in St. Mary's, Charles, and Ann Arundel Counties. Most secondary employment impacts and impacts on population would also be expected in these counties. Table 2.6 shows the current geographic distribution of the residences of CCNPP employees by county. Most of the tax revenue losses would occur in Calvert County. ; Additionally, the potential for future adverse impacts to known or unrecorded cultural resources at the l CCNPP following decommissioning will depend on the fuhre land use of the site. Known resources and activities include the current visitors center, historic properties, and associated interpretative efforts i October 1999 8-2 NUREG-1437, Supplement 1
Alternativss to Lic nse Ren vml th:t are funded and maintained by BGE. Eventual sale or transfer of the land within the plant site could r:sult in adverse impacts to these resources, should the land-use pattern change dramatically. l Current operations at CCNPP do not have disproportionate impacts on low-income and minority populations of the surrounding counties, and no environmental pathways have been identified that l would cause disproportionate impacts. Since closure would result in a decrease in employment and tax r:v:nues in Calvert County, it is possible that the County's ability to maintain rocial services could be reduced at the same time as diminished economic conditions reduce employ ment prospects for the minority or low-income populations. There is some possibility of negative and disproportionate impacts on minority or low-income populations from this source under the No-Action Altemative. Ths No-Action attemative results in these impacts occurring 20 years earlier than if the licenses are r:n:wed (Table 8-1). Table 8-1. Summary of EnvironmentalImpacts from No-Action Altemative Impact Category impact Comment Socioeconomic MODERATE to LARGE Decrease in employment and tax revenues
- l Archaeological and Historic SMALL to LARGE Sale or transfer of land within plant site leads Resources to changes in land use pattern Environmental Justice SMALL to MODERATE Loss of employment opportunities and social programs (a) Recent Maryland utility tax legislation will reduce the property tax rednues substantially on a l phased-in basis. In any event, CCNPP property tax revenues are expected to decline over time by l 60 percent, partially offset by State compensation. l 8.2 Alternative Energy Sources Nuclear power plants are commonly used for base-load generation, the GEIS indicates that coal-fired and gas-fired generation capacity are the feasible attematives to nuclear power generating capacity, b:std on current (and expected) technological and cost factors. The attematives of coal-fired gen: ration and gas-fired generation are presented (Sections 8.2.1 and 8.2.2, respectively) as if such l plints were constructed at the CCNPP site, using the existing water intake and discharge structures, switchyard, and transmission lines, or at an alternate location, which could be either a current industrial l sits or an undisturbed, pristine site requiring a new generating building and facilities, new switchyard, l end at least some new transmission lines. For the purposes of this SEIS, a "greenfield" site is assumed l to be an undisturbed, pristine site. l NUREG-1437. Supplement 1 8-3 Octaber 1999
Alt:rnativ s to Licens7 R:n::wal Depending on the location of an attemative site, it might also be necessary to provide a connection to the nearest gas pipeline (in the case of natural gas) or rail connection (in the case of coal). The requirement for these additional facilities also likely would increase the environmental impacts relative to those that would be experienced at the CCNPP site, although this is less certain. l The cooling water needs of a fossil fuel-fired plant of equal capacity to the CCNPP facility would require i l the use of either a once-through cooling system located on a large body of water such as the l Chesapeake Bay or a closed-cycle system using cooling towers. The potential for using imported power is discussed in Section 8.2.3. Imported power is considered feasible, but would result in the transfer of environmental impacts from the current region in Maryland to l some other location in Maryland, an other state, or a Canadian province. Several other technologius were considered, but were determined not to be reasonable replacements for a nuclear power plant. These options included wind, solar, hydropower, geothermal, wood energy, municipal solid waste, oil, l advanced nuclear, delayed retirement of other generating units, utility-sponsored conservation, and fuel [ cells, and these are discussed in Section 8.2.4. l Some of the altematives in this section are not inherently infeasible, but could not provide enough l power to replace CCNPP on their own. The final subsection considers the environmental l consequences of a mix of altematives. In general, these impacts are larger than the environmental l consequences of relicensing. I 8.2.1 Coal-Fired Generation l In its Environmental Report (ER) related to renewal of CCNPP (BGE 1998a), BGE used information l about the Delmarva Power and Light Company's Dorchestor Power Plant and the South Carolina l Electric and Gas Company's Cope Power Plant to develop a representative attemative coal-fired plant. l For some plant characteristics, the 6ta were referenced directly; in other cases, BGE appropriately I scaled data to fn .1e size plant needed for a CCNPP-alternative energy source. The staff has reviewed the description and considers that it reasonably represents the type of technology that would be used. BGE assumed that it would require 1800 MW coal-fired generation capacity to replace the 1690-MW capacity of CCNPP. The larger-sized coal-fired facility would be necessary to offset increased electrical usage for pollution control, pumping water for cooling, or transporting coal or ash. l l 8.2.1.1 Once-Through Cooling System
- I
! l The coal-fired attemative described by BGE in the ER (BGE 1998a) consists of three (600-MW) units that would bum pulverized bituminous coal. The units would be constructed at the same time with phased-in service dates to replace the power demands supplied by CCNPP and would have an j operationallife of 40 years (South Carolina Electric and Gas Co.1991). Constructing a larger number l October 1999 8-4 NUREG-1437, Supplement 1 !
Alternatives to License Renewal of smaller units instead of three (600-MW) units would offer no known environmental benefits. A maximum of 13,900 metric tonnes (MT) (15,300 tons) of coal and 760 MT (840 tons) of lime / limestone l per day would be delivered by barge to the existing plant dock. Coal is assumed to have a heating v:lue of 30,000 Joule / kilogram (J/kg) (13,000 BTU per pound) and ash content of 10 percent. The l sulfur content of the coal would be 0.8 percent. Ths following discusses the environmental impacts of converting the current CCNPP site to a coal-fired g:neration facility and building a similar facility on a greenfield site. The impacts are summarized in Tcble 8-2.
. Land Use: The coal-fired generation alternative would necessitate converting roughly an additional 360 ha (900 acres) of the 2108-acre CCNPP site to industrial use (plant, coal storage, and ash and l scrubber sludge disposal), expanding the altered area at the site from 90 ha (220 acres) to 450 ha (1120 acres). Currently, this land is open space, some of it is farmed, and the rest is a revegetated dredged spoils disposal area known as Lake Davies. Facilities would also need to be constructed to control and treat leachate from coal storage areas, and ash and scrubber waste disposal areas.
The existing switchyard and transmission system would be used. It is assumed that coal-fired generation structures and facilities, incluoing coal storage and waste disposal, would be located in one or more of the CCNPP site open areas. BGE indicated that the power block and coal pile alone would occupy approximately 120 ha (300 acres). Approximately 240 ha (600 acres) (South Carolina Electric and Gas Co.1991) would be used to dispose of 1.4 million MT (1.5 million tons) of l waste per year (ash and scrubber sludge) produced during a 40-year plant lifetime. In contrast, the GEIS estimate for constructing a 1000-MW coal plant at a new site would require approximately 700 l ha (1700 acres), almost twice as much land. Converting 360 ha (900 acres) onsite from agricultural and revegetated spoil disposalland to industrial use would be a detectable change that would noticeably alter the present land-use pattem. Although agricultural usage would be eliminated at the site, site agricultural lands are not unique in the region, and eliminating agriculture at the CCNPP site should not affect offsite l agricultural land use. Almost 400 ha (1000 acres) of the site's natural habitat would remain unaffected by the construction, and no important attribute would be destabilized. The impact of coal-fired generation on land use is best characterized as MODERATE; its impact would be greater l than the proposed action. In contrast, land use for a coal-fired generation attemative using once-through cooling at an attemative greenfield site would require an additional 60 ha (150 acres) for offices, roads, parking areas, and a switchyard. This is in addition to the 360 ha (900 acres) discussed previously. An additional 170 ha (424 acres) would be needed for transmission lines (assuming the plant is sited l 16 km [10 miles) from the nearest intertie connection), for a total of approximately 600 ha l (1500 acres). Depending on transmission line routing, these alternatives could result in NUREG-1437, Supplement 1 8-5 October 1999
Alt:rn:tiv:S to License R:n;wil l MODERATE or LARGE land-uSe impacts Consistent with the GEIS Characterization of land uSe at a greenfield Site. Table 8-2. Summary of Environmental Impacts from Coal Alternative-OnCe-Through Cooling Calvert Cliffs Site Alternate "Greenfield" Site impact Category impact Comments impact Comments l Land Use MODERATE Uses another 360 ha (900 acres) of MODERATE 600 ha (1500 acres) including CCNPP site to LARGE transmission lines Ecology SMALL Use of previously disturbed areas MODERATE 1mpact will depend on ecology of site to LARGE l Water Use and Quakty:
- Surface Water SMALL . Uses existing intake and discharge SMALL to impact will depend on volume and structures MODERATE other characteristics of receiving water
. Volume and temperature rise the same
- Groundwater LARGE . Increases groundwater usage to SMALL to impact will depend on site 0.13 m2/s (3 milhon gpd) LARGE charactenstics and availability of .
. Increase could destabilize resource groundwater l Air Quality MODERATE . Sulfur oxides MODERATE Same impacts as Calvert Chffs site.
- 3250 MT (3600 tons)/yr although pollubon control standards
- allowances required may vary
. Nitrogen oxides
- 1525 MT (1680 tons)/yr
- allowances required
. Particulate
- 210 MT (234 tons)/yr filterable
- 50 MT (54 tons) PMw
. Carbon monoxide
- 1060 MT (1170 tons)/yr
. Mercury
- small emissions l Waste MODERATE 1.4 million MT (1.5 million tons)/yr fly ash MODERATE Same impacts as Calvert Cliffs site; and scrubber sludge waste disposal constraints may vary l Human Health SMALL Impacts considered minor SMALL Same impact as Calvert Chffs site Socioeconomics MODERATE 1500 to 2000 additional workers during MODERATE Construction impacts would be 5-year construction persod, followed by relocated. Community near CCNPP reduction from current 1550 to 220 would still experience reduction from persons 1550 persons to 220 persons Aesthetics MODERATE Visual impact of large h dustrial facility MODERATE Attemate locations could reduce to LARGE and stacks would be sigr.ificant to LARGE aesthetic impact if siting is in an industrial area Archeological and SMALL only previously disturbed areas would be SMALL Altemate location would necessitate Historical Resources affect *d cultural resource studies Environmental Justice MODERATE impacts on minority and low-income SMALL to impacts will vary depending on communities should be similar to those LARGE population distribution and make up experienced by the population as a whole. Impacts on hotising are likely.
l October 1999 8-6 NUREG-1437, Supplement 1
l Altematives to Licensa R:newal
- Ecoloav: Locating an alternate energy source at the existing CCNPP site should not noticeably alter ecological resources due to the use of previously disturbed areas and the existing intake and discharge system. Important CCNPP site ecological resources, such as the special-status species (discussed in Sections 2.2.5 and 2.2.6), would not be expected to be significantly affected, and approximately 400 ha (1000 acres) of natural habitat at the site would remain untouched by construction. The impact to the Chesapeake Bay ecology would be expected to remain unchanged because the once-through cooling system at CCNPP has not shown significant negative impact to the Bay. The appropriate characterization of coal-fired generation ecologicalimpacts of the CCNPP site would be SMALL.
Constructing a coal-fired plant at a greenfield site, particularly one sited in a rural area with , considerable habitat, would certainly alter the ecology and could impact any endangered or j threatened species present at the site. These ecological impacts could be MODERATE to LARGE l consistent with the GEIS characterization of ecologicalimpacts at a greenfield site.
- Surface Water Use and Quality: The coal-fired generation altemative is assumed to use the existing l CCNPP intake and discharge structures as part of a once-through cooling system. This alternative ;
would minimize environmentalimpacts since minimal construction would be required to adapt the system to the coal-fired altemative. it is assumed that the coal-fired attemative cooling water volume and temperature rise would be approximately the same as for the current nuclear plant (i.e., l 140 m*/s [3200 million gpd] with a 7*C [12*F] temperature rise). This temperature rise would l ) comply with the existing CCNPP National Pollutant Discharge Elimination System (NPDES) permit l (MDE 1994). Surface water quality would also be affected by the need for routine maintenance dredging at the existing barge dock to support daily barge traffic. Best management practices required by the County Erosion and Sediment Control Ordinance would minimize erosion and sedimentation that would be expected from land-clearing activities. The GEIS analysis determined that surface water quality, hydrology, and use impacts for license renewal would be SMALL. Because the coal-fired generation alternative is assumed to have the same discharge characteristics as CCNPP, and maintenance dredging impacts would be temporary and localized, surface water impacts are expected to remain SMALL; the impacts would be so minor that they would not noticeably alter any important attribute of the resource. For altemative greenfield sites, the impact to the surface water would depend on the volume associated with the cooling system and characteristics of the receiving body of water. The impacts would be SMALL or MODERATE.
= Groundwater Use and Quality: The reduced workforce size (1550 for two nuclear unit operation to an estimated 220) would reduce groundwater withdrawals for potable water use, but additional withdrawals would be needed for wet-scrubber sulfur oxides emissions control and boiler makeup.
Maximum groundwater consumption is assumed to be 0.05 m3/s per unit (800 gpm or 1,152,000 l gpd). This would exceed the amount authorized by the currer,t groundwater allocation permit. ! I NUREG-1437, Supplement 1 8-7 October 1999
Alt:m:.tiv:s to License R:ntwil Leachate from coal storage areas and ash and scrubber waste disposal areas would have to be controlled to avoid grourhater contamination. The GEIS did not address groundwater impacts from coal-fired generation. However, groundwater withdrawa!s in Calvert and St. Mary's Counties by public water supply systems, such as Lexington l Park, and the Pa'tuxent River Naval Air Station is of some concem in the region. The coal-fired l generation attemative would increase the site groundwater use from a current a terage 0.017 m'/s l (392,000 gpd) to a potential maximum of more than 0.13 m /s (3,000,000 gpd This would significantly exceed the current site's groundwater allocation permit of 0.02 m'/s (450,000 gpd). ( Such an increase would noticeably alter the site's impact on groundwater resources. It might be sufficient to destabilize the resource due to the volume of groundwater available. For these { reasons, the appropriate characterization of coal-fired generation groundwater impacts would be LARGE. For attemative greenfield sites; the irnpact to the groundwater would depend on the site characteristics, including the amount of groundwater available. The impacts would range between SMALL and LARGE.
. Air Quality: BGE assumed that each of the three units could be 60-m (200-feet) tall, would be tangentially fired, dry-bottom boilers, and would include an approximately 180-m (600-foot) high stack. This firing configuration was chosen because it would have moderate uncontrolled emissions l of nitrogen oxides (NO,) compared with other applications. NO, emissions controls would include l low NO, bumers, overfire air, and post-combustion selective catalytic reduction. The combination of l low NO, bumers and overfire air would achieve a NO, reduction of 40 to 60 percent from l uncontrolled levels. These combustion controls, along with selective catalytic reduction, can l achieve the current upperlimit of NO, control (95 percent reduction). Based on an operating l capacity factor of 83.9 percent, the resulting annual NO, emissions would be approximately 510 MT l (560 tons) per unit (EPA 1993; Delmarva Power and Light Co.1992). Each unit would have fabric filters or electrostatic precipitators (99.9 percent particulate removal efficiency) and a wet lime / limestone flue gas de-sulfurization system (95 percent scrubber removal efficiency). Based on an operating capacity factor of 83.9 percent, the resulting annual emissions per unit would be 71 MT (78 tons) of filterable particulates,16 MT (18 tons) of particulate matter having a diameter of l 10 microns or less (PMw), and 1090 MT (1200 tons) of sulfur oxides (SO,). Carbon monoxide emissions would be approximately 350 MT (390 tons) per year per unit (EPA 1993; Delmarva l Power and Light Co.1992).
Air quality impacts of coal-fired generation vary considerably from those of nuclear power due to l emissions of SO,, NO,, particulates, and CO. The air quality impacts would be considered MODERATE for coal-fired generation. The impacts would be clearly noticeable, but would not l destabilize air quality. The following discussion of SO, and NO, emission regulatory provisions is l taken from the BGE Integrated Resource Plan (IRP) (BGE 1995). October 1999 8-8 NUREG-1437, Supplement 1 I
i \ l Alt;mitivas to License R:newal l l l l \ The impacts at a greenfield site would be similar to those at the CCNPP site, although pollution control standards may vary. Therefore, the impacts would be MODERATE. Sulfur oxides emissions: Using current SO, emissions control technology, the total annual stack l cmissions would include approximately 3250 MT (3600 tons) of SO,, most of which would be sulfur l dioxide (SO2). Additional reductions could become necessary. The acid rain provision of the Clean l Air Act (CAA) (Sections 403 and 404) capped the nation's SO2 emissions from power plants. Under l the CAA, affected fossil fuel-fired steam units are allocated a number of SO2 emission allowances. l To achieve compliance, each utility must hold enough allowances to cover its SO2 emissions l l cnnually or be subject to certain penalties. If the utility's SO, emissions are less than its annually l j cllocated emission allowances, then the utility may bank the surplus allowances for use in future l years. A SO allowances 2 market has been established for the buying and selling of allowances. [ BGE has SO, allowances that it anticipates will last until 2002 for its existing coal-fired units. To l operate a coal-fired generation altemative beginning in 2014, however, BGE would have to ; purchase additional allowances or further reduce SO2 emissions at existing coal-fired plants. BGE l l could achieve further reductions by shutting other plants, by lowering coal sulfur content (e.g., pre-combustion cleaning), or by increasing emissions removal efficiency at existing plants. Because of l cllowances, any major new combustion facility in Maryland would not add SO 2 impacts on a regional l basis, though it might do so locally. l i Nitroaen oxides emissions: Using currently available control technology, the total annual NO, l l cmission would be approximately 1525 MT (1680 tons). Section 407 of the CAA establishes an j cnnual NO, emissions reduction program. In addition, provisions in the Northeast Ozone Transport l Region, authorized by Section 184(a) of the CAA, are more stringent. The current, reasonably l tvailable control technology (RACT) is not expected to achieve the ambient ozone standard (40 CFR 50.9, 50.10), and further regional NO, reductions would be necessary. To implement a coal- l fired attemative, BGE would be required to offset its corporate NO, emissions through further l l reductions in NO, emissions elsewhere, by shutting other sources down, or by backfitting to reduce l NO, formation (e.g., installing over-fired air, low NO, bumers, flue gas recirculation, and selective l non-catalytic and catalytic reduction systems). Attematively, offsets might be available for purchase on the open market. A major new combustion facility would not add to net regional emissions, l though it might do so locally. l Particulate emissions: The total estimated annual stack emissions would include 210 MT (234 tons) of filterable particulates and 50 MT (54 tons) of particulate matter having a diameter of 10 microns l or less (PMw). In addition, coal handling equipment would introduce fugitive particulate emissions. l l Carbon monoxide emissions: The total CO emissions would be approximately 1060 MT (1170 tons) l per year. The GEIS analysis did not quantify coal-fired emissions, but implied that air impacts would be substantial and mentioned global warming and acid rain as potential impacts. Adverse human health effects from coal combustion have led to important Federal legislation in recent years, and NUREG-1437, Supplement 1 8-9 October 1999
Alt:rnativrs to Licensa R:n:wal public health risks, such as cancer and emphysema, have been associated with the products of coal ; combustion. Federal legislation and large-scale concems, such as acid rain and global warming, l are indications of concerns about air resources. SO 2emission allowances, NO, emission offsets, l low NO, bumers, overfire air, selective catalytic reduction, fabric filters or electrostatic precipitators, ) and scrubbers may be required as mitigation measures. Mercury: Coal-fired boilers account for nearly a third of mercury emissions in the United States. Technologies available to control mercury emissions have varying degrees of success. In response l to growing concems with mercury, the CAA has required the EPA to identify mercury emission sources, evaluate the contributions of power plants and municipal incinerators, identify control technologies, and evaluate the toxicological effects of eating mercury-contaminated fish. It is likely that these studies will lead to additional restrictions conceming mercury emissions associated with coal-fired power plants, as well as other sources of mercury emissions. The Maryland Power Plant Research Program's recent studies have indicated that although coal-fired power plants contribute to mercury emissions, the resulting concentrations are not high enough to adversely affect humans l or other organisms. Therefore, the probable effect of mercury emissions on human health would be SMALL.
. Waste: Coal combustion generates waste in the form of ash, and air pollution control equipment generates additional ash and scrubber sludge. Approximately 1.4 million MT (1.5 million tons) of this waste would be generated annually for 40 years and disposed of onsite, accounting for 240 of the 360 ha (600 of the 900 acres) of land-use. While only half of these values are directly attributable to the alternative to a 20-year CCNPP license renewal, the total values are pertinent as a cumulative impact. This impact could extend well after the 40-year operation life because revegetation management and groundwater monitoring for leachate contaminant impacts could be a permanent requirement.
l The GEIS analysis noted that large amounts of fly ash and scrubber sludge would be produced and would require constant management. BGE agrees that disposal of this waste could noticeably affect land use and groundwater quality, but believes that, with appropriate management and monitoring, it would not destabilize any resources. After closure of the waste site and revegetation, the land would be available for other uses, and regulatory requirements would ensure groundwater protection. For these reasons, the appropriate characterization of coal-fired generation waste impacts would be MODERATE; the impacts would be clearly noticeable, but would not destabilize any important resource. Siting the facility on an attemate greenfield site would not alter waste generation, although other sites might have more constraints on disposallocations. Therefore, the impacts would be MODERATE. i October 1999 8-10 NUREG-1437, Supplement 1
Altemativas to Licensa Renewal
. Human Health: Coal-fired power generation introduces worker risks from fuel and lime / limestone mining, and worker and public risks from fuel and lime / limestone transportation and stack emissions inhalation. Stack impacts can be very widespread and health risks difficult to quantify. This attemative also introduces the risk of coal-pile fires and attendant inhalation risks.
The GEIS analysis noted that there could be human health impacts (cancer and emphysema) from inhalation of toxins and particulates, but did not identify the significance of this impact. Regulatory agencies, such as the EPA and the Maryland Department of the Environment (MDE), focus on air l emissions and revise regulatory requirements, or propose statutory changes, based on human health impacts. Such agencies also impose site-specific emission permit limits as needed to protect human health. Thus, coal-fired generation human health impacts would be SMALL. Siting the facility at an attemate greenfield site would not alter the expected human health effects. Therefore, the impacts would be SMALL.
. Socioeconomics: Construction of the coal-fired alternative would take approximately 5 years. It is l assumed that construction would take place concurrently while CCNPP continues operation and f would be completed at the time CCNPP would halt operations. BGE estimated the workforce would be expected to average 1500 with a peak of 2000 additional workers during the 5-year construction l period. The surrounding communities would experience demands on housing and public services that could have large impacts. After construction, the communities would be impacted by the loss of jobs; construction workers would leave, the nuclear plant workforce (1550) would decline through a decommissioning period to a minimal maintenance size, and the coal-fired plant would introduce only 220 new jobs.
The GEIS analysis noted that socioeconomic impacts at a rural site would be larger than at an urban site because more of the estimated 1200-2500 peak construction workforce would need to move to the area to work. Operational impacts could result in moderate socioeconomic benefits in the form of several hundred additional jobs, substantial tax revenues, and plant expent'aures. The size of the coal-fired generation construction workforce and plant-related spending during construction would be noticeable. However, due to the site's proximity to large labor pools in the Washington, D.C., and Baltimore areas, SGE would not expect construction workers to move to the CCNPP area. Operationalimpacts would include an eventualloss of approximately 1330 jobs (1550 for two nuclear units down to 220 for the coal-fired plant), with a commensurate reduction in demand on socioeconomic resources and contribution to the regional economy. BGE would expect that the area's rapid population growth would prevent any destabilization of socioeconomic resources. For these reasons, the appropriate characterization of coal-fired generation socioeconomic impacts would be MODERATE; the impacts would be clearly noticeable, but would not destabilize any important resource. NUREG-1437, Supplement 1 8-11 October 1999 l
Alt mativ:s to License R:n:wil Construction at another site would relocate some socioeconomic impacts, but would not eliminate them. The community around CCNPP would still experience the impact of CCNPP operational job loss, and the communities around the new site would have to absorb the impacts of a large, temporary workforce and a moderate, permanent workforce. Therefore, the impacts are MODERATE.
. Aesthetics: The three power plant units, which could be as much as 60-m (200-feet) tall, would be visible over intervening trees for miles around, particularly in both directions along the reach of the Chesapeake Bay. The three 180-m (600-foot) tall stacks could be visible as far away as Annapolis, a distance of 64 km (40 miles). This view would contrast strongly with what is otherwise a natural-appearing rural area, with woods and farming areas. Coal-fired generation would also introduce additional mechanical sources of noise (e.g., induced-draft fans and coal handling equipment) that may be audible offsito due to their proximity to the Bay.
The GEIS noted that aesthetic impacts from such a large construction effort in a rural area could be substantial. Industrial structures that would be located atop the 30-m (100-foot) cliffs at the CCNPP site would tower above area vegetation and create a noticeable visual impact for a large area. Aesthetics is a significant attribute of the Bay's westem shore in the CCNPP site area, given the predominantly natural-appearing rural viewscape from the Chesapeake Bay. A coal-fired generating station would contrast strongly with the existing resource. The aesthetics impacts would be MODERATE to LARGE. Altemative locations could reduce the aesthetic impact of coal-fired generation if siting was in an area that was already industrialized. In such a case, however, the introduction of such tall stacks and cooling towers would probably still have a MODERATE incremental impact. Other sites could show a LARGE impact. l . Archaeolooical and Historic Resources: The GEIS analysis noted that impacts to cultural resources would be relatively SMALL unless important site-specific resources were affected. Under this attemative, cultural resources inventories would be required for any lands that have not been l previously disturbed to the extent that no archaeological or historic resources might remain. Other land, including areas where minimal disturbance of the surface, such as farming, has occurred, would require field cultural resources inventory, identification and recording of extant archaeological l and historic resources, and possible mitigation of adverse effects from subsequent ground-disturbing actions related to physical expansion of the plant site. Therefore, the impacts would be SMALL. Construction at another site would necessitate studies to identify, evaluate, and mitigate potential impacts of new plant construction on cultural resources. This would be required for all areas of potential disturbance at the proposed plant site and along associated corridors where new October 1999 8-12 NUREG-1437, Supplement 1
)
u_
Altrrnativ:s to Licensa Rentw:1 construction would occur (e.g., roads, transmission corridors, or other rights of way). Impacts can generally be managed and maintained as SMALL.
. Environmental Justice: No environmental pathways have been identified that would result in disproportionately high and adverse environmental impacts on minority and low-income populations l if a replacement coal-fired plant were built at the CCNPP site. Some impacts on housing availability l
and prices during construction might occur, and this could disproportionately affect the minority or l low-income populations. Impacts at other sites would depend upon the site chosen. These impacts l would be MODERATE. If the replacement plant were built in Calvert County, the County's tax base would be largely maintained, and some potential negative socioeconomic impacts on the low- l income or minority populations would be avoided. If the plant were built elsewhere, environmental
. justice impacts would be SMALL to LARGE, depending on the population distribution and make-up. l 8.2.1.2 Closed-Cycle Cooling System l BGE has also evaluated a cooling-tower-based, closed-cycle cooling system that would use the existing intike and discharge structures (Gilbert / Commonwealth 1996). Flow requirements would be less (80 percent reduction) than the once-through cooling system. This attemative would add an approximately 160-m (520-foot) high natural draft cooling tower for each unit, which would occupy a total of 10 ha (25 acres). Cooling water consumption, due to evaporation, would be approximately 1.5 m'/s (35 million gpd). Total water flow, including tempering water and tower makeup water, would l be 23 m8/s (520 million gpd). The closed-cycle cooling system would introduce cooling tower blowdown that would be at least two-and-one-half times as saline as the Chesapeake Bay. Cooling tower operation would require more electrical power than the once-through cooling system due to the
' mod;fied pumping systems. The towers would discharge a plume of water vapor and a measurable amtunt of saltwater drift. Mrchanical draft cooling towers are an attemative to natural draft cooling towers. Mechanical draft cooling towers are 15- to 30-m (50- to 100-ft) tall, but would demonstrate operational impacts similar to tha natural draft towers noted above. The change in environmental impacts from redesigning the site for cooling towers are listed in Table 8-3. The overall impacts are also discussed below.
- Land Use: A closed-cycle cooling system attemative would impact an additional 10 ha (25 acres)
' for cooling tower construction at either the greenfield site or the CCNPP site. These alternatives l would result in a minor to moderate change above those already considered for the once-through cooling attemative. The overallimpact would be SMALL to MODERATE at CCNPP, MODERATE to LARGE elsewhere, j 1
NUREG-1437, Supplement 1 8-13 October 1999 J
Att:mitiv:s to Licensa Rrn:wil l l Table 8-3. Summary of EnvironmentalImpacts from Altemate Cooling System (Cooling Towers with Closed-Cycle Cooling) Change in impact from Calvert Cliffs impact Category Once-Through Cooling Comments l Land Use Minor to moderate change 10 additional ha (25 acres) required l Ecology Minor change . Additional impact to terrestrial ecology from salt drift
. Reduced impact to aquatic ecology l Water Use and Quality Surface Water Minor change . Blowdown is 2-1/2 times as saline as Chesapeake Bay
. Reduced flow Groundwater No change None Air Quality No change None Waste No change None Human Health No change None Socioeconomics - No change None Aesthetics Small change . Addition of three 160-m (520-ft) cooling towers OR
. Noise from mechanical draft towers Archaeology and Minor change Minimal cultural studies possibly required l Historic Resources Environmental Justice No change None
. Ecoloov: The closed-cycle cooling system attemative would further reduce opera'tional aquatic ecology impacts, but would introduce risk to vegetation, particularly tobacco crops, from salt drift.
However, these ecological impacts result in minor changes above those for the once-through l cooling attemative, resulting in SMALL overallimpacts at CCNPP and MODERATE to LARGE impacts elsewhere. l . Surface Water Use and Quality: Although surface water impacts are expected to remain small, the closed-cycle cooling system attemative would introduce cooling tower blowdown that would be at least two-and-one-half times as saline as the Chesapeake Bay, but, because of the reduced flow, surface water quality impact changes would be minor; overall impacts would be SMALL at CCNPP and SMALL to MODERATE elsewhere. l Groundwater Use and Quality: The facility's use of groundwater would not be impacted as a result l of the variation between once-through cooling system and a cooling-tower-based system. Overall ! impacts would be SMALL at CCNPP and SMALL to MODERATE elsewhere. October 1999 8-14 NUREG-1437, Supplement 1
Altsrnatives to Lic nsa Renewal e ' Air Quality: The air quality would be the same whether a cooling-tower-based closed-cycle cooling system or a once-through cooling system was used. Overall impacts would be MODERATE at all locations. Waste The amount of waste and impacts resulting from waste disposal would be the same whether a cooling-tower-based closed-cycle cooling system or a once-through cooling system was t used. Overallimpacts would be MODERATE at alllocations. 1 Human Health: Human health effects would be the same whether a cooling-tower-based closed-cycle cooling system or a once-through cooling system was used. Overallimpacts would be SMALL at alllocations.
. Socioeconomics: Socioeconomic impacts would be the same whether a cooling-tower-based closed-cycle cooling system or a once-through cooling system was used. Overall impacts would be MODERATE at alllocations.
. - Aesthetics: The closed-cycle cooling system attemative would increase aesthetic impacts by Edding three 160-m (520-ft) cooling towers and associated plumes. Although the ER assumed use of natural draft towers as an alternative technology, mechanical draft towers are also available. ;
Such devices, being only 15- to 30-m (50- to 100-ft) tall, would reduce the visual impact of natural l draft towers. Mechanical draft towers, however, introduce another noise source. Smallincremental change; MODERATE to LARGE overall impact.
. Archaeoloaical and Historic Resources: Minimal amounts of additional cultural resource studies l h would be required before construction of cooling towers, if towers were constructed on land that l had already had cultural resource studies, further studies would not be necessary. Minor incremental change; SMALL impacts at all locations.
- Environmental Justice: Environmental justice impacts would be the same whether a cooling-tower-based closed-cycle cooling system or a once-through cooling system was used. Overall impacts cre MODERATE at CCNPP; SMALL to LARGE elsewhere.
1 8.2.2 Gas-Fired Generation l l In the ER, BGE described a representative gas-fired plant that was based on documentation submitted q to the Maryland Public Service Commission (PSC) for the Perryman Power Plant (BGE 1989), coupled l l with EPA documentation for the Polk Power Station (EPA 1994). BGE also used this information to scale the size of the plant (megawatts and land usage) described in the ER. The Perryman and Polk facilities are typical of gas-fired technology being constructed and operated today. In addition,
~ information from the EPA and DOE's Energy Information Administration (EIA) technical publications on l - fusi specifications and best available emission control technology was used to specify fuel types and l NUREG-1437, Supplement 1 8-15 October 1999 i
Alt:rnativas to License R:n:wal emission control technology that would be used in the gas-fired attemative (DOE 1995; EPA 1993). In some cases, BGE was able to use referenced data directly; in other cases, BGE appropriately scaled data to fit the size of the plant needed for a C LNPP altemative energy source. , ( It was assumed that it would take 1760-MW gas-fired generation to replace the 1690-MW CCNPP. The l increased size over current CCNPP capacity would be necessary to offset increased internal electrical
]
usage for pollution control and pumping water for cooling, but would not be as great as for the coal-fired 1 alternative due to reduced cooling water flow and pollution control needs. I It was assumed that a replacement natural gas-fired plant would use combined cycle technology. In the combined cycle unit, hot combustion gases in a combustion turbine rotate the turbine to generate electricity. Waste combustion heat from the combustion turbine is routed through a heat recovery steam generator to generate additional electricity. The size, type, and configuration of gas-fired generation units and plants currently operational in the United States vary and include simple-cycle combustion and combined-cycle units that range in size from 25 MW to 600 MW (EPA 1994). As with coal-fired technology, units may be configured and combined at a location to produce the desired amount of megawatts, and construction can be phased to meet electrical power needs. l l 8.2.2.1 Once-Through Cooling Systern l l The gas-fired generation attemative consists of four 440-MW combined-cycle units each consisting of two 155-MW simple-cycle combustion turbines and a 130-MW heat recovery steam generator. On an l average annual basis, these units would each generate up to 440 MW, providing the 1760 MW needed l to replace CCNPP. Natural gas typically has an average heating value of 3.7x107 J/m (1,000 DTU per l cubic foot) (DOE 1996; EPA 1993), and it would be the primary fuel; the gas-fired alternative plant ( would burn approximately 108 J/m8 -s (10 million cubic feet per hour). Low-sulfur No. 2 fuel oil would be the backup fuel (BGE 1989). Each unit would be less than 30 m (100 feet) high and would be designed with dry, low NO, combusters, water injection, and selective catalytic reduction. Each unit would exhaust through a 70-m (230-foot) stack after passing through heat recovery steam generators. This stack height is consistent with EPA regulations (40 CFR 51.100), which address requirements for determining the stack height of new emission sources. Section 51.100 allows stack heights based on good engineering stack height (as defined) or modeling, but does not allow credit for offsite contaminant level reduction for taller stacks. The 70-m (230-foot) height is based on the regulation's good engineering practice formula l using the tallest proposed onsite facility (i.e., the 28-m [92-foot) turbine building). While modeling would have to be used to justify stack height greater than 70-m (230 feet), the relatively flat terrain and low structures of the area indicate that modeling would not likely support a greater stack height. l Natural gas would be delivered via a newly constructed connection to the existing pipeline located parallel to Maryland Highway 2-4 near the CCNPP site, a distance of approximately 2.4 km (1.5 miles) October 1999 8-16 NUREG-1437, Supplement 1
Altzmatives to License Renewal (US Geological Survey 1987). The proposed route would follow an existing Southem Maryland Electric l Cooperative power line right-of-way onto the CCNPP site adjacent to the Lake Davies area. Approximately 4 ha (10 acres) would be disturbed during pipeline construction. The existing line curr:ntly has sufficient reserve capacity to supply the needs of the gas-fired attemative. Environmental impacts of conversion to the gas-fired generation option at both CCNPP and a greenfield sita are summarized in the following text and are listed in Table 8.4.
- Land Use: Gas-fired generation at the Calvert Cliffs site would require converting an additional 25 ha (60 acres) of the site to industrial use. This 25 ha (60 acres) would be used for the power block (BGE 1989). Currently, some of this land is farmed, and the rest is a revegetated dredged l spoils disposal area. An additional 4 ha (10 acres) would be disturbed during pipeline construction.
Some additional land would also be required for backup oil storage tanks. Gas-fired generation l land-use impact at the existing CCNPP site is SMALL; the impact would not be detectable or would be so minor that it would neither destabilize nor noticeably alter any important attribute of the resource. Construction at a greenfield site would impact approximately 4 ha (10 acres) for offices, roads, parking areas, and a switchyard. The power block would require 25 ha (60 acres). Some additional l 1:nd would also be required for backup oil storage. In addition, it is assumed that another 170 ha l f (424 acres) would be necessary for transmission lines (assuming the plant is sited 10 nd!es from the nearest intertie connection), although this is uncertain and would depend on actual plant location. l Including the land required for pipeline construction, a greenfield site would require approximately l 200 ha (500 acres). Depending on the transmission line routing, the greenfield site attemative could I result in SMALL to MODERATE land-use impacts. The GEIS estimated that land-use requirements for a 1000-MW gas-fired plant at a greenfield site would be SMALL (approximately 45 ha (110 acres) for the plant site), and that colocating with a l retired nuclear p! ant would reduce these impacts. The BGE tand-use estimate is less than the NRC estimate and is roughly one-tenth of the BGE estimate for coal-fired generation. The land-use change should not noticeably alter the overall site natural land-use pattem. Therefore, the impacts would be SMALL to MODERATE.
. Ecoloav: Siting gas-fired generation at the existing CCNPP site would have little ecologicalimpact because the facility would be constructed on previously disturbed areas. Additional acreage would include farmland and a dredged spoils disposal area. Ecological impacts would also be minimized by using the existing intake and discharge system. The impact to Chesapeake Bay ecology would be expected to remain unchanged because the operational monitoring of the effects of once-through cooling at CCNPP have not shown significant negative impacts. At the existing site, adding gas-fired generation would introduce construction impacts and new, albeit incremental, operational impacts.
NUREG-1437, Supplement 1 8-17 October 1999
Alt:m:tiv:s to License R:newal O l Table 8-4. Summary of Environmental Impacts from Gas-Fired Generation-Once-Through Cooling Alternative Calve t Cliffs Site Alternative "Greenfield" Site impact Category impact . Comments impact Comments Land Use SMALL . Additional 25 ha (60 acres) SMALL to 200 ha (500 acres) required for required for power block MODERATE site, pipelines, and an l . Additional 4 ha (10 acres) estimated 10-mi transtnission l disturbed for pipeline construction line connection l . Additionalland for backup oil . Additionalland for backup oil l storage tanks storage tanks Ecology SMALL Constructed on previously disturbed SMALL to impact depends on location and areas MODERATE endangered and threatened species l Water Use and l Quality:
- Surface Water SMALL 70 percent reduction in water flow SMALL to impact depends on volume and MODERATE characteristics of receiving body of water
- Groundwater SMALL Reduced groundwater withdrawals SMALL Groundwater would be used for due to reduced workforce potable water only l Air Quality SMALL to Primarily nitrogen oxides. Impacts SMALL to Same impacts as for CCNPP l
MODERATE could be noticeable, but not MODERATE destabilizing l Waste SMALL Waste generation is minor SMALL Same impacts as for CCNPP Human Health SMALL Impacts considered to be minor SMALL Same impacts as for CCNPP l Socioeconomics SMALL 500 to 750 additional workers SMALL Construction impacts would be during 3-year constructior, period; relocated. Community near l followed by reduction from 1650 CCNPP would still experience persons to 125 persons reduction from 1550 persons to 125 persons. Aesthetics SMALL to Visualimpact of stacks and SMALL to Attemate locations could reduce MODERATE equipment would be noticeable, but MODERATE the aesthetic impact if siting is in not as significant as coal option an industrial area. Archaeological and SMALL Only previously disturbed areas SMALL Attemate location would Historic Resources would likely be affected necessitate cultural resource studies l Environmental SMALL to impacts on minority and low-income SMALL to impacts vary depending on l Justice MODERATE communities should be similar to MODERATE population distribution and those experienced by the population makeup as a whole. Impacts on housing are possible. October 1999 8-18 NUREG-1437, Supplement 1 4 l I
Alt:mativ:s to License Renewal 1 The GEIS noted that land-dependent ecological impacts from construction would be SMALL unless site-specific factors should indicate a carticular sensitivity, and that operational impacts would be sr,ialler tnan for other fossil fuel technologies of equal capacity. The staff has identified no site-specific factors that would make gas-fired alternative ecological impacts larger than for the coal-fired titernative or license renewal. The appropriate characterization of gas-fired generation ecological impacts would be SMALL. Construction at a greenfield site would certainly alter the ecology of the site and could impact l threatened and endangered species. These ecologicalimpacts could be SMALL to MODERATE.
. Water Use and Quality: The plant would use the existing CCNPP intake and discharge structures l as part of a once-through cooling system; however, since cooling requirements would be less (70 percent reduction), flows would average approximately 2.3 m /s (1000 million gpd) (EPA 1994).
Water quality impacts would continue to be SMALL. The reduced workforce size (1550 to 125) would reduce groundwater withdrawals for potable water use; however, the existing groundwater impact is already small (Section 4.5.1). Water quality impacts from sedimentation during construction was another land-related impact that the GEIS categorized as SMALL. The GEIS also noted that operational water quality impacts would be similar to, or less than, those from other centralized generating technologies. The staff has concluded that water quality impacts from coal-fired generation would be SMALL, and gas-fired citemative water usage would be less than that for coal-fired generation. Surface water impacts would remain SMALL; the impacts would not be detectable or be so minor that they would not noticeably alter any important attribute of the resource. I For attemative greenfield sites, the impact on surface water would depend on the volume and other l characteristics of the receiving body of water. The imoacts would be SMALL or MODERATE. The impact on the groundwater would remain SMALL, since the groundwater would just be used for potable water, and the number of employees would be similar at either site.
. Air Quality: Natural gas is a relatively clean-burning fuel, but, due to the site's location within the l Northeast Ozone Transport Region and the Washington, D.C. nonattainment area for ozone, air quality impacts of gas-fired generation would be of concern. NO, emissions from the gas-fired alternative would be 350 MT (386 tons) per year (assuming a 60 percent thermal efficiency and l 0.004 kg [0.0088 pounds) NO, per 10' J [105 BTU]). As discussed in Section 8.2.1 for coal-fired l generation, regulations implementing Section 407 of the CAA might result in BGE having to further l reduce NO, by shutting down other sources or by backfitting to reduce NO, formation (e.g., installing l over-fired air, low NO, bumers, flue gas recirculation, and selective non-catalytic and catalytic l reduction systems). Because of required offsets, a new combustion source could not add l emissions on a regional basis, but it could locally. l NUREG-1437, Supplement 1 8-19 October 1999
Alt:mitivss to Licens3 R:nsw:1 The GEIS noted that gas-fired air quality impacts are less than other fossil technologies because j l fewer pollutants are emitted, and SO2 is not emitted at all. Emissions from the gas-fired altemative would be less than emissions from the coal-fired altemative. However, the gas-fired alternative l Nould contribute NO, emissions to an area that is classified as a serious nonattainment area for l ozone. Because NO, contribute to ozone formation, the reduced NO, emissions are still of concern, l and low NO, combusters, water injection, and selective catalytic reduction are regula, tory-imposed mitigation measures. For these reasons, the appropriate characterization of gas-fired generation air l impacts would be SMALL to MODERATE; the impacts, primarily NO,, would be clearly noticeable, l but would not be sufficient to destabilize air resources as a whole. Siting the gas-fired plant elsewhere would not significantly change air quality impacts, although the site could be located in an area that was not a serious nonattainment area for ozone. In addition, the location could result in installing more or less stringent pollution control equipment to meet the regulations. Therefore, the impacts would be MODERATE.
. Waste: There should be no solid waste products (i.e., ash) from natural gas fuel-burning. The GEIS concluded that waste generation from gas-fired technology would be minimal. Gas-firing results in very little combustion byproduct because of the clean nature of the fuel. Waste generation would be limited to typical office wastes. This impact would be SMALL; waste generation impacts l would be so minor that they would not noticeably alter any important resource attribute. Siting the l facility at an altemate greenfield site would not alter the waste generation; therefore, the impacts would continue to be SMALL.
. Human Health: The GEIS analysis mentions potential gas-fired attemative health risks (cancer and emphysema). The risk may be attributable to NO, emissions that contribute to ozone formation, which in tum contributes to health risks. As discussed in Section 8.2.1 for the coal-fired attemative, legislative and regulatory control of the nation's emissions and air quality are protective of human health, and the appropriate characterization of gas-fired generation human health impacts would be SMALL; that is, human health effects would not be detectable or would be so minor that they would l neither deMabilize nor noticeably alter any important attribute of the resource. Siting of the facility at an attemate greenfield site would not aiter the human health effects that would be expected.
Therefore, the impacts would be SMALL.
. Socioeconomics: it is assumed that gas fired construction would take place while CCNPP continues operation, with completion at the time that the nuclear plant would halt operations.
l Construction of the gas-fired alternative would take approximately 3 years, and the work force l during the construction period would average 500, with a peak of 750. Therefore, for the 3-year construction period, the site would have between 500 and 750 additional workers. During this time, the surrounding communities would experience demands on housing and public services that could have large impacts. After construction, the communities would be impacted by the loss of jobs; construction workers would leave, the nuclear plant workforce (1550) woula decline through a l October 1999 8-20 NUREG-1437, Supplement 1
Alt mativ:s to Lic nsa R:n:wal l decommissioning period to a minimal maintenance size, and the gas-fired plant would introduce ebout 125 new jobs. The GEIS noted that gas-fired construction socioeconomic impacts would not be very noticeable end that the small operational workforce would have the lowest socioeconomic impacts (local purchases and taxes) of any nonrenewable technology. BGE estimates that, compared to the coal-fired altemative, the smaller size of the construction workforce, the shorter construction timeframe, cnd smaller size of the operations workforce all would reduce socioeconomic impacts. For these reasons, gas-fired generation socioeconomic impacts would be SMALL; that is, socioeconomic cffects would be so minor that they would neither destabilize nor noticeably alter any important cttribute of the resource. Construction at another site would relocate some socioeconomic impacts, but would not eliminate them. The community around the CCNPP site would still experience the impact of CCNPP operational job loss, and the communities around the new site would have to absorb the impacts of a large, temporary workforce and a moderate, permanent workforce. Therefore, the impacts would be SMALL.
- Aesthetics: The combustion turbines and heat recovery boilers would be relatively low structures cnd would be screened from most offsite vantage points by intervening woodlands. The steam turbine building would be taller, approximately 30 m (100 feet) in height, and together with 70-m l (230-ft) exhaust stacks, would be visible offsite.
The GEIS analysis noted that land-related impacts, such as aesthetic impacts, would be small unless site-specific factors indicate a particular sensitivity. As in the case of the coal-fired citemative, aesthetic impacts from the gas-fired alternative would be noticeable. However, because the gas-fired structures are shorter than the coal-fired structures and more amenable to screening by vegetation, the staff determined that the aesthetic resources would not be destabilized by the gas-fired attemative. For these reasons, the appropriate characterization of gas-fired generation aesthetic impacts would be SMALL to MODERATE; the impacts would be clearly noticeable, but l would not destabilize this important resource. Altemative locations could reduce the aesthetic impact of gas-fired generation if siting was in an crea that was already industrialized. In such a case, however, the introduction of the steam generator building, stacks, and cooling tower plumes would probably still have a SMALL to MODERATE impact.
- Archaeoloaical and Historic: The GEIS analysis noted, as for the coal-fired attemative, that gas-fired altemative cultural resource impacts would be small unless important site-specific resources were affected. Gas-fired attemative construction at the CCNPP site would affect a smaller area within the footprint of the coal-fired attemative. As discussed in 8.2.1, site knowledge NUREG-1437, Supplement 1 8-21 October 1999
Alt mitiv:s to Licens3 R:n',wil minimizes the possibility of cultural resource impacts. Cultural resource impacts would be SMALL; that is, cultural resource effects would not be detectable or would be so minor that they would neither destabilize nor noticeably alter any important attribute of the resource. Therefore, the impact is SMALL. l Construction at another site could necessitate instituting cultural resource preservation measures, ! but impacts can generally be managed and maintained as SMALL. Cultural resources studies would be required for the pipeline construction and any other areas of ground disturbance associated with this alternative.
. Environmental Justice: No envirorimental pathways have been identified that would result in l disproportionately high and adverse environmental impacts on minority and low-income populations if a replacement gas-fired plant were built at the CCNPP site. Some impacts on housing availability l and prices during construction might occur, and this could disproportionately affect the minority or l low-income populations. The impacts would be SMALL to MODERATE. Impacts at other sites would depend upon the site chosen. If the replacement plant were built in Calvert County, the County's tax base would be largely maintained and some potential negative socioeconomic impacts l on the minority or low-income populations would be avoided. If the plant were built elsewhere, l Environmental Justice impacts would be SMALL to MODERATE, depending on the population density and make-up.
8.2.2.2 Closed-Cycle Cooling System BGE assumes that cooling for the gas-fired facility could also be accomplished by a closed-cycle system, which would also use the existing intake and discharge structures, but flow requirements would < be 90 percent less than the once-through cooling system (Gilbert / Commonwealth 1996). This l altemative would use an approximately 160-m (520-ft) high natural draft cooling tower for each unit. Cooling water consumption, due to evaporation, would be approximately 0.44 m8 /s (10 million gpd). Total water flow, including tempering water and tower makeup water, would be 6.7 m8 /s (152 million gpd). The closed-cycle cooling system attemative would introduce cooling tower blowdown that would be at least two-and-one-half times as saline as the Chesapeake Bay. Cooling tower operation would require more electrical power than the once-through attemative due to the modified pumping systems. Cooling towers would discharge a plume of water vapor and a small amount of saltwater drift. Mechanical draft cooling towers are an altemative to natural draft cooling towers. Mechanical draft l cooling towers are 15- to 30-m (50- to 100-ft) tall, but would demonstrate operational impacts similar to the natural draft towers noted above. The environrnentalimpacts of converting to a closed-cycle cooling system are essentially the same ] impacts as for the closed-cycle cooling system at a coal-fired plant. The impacts are discussed in Section 8.2.1.1 and are listed in Table 8-5. l l l I October 1999 8-22 NUREG-1437, Supplement 1
Alt matives to Lic nse R:n:wal Table 8-5. Summary of EnvironmentalImpacts of Gas-Fired Generation with Attemate l 9 Cooling System (Cooling Towers with Closed-Cycle Cooling) Change in impact from Calvert Cliffs impact Category Once-Through Cooling Comments Land Use Minor to moderate change Uses an additional 10 ha (25 acres) for cooling tower l construction Ecology Minor change . Additional impact to terrestrial ecology from salt drift
. Reduced impact to aquatic ecology Water Use and l Quility; l
- Surface Water Minor change . Blowdown is 2-1/2 times as saline as Chesapeake Bay
. Reduced flow
- Groundwater No change None Air Quality No change None Waste No change None Human Health Small Impacts considered minor Socioeconomics No change None Aesthetics Minor change Addition of four 160-m (520-ft) high natural draft cooling towers or noise from mechanical draft towers Archaeology and Minor change Minimal studies (if necessary) prior to construction of Historical cooling towers R: sources Environmental No change None Justice 8.2.3 Imported Electrical Power
" imported power" means power purchased and transmitted from electric generation plants that the cpplicant does not own and that are located elsewhere within the region, nation, or Canada. The epplicant imports substantial amounts of power from Ohio and Pennsylvania, especially from the Conemaugh and Keystone plants in western Pennsylvania. In 1996, Maryland was a substantial net importer of electricity; imports represented approximately 28 percent of electrical sales within the State.
Th3 epplicant imported approximately 10,500 gigawatt-hours in 1996, approximately 28 percent of total sil:s (MDNR 1999a). In theory, importing (purchasing) additional power is a feasible attemative to l CCNPP license renewal. However, regardless of the technology used to generate imported power, the g::nerating technology would be one of those described in this SEIS and in the GEIS (probably coal, natural gas, nuclear, or Canadian hydroelectric). The GEIS, Chapter 8, description of the NUREG-1437, Supplement 1 8-23 October 1999 f
Altimativas to License Renewal environmental impacts of other technologies is representative of the imported electrical power attemative to CCNPP license renewal. BGE stated that bulk sales and purchased power will continue to expand: Recent generating additions in the competitive electric market have been primarily either simple l- l . cycle combustion turbines or. combined cycle facilities with a lesser amount of coal-fired plants. BGE has stated and still believes that future generation additions will be predominantly satisfied by those technologies. Wdh the evolution of regional and national bulk power markets, the movement of electric energy between regions is expected to grow. There is a high probability that the importation of energy from Canada will continue. From a historical perspective, it has been BGE's experience that replacement energy for CCNPP is predominantly provided by interchange purchases from the Pennsylvania-New Jersey-Maryland (PJM) Interconnection, unless a specific l bilateral contract has been effected (BGE 1998a). Since April 1998, the PJM power pool has operated with an independent system operator and Pool Spot Energy Market (PX) that uses cost-i based bids from generators on a day-ahead basis. Membership in the PJM is open to different segments of the industry. According to the EIA's intemational Energy Outlook 1998 (EIA 1997): Hydro Quebec has targeted the U.S. market for future sales growth. Hydro Quebec currently owns Vermont Gas and has signed a deal with Enron to market electricity in the Northeast while selling l Enron's gas in Quebec. In April 1997, Hydro Quebec petitioned the Federal Energy Regulatory , l Commission (FERC) to sell electricity in the United States. In retum, it would allow U.S. competitors to wheel electricity into Quebec. In November 1997, Hydro Quebec received FERC approval to sell 4 power in the United States at market-based rates. l Depending on transmission availability, relative power costs, whether Canadian environmental and aboriginal rights controversies over the hydroelectric James Bay Project in Northem Quebec could be solved, and appropriate transmission agreements and facilities could be put in place, Hydro Quebec could be a future source of imported power. However, there would be significant environmental impacts in Northem Quebec. 8.2.4 Other Alternatives l - This section identifies attematives to CCNPP license renewal that are not feasible as direct l replacements for CCNPP and describes why the attematives are not considered feasible. l i October 1999 . 8-24 NUREG-1437, Supplement 1
i Alt:matives to Lic:nsa R:newal 8.2.4.1 Wind Wind speeds in most a.eas of Maryland average 13 to 16 km (8 to 10 mi) per hour. The GEIS stated tv:; rage wind speeds of more than 21 km (13'mi) per hour are normally required for wind turbines to operate efficiently. Some areas of western Maryland may have potential for use of wind energy, but th:se locations, found at the highest levels of sharp ridge lines, would incur high costs for land ccquisition and power line construction (MDNR 1986). Based on the GEIS land use estimate for wind power (the GEIS, Section 8.3.1, estimates 60,750 ha [150,000 acres) per 1000 MW-electric for wind power), replacement of CCNPP generating capacity, even assuming ideal wind conditions, would require dedication of almost 13,000 km2 (400 mir), an area about twice the size of the county (Calvert l County is approximately 5250 km2 [220 mi2]) in which CCNPP is located. Based on the lack of sufficient l wind speeds and the amount of land needed to replace CCNPP, the wind attemative would require a l larga greenfield site, which would result in a LARGE environmental impact. l 8.2.4.2 Solar Solrr power technologies, photovoltaic and thermal, cannot currently compete with conventional fossil-furled technologies in grid-connected applications due to high costs per kilowatt of capacity (DOE 1995). Maryland receives slightly more than 3.3 kilowatt-hours of solar radiation per square meter (kWh/m2 ) per day, compared to 5 to 7.2 kWh/m2 per day in areas of the West, such as California, which ara most promising for solar technologies (GEIS, Section 8.3.3). Because of the area's low rate of solar radittion and high technology costs, the role of solar power in Maryland is limited to niche applications tnd is not a feasible baseload attemative to CCNPP license renewal. 8.2.4.3 Hydropower Approximately 4 percent, or 535 MW, of Maryland generating capacity is hydroelectric (MDNR 1996). As GEIS, Section 8.3.4 points out, hydropower's percentage of the country's generating capacity is cxpected to decline because hydroelectric facilities have become difficult to site as a result of public concem over flooding, destruction of natural habitat, and destruction of natural river courses. GEIS, S:ction 8.3.4, estimates land use of 400,000 ha (1 million acres) per 1000 MW-electric for hydroelectric l l I power _ Based on this estimate, replacement of CCNPP generating capacity would require flooding mors than 6700 km; (2600 mi2), a LARGE impact on land use. Due to the lack of locations for siting a l hydroelectric faci'.ity large enough to replace CCNPP, local hydropower is not a feasible attemative to CCNPP license renewal on its own. See Section 8.2.3 for a discussion of Canadian hydropower. l 8.2.4.4 Geothermal l As illustrated by GEIS, Figure 8.4, geothermal plants might be located in tire westem continental United l States, Alaska, and Hawaii where hydrothermal reservoirs are prevalent, but would not be a feasible tit:rnative to CCNPP license renewal in Maryland. , l NUREG-1437, Supplement 1 8-25 October 1999 f l
Altimativas to Licens3 Ranswil 8.2.4.5 Wood Energy l A significant barrier to the use of wood waste to generate electricity is the high delivered fuel cost. States with significant wood resources, such as Califomia, Maine, Georgia, Minnesota, Oregon, Washington, and Michigan benefit from using local resources. The pulp, paper, and paperboard industries, which consume large quantities of electricity, are the largest consumer of wood and wood l . waste for energy, benefitting from the use of waste materials that could otherwise represent a disposal problem. However, the larger wood waste power plants are only 40 to 50 MW in size. The 10'SJ l (11.5 trillion BTU) of energy estimated to be available annually from Maryland forests (MDNR 1986) ' would only produce the amount of electricity that CCNPP produces in one month. Due to the lack of sufficient resource base in the Maryland area, wood waste is not a feasible attemative to renewing the CCNPP licenses. 8.2.4.6 Municipal Solid Waste The decision to bum municipal waste to generate energy is usually driven by thc need for an atternative to landfills rather than by energy considerations. The use of landfills as a waste disposal option is likely to increase in the near term; however, it is unlikely that many landfills will begin converting waste to energy because of unfavorable economics, particularly with electricity prices declining (DOE 1995). Therefore, municipal solid waste would not be a feasible altemative to CCNPP license renewal, particularly at the scale required. 8.2.4.7 Other Biomass-Derived Fuels In addition to wood and municipal solid waste fuels, there are several other concepts for fueling electric 4 generators, including buming energy crops, converting crops to a liquid fuel such as ethanol (ethanol is primarily used as a gasoline additive for automotive fuel), and gasifying energy crops (including wood waste). None of these technologies have progressed to the point of being competitive on a large scale or of being reliable enough to replacts a baseload plant such as CCNPP. For these reasons, such fuels l do not offer a feasible attemative to CCNPP license renewal in addition, these systems have LARGE l impacts on land use.
. 8.2.4.8 Oil '
BGE has several oil-fired units. However, the cost of oil-fired operation is about eight times as expensive as nuclear and coal-fired operation. In addition, future increases in oil prices are expected to make oil-fired generation increasingly more expensive than coal-fired generation (DOE 1996). For l these reasons, oil-fired generation is not a feasible attemative to CCNPo license renewal nor is it likely l ;to be included in a mix with other resources, expect as a back-up fuel. October 1999 8-26 NUREG-1437, Supplement 1
Alt:mitivas to Licens3 R:ntwal 8.2.4.9 Advanced Nuclear Power Work on advanced reactor designs has continued, and nuclear plant construction continues overseas. l However, the cost of building a new nuclear plant and the political uncertainties that have historically surrounded many nuclear plant construction projects are among the factors that have led energy forecasters such as the EIA to predict no new domestic orders for the duration of current l foracasts-through the year 2010 (DOE 1996). For these reasons, new nuclear plant construction is l not considered a feasible attemative to CCNPP license renewal. l 8.2.4.10 Delayed Retirement - CCNPP provides about 27 percent of BGE's generating capacity and approximately 40 percent of its ensrgy requirements. Even without retiring any generating units, BGE expects to require additional capacity in 2000 or 2001. Thus, even if substantial capacity were scheduled for retirement and could be delayed, some of the delayed retirement would be needed just to meet load growth. In the current Stranded Cost Filing with the Maryland Public Service Commission, BGE used the 1992 Technical Update of Depreciation Rates for BGE for the purpose of modeling power plant retirement. This retirement schedule is presented in Table 8-6. Using a reserve obligation of 15 percent and based on information from the 1998 BGE Integrated R: source Plan, BGE will have a PJM reserve obligation of 6759 MW (5877 x 1.15) in the year 2000. l With a current supply portfolio projected to be 6562 MW, BGE is expecting to be deficient by nearly 200 MW in the year 2000, even with CCNPP available. During the assessment of capacity
' requirements for the ER, BGE did not incorporate any retirement plans (BGE 1998b) (i.e., the plants in l Table 8-6 were assumed to be available). Therefore, CCNPP would be required in part to offset any actual retirements that occur, so that delayed retirement of other BGE generating units could not provide a replacement of the 1690 MW supplied by CCNPP and could not be a feasible attemative to CCNPP license renewal.
8.2.4.11 Utility-Sponsored Conservation Th3 Maryland PSC requires Maryland electric utilities to implement demand-side management
- as a l moins to conserve energy and to take demand-side management energy savings into account in long-rtnge planning. The applicant has an extensive program of residential, commercial, and industrial
' (c) The GEIS, Section 8.3.14, discusses conservation technologies to conserve energy consumption.
These measures generally come under the heading of " demand-side management," which is a collection of diverse measures to reduce customers' electricity consumption without adversely affecting service. NUREG-1437, Supplement 1 8-27 October 1999
Alt:rnativ;s to License R':newil Table 8-6. Retirement Schedule of BGE Power Plants BGE RETIREMENT SCHEDULE FOR STRANDED Cost flung Summer Capacity l Unit Name (MW) Retirement Year Gould Street 3 104 2010 Riverside 4 - 78 2010 l C.P. Crane CT 14 2010 H.A. Wagner CT 1 ' 14 2010 Notch Cliff 1-8 128 2010 Philadelphia Road 1-4 64 2010 Perryman 1-4 208 2010 Riverside 6-8 173 2010 Westport 5 121 2010 Total 904 C.P. Crane 1 190 2015 C.P Crane 2 195 2015 H.A. Wagner 1 137 2015 H A Wagner 2 135 2015 H.A. Wagner 3 324 201 H.A. Wagner 4 410 2015 i Total 1391 programs designed to reduce both peak demands and daily energy consumption (demand-side management). Program components include the following:
- Peak cliopino oroarams: Include energy saver switches for air conditioners, heat pumps, and water heaters, allowing the applicant to interrupt electrical service to reduce load during periods of peak demand; dispersed generation, giving the applicant dispatch control over customer backup generation resources; and curtailable service, allowing the ap- "nt to reduce customers' load
~
during periods of peak demand.
. Load shiftino oroarams: Use time-of-use rates and cool storage rebate programs to encourage shifting loads from on-peak to off-peak periods. j October 1999 8-28 NUREG-1437, Supplement 1
1 Alt:rnatives to License Ren:wal l e Conservation proarams: Promoting use of high-efficiency heating, ventilating, and air conditioning; cncouraging construction of energy-6'ficient homes and commercial buildings; improving energy cfficiency in existing homes; providing iecentives for use of energy-efficient lighting, motors, and compressors. The applicant originally estimated that its demand-side management program would produce an annual pe k demand generation reduction of about 700 MW, and BGE believed that it could continue to incrcase generation savings from demand-side management. The applicant's load growth projection enticipated a demand-side management savings of about 1000 MWin 2016. Because these savings tra part of the long-range plan for meeting projected demand, however, it is not available as an " offset" for CCNPP, and the applicant did not foresee availability of another 1690 MW (CCNPP capacity). For th:se reasons, the demand-side management is not a feasible altemative to renewing the CCNPP heense. Each of the conservation program components identifie
- by the applicant still exist in their load management programs. However, the emerging competitive electricity market along with pending retail choice for customers has significantly reduced the long-term growth expectations for most programs (MDNR 1999). BGE's 1998 integrated resource plan (IRP) response to the Maryland PSC indicated an l l cxisting total of about 730 MW in 1997, whereas the existing value for 1996 reported in the ER was l "cbout 700 MW." BGE's expectation for the future indicates a value of approximately 750 MW in 2012, l i whrreas the ER reported a value of "about 1000 MW in 2016" (BGE 1998a). l BGE states that their conclusion remains unchanged in view of the update to their IRP and is further l r:inforced by diminishing long-term expectations for load management. The staff has reviewed the
> evailable information and concurs in this finding.
BGE (with the concurrence of the Maryland PSC) recently has eliminated nearly all of its ongoing l conservation programs. Maryland's restructuring legislation requires that the PSC review the need for l conservation programs according to certain criteria. The review will take place in consultation with the l j M:ryland Energy Administration (MEA). The outcome of such a PSC review cannot be predicted at this l timac The present outlook is that utility-sponsored conservation programs in the future will likely be l sm ller in scope than in the past. l l With reduced utility efforts and investment in conservation programs, it is unclear whether market forces l und:r a restructured envircnment will enhance or retard customer conservation efforts. However, to the l cxt::nt restructuring leads to lower retail rates, this will encourage greater demand for electricity (price l cl sticity effects), thereby undermining or offsetting the possibility that conservation programs could l substitute for or replace CCNPP (MDNR 1999b). l 1 NUREG-1437, Supplement 1 8-29 October 1999
Alt:mativ s to Lic nse Ransw:1 l 8.2.4.12 Fuel Cells -l l Phosphoric Acid Fuel Cells are the most mature fuel cell technology, but they are only in the initial l stages of commercialization. Two hundred tum-key plants have been installed in the United States, l Europe and Japan. Recent estimates suggest that a company would have to produce about 100 MW of l fuel cell stacks annually to achieve a price of $1000 to $1500 per kilowatt (DOE 1999). However, the l current production capacity of all fuel cell manufacturers only totals about 60 MW per year. Therefore, l the staff considers fuel cells not to be a feasible alternative to license renewal at this time. l l 8.2.4.13 Combination of Alternatives l l Even though individual altematives to CCNPP might not be sufficient on their own to replace CCNPP l due to the small size of the resource (hydro) or lack of cost-effective opportunities (e.g., for l conservation), it is conceivable that a mix of alternatives might be cost-effective. For example, if some l additional cost-effective conservation opportunities could be found and combined with a smaller l imported power or natural gas-fired attemative, it might be possible to reduce some of the key l environmental impacts of attematives. However, it is unlikely that the environmental impact of such a l hypotheticai r-ix could be reduced below SMALL (see Table 8-7). The impacts of renewing the CCNPP l licenses are SMALL on all dimensions. .I l 8.3 References l 40 CFR 50.9, " National primary and secondary ambient air quality standard for nitrogen dioxide." 40 CFR 50.10. " National 8-hour primary and secondary ambient air quality standards for ozone." 40 CFR 51.100, " Definitions." Baltimore Gas and Electric Company (BGE). 1989. Perryman Power Plant Certification of Public
. Convenience and Necessity, Environmental Review Document, Volume 2. Baltimore, Maryland.
l' Baltimore Gas and Electric (BGE). 1998a. Calvert Cliffs Nuclear Power Plant Units 1 and 2 License Renewal Application, Volume 3. Lusby, Maryland. ,j: Baltimore Gas and Electric (BGE).1998b. Letter from Mr. C.H. Cruse (BGE) to NRC Document .l Control Desk, " Response to Request for Additional information for the Review of the Calvert Cliffs l . Nuclear Power Plant Unit Nos.1 & 2, Environmental Report Associated with Licens~e Renewal, and l Errata (TAC Nos. MA1524 and MA1525)," November 20,1998, Lusby, Maryland. l l Baltimore Gas and Electric (BGE).1995. Integrated Resource Plan. Lusby, Maryland. I-
' October 1999 8-30 NUREG-1437, Supplement 1
i Alternatins to Licens3 Ren:wal Tcbis 8-7. Summary of Environmental Impacts of 500 MW(e) Demand-Side Measures, l Plus 1200 MW(e) Gas-Fired Generation (Once-Thr>> ugh Cooling) l l Calvert Cliffs Site Alternative "Greenfield" Site impact Category impact Comments impact Comments Ltnd Use SMALL . Additional 18 ha (45 acres) SMALL to 200 ha (500 acres) required for required for power block MODERATE site plus transmission line, l ;
. Additional 4 ha (10 acres) backup fuel tanks, pipeline '
disturbed for pipeline construction l
. Additionalland for backup oil storage l Ecology SMALL Constructed on previo ; sly disturbed SMALL to impact depends on location and land MODERATE threatened and endangered species l Witer Use and l Quility: l
- Surface Water SMALL ' >70 percent reduction in water flow SMALL to impact depends on receiving l MODERATE body of water l
- Groundwater SMALL Reduced groundwater withdrawals SMALL to Groundwater would be used for l due to reduced workforce MODERATE potable water only l Air Quality SMALL to Primarily nitrogen oxides SMALL to Same impacts as for CCNPP site I l
MODERATE MODERATE l l WIste SMALL Minor waste generation with gas (oil SMALL Same impacts as for CCNPP site l not evaluated) l Human Health SMALL Impacts considered to be minor SMALL Same irnpacts as for CCNPP site l (see discussion of gas-fired l 3 altemative) l Socioeconomics SMALL 250 to 400 additional workers SMALL to Construction impacts would be l during a 2- to 3-year construction MODERATE relocated. Community near l period; followed by a reduction in CCNPP would still experience l employment from 1550 persons at redaori' rom 1700 workers to 0. l CCNPP to 125 persons Othor community gains 125 l workers. l A;;sthetics SMALL to Visualimpact of stacks would be SMALL to Altemafe locations cc Jid reduce l MODERATE noticeable, but less so than for the MODERATE aesthetic impact if siting is in an l gas-fired attemative industrial area. l Archaeological and SMALL Only previously disturbed and SMALL Altemate location would l Historic Resources adjacent areas would likely be necessitate cultural resource l affected studies l Environmental SMALL to Impacts on minority and low-income SMALL to impacts vary depending on l Justice MODERATE should be similar to those MODERATE population distribution and l experienced by the population as a makeup l whole. Greater loss of revenues by l county,less construction impact. l l NUREG-1437, Supplement 1 8-31 October 1999
Altern:tives to License R::newil l Clean Air Act (CAA), as amended,42 USC,7401 et seg. Delmarva Power and Light Company.1992. Final Site Selection Study; 600 MW Coal-Fired Power Plant. Energy information Administration (EIA).1997. AnnualEnergy Outlook 1998, Table A2. DOE /EIA-0383(98), Washington, D.C. GilbertICommonwealth, Inc.1996. Update to Calvert Cliffs NuclearPower Plant Units 1 & 2 Cooling I Towr System Study. l Maryland Department of the Environment (MDE).1994. State Discharge Permit Number 92-D9-0187; Calvert Cliffs NuclearPowerPlant. Maryland Department of Natural Resources (MONR).1986. PowerPlant Cumulative Environmental Impact Report for Maryland, PPER-CEIR-5. Maryland Power Plant Siting Program, Annapolis, Maryland. Maryland Department of Natural Resources (MDNR).1996. Maryland Powerplants and the Environment: A Review of the Impacts of Power Plant and Transmission lines on Maryland's Natural Resources, Supporting Materials, PPRP-CEIR-9/2. Maryland Power Plant Research Program, Annapolis, Maryland.- l Maryland Department of Natural Resources (MDNR). 1999a. Maryland Power Plants and the Environment: A review of the impacts ofpowerplants and transmission lines on Maryland's natural resources, PRRP-CElR-10. Maryland Power Plant Research Program, Annapolis, Maryland. : ' l Maryland Department of Natural Resources (MDNR).1999b. Letter from Richard I. McLean, Manager, l . Nuclear Programs to Chief, Rules Review and Directives Branch, Division of Administrative Services, j ' ' Nuclear Regulatory Commission, May 19,1999. I South Carolina Electric and Gas Company.1991. Environmental Assessment for Cope Power Plant.
. U.S. Department of Energy (DOE).1995. Electric PowerAnnual. Energy Information Administration, Washington, D.C.
U.S. Department of Energy (DOE).1996. AnnualEnergy Outlook; 1996 with Projections to 2015, DOE /EIA-0383(96). Energy Information Administration, Washington, D.C. October 1999 8-32 NUREG-1437, Supplement 1 , I l
Alt;mitivas to License R:newal U.S. Department of Energy (DOE). 1999. Advanced Fuel Cell Systems - A Revolutionary Power l Technology, Fossil Energy-Fuel Cell Power Systems Overview. l l (http://www.fe. doe. gov / coal _ power /fc_ sum.html) (accessed August 4,1999). l ! U.S. Environmental Protection Agency (EPA).1993. AirPollutant Emission Factors, Volume 1: St:tionary Point and Area Sources, EPA, AP-42. Washington, D.C. : U.S. Environmental Protection Agency (EPA).1994. Fina/ Environmental /mpact Statement, Volume I: Tcmpa Electric Company- Polk Power Station, EPA 90419-94-002. Washington, D.C. U.S. Geological Survey (USGS).1987. Cove Point, Maryland, Scale 1:24000 (7.5-minute map). U.S. Nuclear Regulatory Commission (NRC).1988. Final Generic /mpact Statement on Decommissioning of Nuclear Facilities, NUREG-0586. Washington, D.C. U.S Nuclear Regulatory Commission (NRC).1996. Generic Environmentallmpact Statement for License Renewal of Nuclear Plants (GEIS), NUREG-1437 Washington, D.C. l I l i NUREG-1437, Supplement 1 8-33 October 1999 l
i l l l 9.0 Summary and Conclusions By I;tter dated April 8,1998, BGE submitted an application to the NRC to renew the CCNPP operating i licenses for Units 1 and 2 for an additional 20-year period (BGE 1998). If the operating licenses are rcnewed, continued operation of the plant will be at the discretion of BGE, State, and, where authorized, Federal (other than NRC) decisionmakers. If the operating licenses are not renewed, the plant will be shut down at or before the expiration of the current operating licenses for Unit 1 and Unit 2, which are l July 31,2014, and August 13,2016, respectively. l , i Under NEPA (42 USC 4321-4370d), an EIS is required for major Federal actions significantly affecting l j the quality of the human environment. The NRC has implemented Section 102 of NEPA in I 10 CFR Part 51. In 10 CFR 51.20(b)(2), the Commission requires preparation of an EIS or a supplement to an EIS for renewal of a reactor operating license; 10 CFR 51.95(c) states that the EIS pr;;pired at the operating license renewal stage will be a supplement to the Generic Environmental l Imp:ct Statement for License Renewal of Nuclear Plants (GEIS),(*) NUREG-1437 (NRC 1996,1999a). Upon acceptance of the BGE application, the NRC began the environmental review process described in 10 CFR Part 51 by publishing a notice of intent to prepare an environmental impact statement and ! conduct scoping (63 FR 31813). The staff visited the CCNPP site in July 1998 and held public scoping meetings on July 9,1998, in Solomons, Maryland (NRC 1998). The staff reviewed the GEIS and the i BGE ER, consulted with other agencies, and conducted an independent review of the issues following th3 guidance set forth in the draft Standard Review Plans for Envimnmental Reviews for Nuclear Power l PI:nts, Supplement 1: Operating License Renewal (NRC 1999b). l The staff then issued a draft of the SEIS for public comment on February 24,1999, which contained the l prcliminary results of its evaluation and recommendation. In addition, the staff held two public meetings j during the comment period for this report on April 6,1999. When the comment period ended on l 3 M:y 20,1999, the staff considered and dispositioned all of the comments received, as discussed in l Appendix A of this report. Modifications were made to this report to address certain comments, where l 4 rppropriate, as described in Appendix A. l This supplemental environmentalimpact statement (SEIS) presents the staff's analysis of the l environmentalimpacts of renewal of the CCNPP operating licenses. The analysis considers and w:ighs the environmental effects of the proposed action, the environmental impacts of attematives to the proposed action, and alternatives available for reducing or avoiding adverse impacts. It also includes the staff's final recommendation regarding the proposed action. l l (c) The GEIS was originally issued in 1996. Addendum 1 to the GEIS was issued in 1999. All f raferences to the "GEIS" include the GEIS and its Addendum 1. , NUREG-1437, Supplement i 9-1 October 1999
SummIry smd Conclusions-The Commission has set forth both the purpose and need for license renewal and the criterion to be used in evaluating the environmental effects of license renewal. The GEIS includes the following statement of purpose and need: The purpose and need for the proposed action (renewal of an operating license) is to provide an option that allows for power generation capability beyond the term of a current nuclear power plant operating license to meet future system generating needs, as such needs may be determined by State, utility, and, where authorized, Federal (other than NRC) decisionmakers. The criterion to be used in evaluating the environmental impacts, found in 10 CFR 51.95(c)(4) and in the GEIS,is as follows:
... whether or not the adverse environmental impacts of license renewal are so great that preserving the option of license renewal for energy planning decisionmakers would be unreasonable.
.] Both the statement of purpose and need and the evaluation criterion implicitly acknowledge that there l are factors, in addition to license renewal, that will ultimately determine whether an existing nuclear power plant continues to operate beyond the period of the current operating license. NRC regulations [10 CFR 51.95(c)(2)) contain the following statement regarding the content of SEISs - prepared at the license renewal stage: The supplemental environmental impact statement for license renewal is not required to include discussion of need for power or the economic costs and economic benefits of the proposed action or of attematives to the proposed action except insofar as such benefits and costs are either essential for a determination regarding the inclusion of an attemative in the range of attematives considered or relevant to mitigation. In addition, the supplemental environmental impact statement prepared at the license renewal stage need not discuss other issues not related to the environmental effects of the proposed action and the attematives, or any aspect of the storage of l- spent fuel for the facility within the scope of the generic determination in $51.23(a) [" Temporary l storage of spent fuel after cessation of reactor operations-generic determination of no significant l environmental impact") and in accordance with $51.23(b). In addition, the Commission has included detailed findings related to the Uranium Fuel Cycle and Waste .l Management in 10 CFR Part 51, Subpart A, Appendix B, Table B-1. The GEIS contains the results of a systematic evaluation of the consequences of renewing an operating l license and operating a nuclear power plant for an additional 20 years. It addresses 93 environmental issues using a three-level standard of significance-small, moderate, or large-based on Council on Environmental Quality guidelines. October 1999 9-2 NUREG-1437, Supplement 1
I l
)
Summary cnd Conclusions These significance levels are: l l SMALL: Environmental effects are not detectable or are so minor that they will neither destabilize nor noticeably alter any important attribute of the resource. MODERATE: Environmental effects are sufficient to alter noticeably, but not to destabilize important l
. attributes of the resource. l 1 ARGE: Environmental effects are clearly noticeable and are sufficient to destabilize important attributes of the resource.
For 69 of the 93 issues considered in the GEIS, the analysis in the GEIS has shown: l
- (1) the environmental impacts associated with the issue have been determined to apply either to all l plants or, for some issues, to plants having a specific type of cooling system or other plant or site characteristics l (2) a single significance level (i.e., smail, moderate, or large) has been assigned to the impacts (except l for collective offsite radiological impacts from the fuel cycle and from high-leve; waste and spent fuel disposal) l (3) mitigation of adverse impacts associated with the issue has been considered in the analysis, and it l his been determined that additional plant-specific mitigation measures are likely not to be sufficiently beneficial to warrant implementation.
These 69 issues were classified in the GEIS as Category 1 issues, in accordance with j to CFR 51.71(d), the staff relied on conclusions as amplified by supporting information in the GEIS for j issues designated Category 1 in 10 CFR Part 51, Subpart A, Appendix B, Table B-1 and, as described l below, considered whether there was any significant new information relevant to the proposed action on j these issues. l Of the 24 issues not meeting the criteria set forth above,22 were classif;sd as Category 2 issues r; quiring analysis in a plant-specific supplement to the GEIS. Environmental justice was not evaluated I on a generic basis and must also be addressed in a plant-specific supplement to the GEIS. The r:m:ining issue concerns the chronic effects of electromagnetic fields. Information on chronic effects of l ciectromagnetic fields was not conclusive at the time the GEIS was prepared. It is still not conclusive. This SEIS documents the staff's evaluation of all 93 environmentalissues considered in the GEIS and I one new issue (microorganisms that live in high radiation, high-temperature conditions) raised during l j the scoping process. As set forth in this SEIS, the staff considered the environmental impacts l cssociated with attematives to license renewal and compares the environmental impacts of license l NUREG-1437, Supplement 1 - 9-3 October 1999 l l l 1 l
Summ ry cnd Conclusions renewal and the altematives. The alternatives to license renewal that are considered include no-action (not renewing the CCNPP operating licenses) and attemative methods of power generation. Among the alternative methods of power generation, coal-fired and gas-fired generation appear the most likely if the power from CCNPP is replaced. These alternatives are evaluated assuming that the replacement power generation plants are located at either the CCNPP site or an unspecified "greenfield" site. 9.1 EnvironmentalImpacts of the Proposed Action-License Renewal l BGE and the staff have established independent processes for identifying and evaluating the significance of new information on the environmentalimpacts of license renewal. Neither BGE the staff l has identified any significant new information related to Category 1 issues that would call into question l the conclusions in the GEIS. Therefore, the staff relied upon the con::!usions of the GEIS for the 69 Category 1 issues. ; BGE's license renewal application presents analyses of the Category 2 issues. The staff has reviewed the BGE analysis for each issue and has conducted an independent review of each issue. Five Category 2 issues are not applicable to CCNPP because the issues are related to plant design features or site characteristics not found at CCNPP. Four additional Category 2 issues are not discussed in this SEIS because they are specifically related to refurbishment. BGE (1998) has stated that it "has not identified the need to undertake the major refurbishment activities that the GEIS assumed for license renewal, and no other modifications have been identified that would directly affect the environment or plant effluents." The remaining 13 Category 2 issues, as well as environmentaljustice and chronic effects of electromagnetic fields, are discussed in Chapters 3 through 7 of this SEIS. For allissues, the staff concludes that the potential environmental effects are of SMALL significance in the context of the GEIS. For SAMAs, the staff concludes that a reasonable, comprehensive effort was made to identify and l evaluate SAMAs. Although a limited number of cost-beneficial SAMAs were identified (four), these SAMAs do not relate to adequately managing the effects of aging during the period of extended l operation, and therefore, need not be implemented as part of license renewal. l In addition to considering the 93 issues listed in the GEIS, the staff considered a potentialissue l associated with microorganisms that live in high radiation, high temperature conditions. The staff concludes that this issue, while new, is not significant. Mitigation measures were considered for each Category 2 issue. In general, current measures to mitigate environmental impacts of plant operation were found to be adequate, and no additional l mitigation measures were deemed sufficiently beneficial to be warranted. October 1999 9-4 NUREG-1437, Supplernent 1
)
Sumra:ry and Conclusions The following subsections discuss unavoidable adverse impacts, irreversible or irretrievable l commitments of resources, and the relationship between local short-term use of the environment and l long-term productivity. l 9.1.1 Unavoidable Adverse impacts An cnvironmental review conducted at the license renewal stage differs from the review conducted at the construction permit stage because the plant is in existence at the license renewal stage and has opercted for a number of years. As a result, adverse impacts associated with the initial construction h'v3 been avoided, have been mitigated, or have occurred. The environmental impacts to be cviluated for license renewal are those associated with resarbishment and continued operation during the renewal term. Adv:rse impacts identified that are specific to CCNPP include the following: Assuming the current pumping rate, the additional drawdown of water at an offsite well during the r newal term attributable to CCNPP operation is estimated to be less than 2 m (5 ft).
. Continued operation of the CCNPP will result in continued loss of fish and shellfish due to cntrainment and impingement despite mitigative measures instituted since plant construction. l However, monitoring studies have demonstrated that impacts from these losses are small and are l not detectable or are so minor that they will neither destabilize nor noticeably alter any important l attribute of the resource. l
. The bounding estimate of an additional 60 employees at CCNPP may result in an increase cf up to l 4 percent in demand for housing and less than 1 percent in water demand and local traffic.
These adverse impacts are considered to be of SMALL significance, and none warrants implementation of additional mitigation measures. The adverse impacts of likely attematives in the event that CCNPP cerses operation at or before the expiration of the current operating licenses will not be smaller than those associated with continued operation of CCNPP, and they may be greater for some impact categories in some locations. 9.1.2 Irreversible or irretrievable Resource Commitments Th2 commitment of resources related to construction and operation of the CCNPP during its current licens] period was made when the plant was built. The resource commitments to be considered in this SEIS cre associated with continued operation of the plant for an additional 20 years. These resources
- include materials and equipment required for plant maintenance and operation, the nuclear fuel used by the re ctors, and ultimately, permanent offsite storage space for the spent fuel assemblies. l NUREG-1437, Supplernent 1 9-5 October 1999
I Summary cnd Conclusions , I l l I The most significant resource commitments related to operation during the renewal term are the fuel and the permanent storage space. The CCNPP requires approximately 88 fuel assemblies per year. Assuming no change in use rate, about 1760 spent fuel assemblies would be required for operation during a 20-year license renewal period. The likely power generation altematives in the event CCNPP ceases operation on or before the expiration of the current operating licenses will require commitment of resources for construction of the replacement plants as well as for fuel to run the plants. 9.1.3 Short-Term Use Versus Long-Term Productivity An initial balance between short-term use and long-term productivity of the environment at the CCNPP site was set when the plants were approved and construction began. That balance is now well established. Renewal of the CCNPP operating licenses and continued operation of the plants will not alter the existing balance, but it may postpone the availability of the site for other uses. Denial of the l application to renew the operating licenses will lead to shutdown of the plants and will alter the balance in a manner that depends on subsequent uses on the site. For example, the environmental consequences of tuming the CCNPP site into a park or an industrial facility are quite different. 9.2 Relative Significance of the EnvironmentalImpacts of License Renewal and the Alternatives The proposed action is renewal of the operating licenses for Calvert Cliffs Nuclear Power Plant Units 1 and 2. Chapter 2 describes the CCNPP and the environment in the vicinity of the plant. Chapters 4 l through 7 discuss environmental issues associated with renewal of the operating licenses. l Environmentalissues associated with the No-Action attemative and attematives involving power generation are discussed in Chapter 8. The significance of the environmentalimpacts from the proposed action (approval of the application for l renewal of the operating licenses), the No-Action altemative (denial of the application), and attematives involving coal- and gas-fired generation of power at the CCNPP site and a unspecified "greenfield site" are compared in Table 9-1. Continued use of the CCNPP once-through cooling system is assumed for Table 9-1. Substitution of a cooling tower for the once-through cooling system in the evaluation of the coal-fired and gas-fired generation altematives would result in somewhat greater environmentalimpacts in some impact categories. Table 9-1 shows that the significance of the environmental effects of the proposed action are SMALL for j all impact categories. The attemative actions, including the No-Action alternative, may have l environmental effects, in at least some impact categories, that reach MODERATE or LARGE significance. October 1999 9-6 NUREG-1437, Supplement 1 l
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Summ ry cnd Conclusions 9.3 Staff Conclusions and Recommendations Based on (1) the analysis and findings in the Genedc Environmentallmpact Statement forLicense Renewal of Nuclear Power Plants, NUREG-1437; (2) the ER submitted by BGE; (3) consultation with l l other Federal, State, and local agencies; (4) its own independent review; and (5) its consideration of j l public comments, the staff recommends that the Commission determine that the adverse environmental { impacts of license renewal for Calvert Cliffs Nuclear Power Plant Unit 1 and Unit 2 are not so great that l preserving the option of license renewal for energy planning decisionmakers would be unreasonable.
)
9.4 References 10 CFR Part 51," Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions." 10 CFR 51.20, " Criteria for and identification of licensing and regulatory actions requiring environmental impact statements." 10 CFR 51.23, " Temporary storage of spent fuel after cessation of reactor operation-generic determination of no significant environmentalimpact." 10 CFR 51.71, " Draft environmental impact statement-contents." 10 CFR 51.95, "Postconstruction environmental impact statements." l 10 CFR Part 51, Subpart A, Appendix B, Table B-1, " Environmental effect of renewing the operating l license of a nuclear power plant." l 10 CFR Part 54, " Requirements for renewal of operating license of a nuclear power plant." 63 FR 31813, "Notit ; of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process." June 10,1998. Baltimore Gas and Electric (BGE).1998. Applicant's EnvironmentalReport-Operating License Renewal Stage at Calvert Cliffs Nuclear Power Piant Units 1 and 2. Docket Nos. 50-317 and 50-318. Lusby, Maryland. National Environmental Policy Act of 1969, as arnended,42 USC 4321-4370d. l U.S. Fish and Wildlife Service (FWS).1998. Letter from John P. Wolflin, FWS to Barth W. Doroshuk, BGE. " Endangered and Threatened Species Calvert Cliffs License Renewal." November 3,1998. !
)
October 1999 9-8 NUREG-1437, Supplement 1
Summary and Conclusions U.S. Nuclear Regulatory Commission (NRC).1996. Generic Environmentallmpact Statement for Lic:nse Renewalof NuclearPlants (GEIS), NUREG-1437. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC).1998. Environmental /mpact Statement Scoping Process Summary Report, Calvert Cliffs NuclearPower Plant Lusby, Maryland. Washington, D.C. U.S. Nuclear Regulatory Commission (NRC). 1999a. Generic Environmental /mpact Statement for l Lic:nse Renewal of Nuclear Plants, Main Report, Section 6.3-Transportation, Table 9.1 Summary of l findings on NEPA issues forlicense renewal of nuclearpowerplants. NUREG-1437, Vol.1, Addendum l
- 1. Washington, D.C. l U.S. Nuclear Regulatory Commission (NRC). 1999b. Standard Review Plans for Environmental l R: views for Nuclear Power Plants Supplement 1: Operating License Renewal. NUREG-1555, Supplement 1. Washington, D.C.
NUREG-1437, Supplement 1 9-9 October 1999
l l 1 Appendix A Discussion of Comments on the Draft Supplement l 1 i Pursuant to 10 CFR Part 51, the staff transmitted the Generic EnvironmentalImpact Statement for l j Lic:nse Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power P! ant, Draft Report for Comment l (NUREG-1437, Supplement 1 (referred to as the Draft SEIS) to Federal, State, local govemment l egencies, and interested members of the public. As part of the process to solicit public comments on l the Draft SEIS, the staff: l 1
= placed a copy of the Draft SEIS into the NRC Public Document Room and the NRC Local Public j Document Room in Prince Frederick, Maryland; I l
- sent copies of the Draft SEIS to the applicant and certain Federal, State, and local agencies; I l
- published a notice of availability of the Draft SEIS in the Federal Register on March 5,1999 l (64 FR 10662); l 1
= issued public announcements, such as advertisements in local newspapers and postings in public !
_ places, of the availability of the Draft SEIS ; l l
= announced and held two public meetings in Solomons, Maryland on April 6,1999, to describe the l l results of the environmental review and answer related questions; l l = ' issued press releases announcing the issuance of the Draft SEIS, the pubSc meetings, and l instructions on how to comment on the Draft SEIS: and l l l = established a website to receive comments on the Draft SEIS thmugh the Intemet. l :
l During the comment period, the staff received a total of 17 comment letters and e-mail messages in l addition to the comments and written statements received during the public meetings. l l Tha staff has reviewed the public meeting transcripts and the 17 comment letters and e-mail messages l that are part of the docket file for the application, ejl of which are available in the NRC Public Document l Room. Excerpts of the transcripts that contained comments or questions are reproduced in this l cppendix along with the written statements submitted at the public meetings and each of the 17 l comment letters and e-mail messages. Triole A-1 lists (1) the speakers at the meetings in initial l speaking order along with the page of the transcript excerpts in this report on which the comment l NUREG-1437, Supplement 1 ' A-1 October 1999 L
Appendix A l appears, and (2) the authors of the comment letters or e-mail messages. The staff response for each l . Issue is provided in Section A.1 of this Appendix. Related issues have been grouped together. I l ' The staff addressed each comment by considering whether it was: l l (1) a comment about a Category 1 issue, and whether it - l l (a) provided significant new information that required evaluation during the review or 'l (b) provided no new information; I l (2) a comment about a Category 2 issue, and whether it l l (a) ' provided information that required evaluation during the review, or
- l. (b) provided no such information; I-l . (3) a comment that raised an environmental issue not addressed in the GEIS or the Draft SEIS; l . (4) a comment on safety issues pertaining to 10 CFR Part 54; or i
l (5) a comment outside the scope of license renewal (not related to 10 CFR Parts 51 or 54). l l There was no significant new information on Category 1 issues (1(a) above]. If the comment provided l new information for a Category 2 issue (2(a)], the staff evaluated the information and modified the SEIS, l as appropriate. If the comment provided no new information for either Category 1 or 2 issues [1(b) or l 2(b)], the GEIS and draft SEIS remained valid and bounding, and no further evaluation was performed. I l ' Comments without a supporting technical basis or that did not provide any new information are l addressed in this appendix, providing relevant references that address the issues within the regulatory l authority of the NRC, where appropriate. These references can be obtained from the NRC Public l Document Room. -l l Subsections A.1.1 through A.1.18 correspond generally to the subject matter in the text of the l supplement (purpose and scope, conclusions, site description, refurbishment, ecology, human health, l socioeconomics, archaeology and historic resources, postulated accidents, uranium fuel cycle and solid l waste management, decommissioning, attematives to the proposed action, and summary and .l conclusions). Within each section, similar comments are grouped together for ease of reference, and a l summary description of the comments is given, followed by the staff's response. Where the comment ' l ' or. question resulted in a change in the text of the draft report, the corresponding response refers the l ' reader to the appropriate section of this report where the change was made. All revisions to the text, l whether substantive (including those made in response to comments) or editorial, are designated by l vertical lines in the margin beside the text. .I
' October 1999 A-2 NUREG-1437, Supplement 1
Appendix A Section A.2 provides relevant portions of the public meeting transcripts, written statements submitted l during the public meetings, and the 17 e-mail messages and letters received in response to the Draft l SEIS. Each comment identified by the staff was assigned a specific alpha-numeric identifier (marker). l That identifier is typed in the margin of the transcript, written statement, e-mail message, or letter at the l beginning of the discussion of the comment. In addition, to assist the reader in finding the response to l tha comment, the section number (s) where the comment is addressed in Section A.1 of this report is l also listed in the margin next to the identifier. A cross-reference of the alpha-numeric identifier, the l speaker or author of the comment, the page of the report where this comment can be found, and the l s:ction(s) of this Appendix in which the comment is addressed is provided in Table A-1. l l Table A-1. Calvert Cliffs SEIS Comment Log Section(s) Speaker or Page of Where No. Author Source Comment Addressed A1 P. Gunter Aftemoon Meeting Transcript (4/6/99) A-47 A.1.3 l A2 P. Gunter Aftemoon Meeting Transcript (4/6/99) A-47 A.1.3 l A3 R. Mills Aftemoon Meeting Transcript (4/6/99) A-49 A.1.12 l A4 R. Mills Afternoon Meeting Transcript (4/6/99) A-49 A.1.12 l AS D. Lochbaum Aftemoon Meeting Transcript (4/6/99) A-50 A.1.3 l A6 D. Lochbaum Afternoon Meeting Transcript (4/6/99) A-50 A.1.3 l l l A7 D. Lochbaum Aftemoon Meeting Transcript (4/6/99) A-51 A.1.3 l A8 D. Lochbaum Aftemoon Meeting Transcript (4/6/99) A-51 A.1.3 l A9 K. Dellinger Aftemoon Meeting Transcript (4/6/99) A-52 A.1.3 l A10 B. Doroshuk Afternoon Meeting Transcript (4/6/99) A-53 A.1.4 l A11 D. Lochbaum Aftemoon Meeting Transcript (4/6/99) A-53 A.1.7 l A12 R. Mills Aftemoon Meeting Transcript (4/6/99) A-54 A.1.10 j l A13 R. Mills Afternoon Meeting Transcript (4/6/99) A-54 A.1.10 l A14 R. Mills Aftemoon Meeting Transcript (4/6/99) A-55 A.1.10 l l A15 D. Lochbaum Afternoon Meeting Transcript (4/6/99) A-55 A.1.6 l A16 D. Lochbaum Aftemoon Meeting Transcript (4/6/99) A-55 A.1.3, A.1.6 l A17 P. Gunter. Aftemoon Meeting Transcript (4/6/99) A-56 A.1.3 l NUREG-1437, Supplement 1 A-3 October 1999
Appendix A Table A-1. Calvert Cliffs SEIS Comment Log Section(s) , Speaker or Page of Where I No. Author Source Comment Addressed l l l A18 Dr. J. Mihursky Afternoon Meeting Transcript (4/6/99) A-60 A.1.2 l A19 Dr. J. Mihursky Aftemoon Meeting Transcript (4/6/99) A-60 A.1.13 l A20 Dr. J. Mihursky Aftemoon Meeting Transcript (4/6/99) A-60 A.1.14 l A21 Dr. J. Mihursky Aftemoon Meeting Transcript (4/6/99) A-60 A.1.5 l A22 Dr. J. Mihursky Aftemoon Meeting Transcript (4/6/99) A-60 A.1.11 l A23 Dr. J. Mihursky Aftemoon Meeting Transcript (4/6/99) A-61 A.1.12 l A24 J. Riccio Aftemoon Meeting Transcript (4/6/99) A-61 A.1.6 l A25 G. Abbe Aftemoon Meeting Transcript (4/6/99) A-62 A.1.5 l A26 J. Riccio Aftemoon Meeting Transcript (4/6/99) A-64 A.1.3 l A27 J. Riccio Afternoon Meeting Transcript (4/6/99) A-64 A.1.10 l A28 J. Riccio Afternoon Meeting Transcript (4/6/99) A-65 A.1.10
! A29 D. Hale Aftemoon Meeting Transcript (4/6/99) A-65 A.1.1 l A30 D. Hale Afternoon Meeting Transcript (4/6/99) A-66 A.1.1 l A31 Dr. D. Rogers Afternoon Meeting Transcript (4/6/99) A-67 A.1.6 l A32 Dr. D. Rogers Afternoon Meeting Transcript (4/6/99) A-68 A.1.6 l A33 R. Mogel Aftemoon Meeting Transcript (4/6/99) A-69 A.1.1
-l A34 G. Clark Aftemoon Meeting Transcript (4/6/99) A-69 A.1.1 l A35 A. Howard Aftemoon Meeting Transcnpt (4/6/99) A-70 A.1.1 l A36 T. Allhoff Aftemoon Meeting Transcript (4/6/99) A-72 A.1.1 l A37 T. Rockwell Aftemoon Meeting Transcript (4/6/99) A-74 A.1.6 l A38 D. Graf Aftemoon Meeting Transcript (4/6/99) A-75 A.1.1 l A39 C. McHugh Aftemoon Meeting Transcript (4/6/99) A-77 A.1.1 l A40 J. Riccio Aftemoon Meeting Transcript (4/6/99) A-78 A.1 3 l A41 J. Riccio Aftemoon Meeting Transcript (4/6/99) A-78 A.1.10 October 1999 A-4 NUREG-1437, Supplement 1
l Appendix A l Table A-1. Calvert Cliffs SEIS Comment Log i Section(s) j Speaker or Pago of Where i No. Author Source Comment Addressed i l A42 J. Riccio Afternoon Meeting Transcript (4/6/99) A-78 A.1.10 l A43 J. Riccio Afternoon Meeting Transcript (4/6/99) A-79 A.1.10 l ! A44 D. Jenkins An* noon Meeting Transcript (4/6/99) A-80 A.1.1 l l A45 P. Gunter Aftemoon Meeting Transcript (4/6/99) A-81 A.1.13 l A46 P. Gunter Aftemoon Meeting Transcript (4/6/99) A-81 A.1.3, l A.1.13 l ) 1 A47 P. Gunter Aftemoon Meeting Transcript (4/6/99) A-82 A.1.5 l l A48 P. Gunter Aftemoon Meeting Transcript (4/6/99) A-82 A.1.6 l A49 C. Reynolds Aftemoon Meeting Transcript (4/6/99) A-83 A.1.1 l A50 R. Mills Aftemoon Meeting Transcript (4/6/99) A-84 A.1.2, l A.1.10 l A51 R. Mille, Aftemoon Meeting Transcript (4/6/99) A-85 A.1.10 l A52 R. Mills Aftemoon Meeting Transcript (4/6/99) A-85 A.1.12 l
.A53 R. Mills Aftemoon Meeting Transcript (4/6/99) A-86 A.1.11 l A54 K. Dellinger Aftemoon Meeting Transcript (4/6/99) A-87 A.1.2 l A55 K. Dellinger Aftemoon Meeting Transcript (4/6/99) A-87 A.1.2, A.1.9 l A56 K. Dellinger Aftemoon Meeting Transcript (4/6/99) A-87 A.1.2 l A57 K. Dellinger Aftemoon Meeting Transcript (4/6/99) A-87 A.1.2, A.1.3 l A58 B. Doroshuk Afternoon Meeting Transcript (4/6/99) A-89 A.1.3 l A59 B. Doroshuk Aftemoon Meeting Transcript (4/6/99) A-91 A.1.15 l AGO. L. Kelly Evening Meeting Transcript (4/6/99) A-93 A.1.1 l A61 L. Kelly Evening Meeting Transcript (4/6/99) A-94 A.1.1 l A62 G.Klein Evening Meeting Transcript (4/6/99) A-95 A.1.1 l A63 D. Jenkins Evening Meeting Transcript (4/6/99) A-96 A.1.1 l AS4 A. Howard Evening Meeting Transcript (4/6/99) A-97 A.1.1 l NUREG-1437, Supplement 1 A-5 October 1999 I
Appendix A Table A-1. Calvert Cliffs SEIS Comment Log Section(s) Speaker or Page of Where No. Author Source Comment Addressed l A65 Mr. Tenore Evening Meeting Transcript (4/6/99) A-97 A.1.1 l A66 B. Doroshek Evening Meeting Transcript (4/6/99) A-98 A.1.1 l 81 Dr. J. Mihursky Written Statement Submitted at Public A-101 A.1.2 l Meetings (4/6/99)
.l B2 Dr. J. Mihursky Written Statement Submitted at Public A-101 A.1.13 l Meetings (4/6/99)
{ B3 Dr. J. Mihursky Written Statement Submitted at Public A-101 A.1.14 l Meetings (4/6/99) l B4 Dr. J. Mihursky Written Statement Submitted at Public A-101 A.1.5 l Meetings (4/6/99) l ,B5 Dr. J. Mihursky Written Statement Submitted at Public A-102 A.1.11 l Meetings (4/6/99) l B6 Dr. J. Mihursky Written Statement Submitted at Public A-102 A.1.12 l Meetings (4/6/99) l B7 ANS Position Statement Written Statement Submitted at Public A-103 A.1.1 l on Nuclear Power: The Meetings (4/6/99) l Leading Strategy for l Reducing Carbon l Emissions l 88 A. Howard Written Statement Submitted at Public A-111 A.1.1 l Meetings (4/6/99) l B9 A. Howard Written Statement Submitted at Public A-111 A.1.1 l Meetings (4/6/99) l B10 A. Howard Written Statement Submitted at Public A-111 A.1.1 l Meetings (4/6/99) l B11 B. Doroshuk Written Statement Submitted at Public A-114 A.1.3 l Meetings (4/6/99) j l 812 B. Doroshuk Written Statement Submitted at Public A-115 A.1.15 l Meetings (4/6/99) l C G. R. Mazetis March 2,1999 Letter A-122 A.1.11 i October 1999 A-6 NUREG-1437, Supplement 1 4
Appendix A Table A-1. Calvert Cliffs SEIS Comment Log Section(s) Speaker or Page of Where N 2. Author Source Comment Addressed D G. Abbe February 25,1999 E-mail Message A-123 A.1.18 l E1 S. W. Samuels March 8,1999 E-mail Message A-124 A.1.15 l E2~ S. W. Samuels March 8,1999 E-mail Message A-124 A.1.13 l E3 S. W. Samuels March 8,1999 E-mail Message A-124 A.1.10 l E4 S. W. Samuels . March 8,1999 E-mail Message A-124 A.1.9 l F T. S. Smith March 18,1999 Letter A-124 A.1.11 l G- S.W. Samuels April 2,1999 E-mail Message A-126 A.1.15 l H L. R. Romo April 9,1999 E-mail Message A-127 A.1.2 l l B. Larcom April 10,1999 E-mail Message A-127 A.1.2 l J J. Bryne April 12,1999 E-mail Message A-128 A.1.2 l K1 D. Lochbaum April 12,1999 Letter - A-128 A.1.3 l K2 D. Lochbaum April 12,1999 Letter A-129 A.1.3, A.1.6 l L1 R. Mills May 4,1999 Letter A-130 A.1.3 l i L2 R. Mills May 4,1999 Letter A-130 A.1.10 l L3 R. Mills May 4,1999 Letter A-130 A.1.15 l L4 R. Mills May 4,1999 Letter A-130 A.1.3 l L5 R. Mills May 4,1999 Letter A-131 A.1.6 l L6 R. Mills May 4,1999 Letter A-131 A.1.12 l L7 R. Mills May 4,1999 Letter A-131 A.1.12 l L8 R. Mills May 4,1999 Letter A-131 A.1.11, l A.1.12 l L9 R. Mills May 4,1999 Letter A-131 A.1.12 l j L10 R. Mills May 4,1999 Letter A-132 A.1.12 l M ' J. R. Lemon for April 27,1999 Letter A-132 A.1.16 l C. H. Cruse l NUREG-1437, Supplement 1 A-7 October 1999
Appendix A 4 Table A-1. Calvert Cliffs SEIS Comment Log Section(s) Speaker or Page of Where No. Author Source Comment Addressed l N J. S. Stahl May 11,1999 E-mail Message A-133 A.1.16 l O K. R. McAllister May 8,1999 Letter A-133 A.1.1 l P A. B. Brownstein May 18,1999 Letter A-134 A.1.16 l Q1 R. I. McLean May 19,1999 Letter A-136 A.1.5 l Q2 R. l. McLean May 19,1999 Letter A-136 A.1.6 l Q3 R. l. McLean May 19,1999 Letter A-136 A.1.15 l O'4 R.1. McLean May 19,1999 Letter A-137 A.1.18 l R C. H. Cruse May 19,1999 Letter A-139 A.1.4, l A.1.8, l A.1.16, l A.1.17, j A.1.18 l Table A-2 l S1 R. l. McLean May 20,1999 Letter A-149 A.1.5 l S2 R. l. McLean May 20,1999 Letter A-149 A.1.5 l T L. S. Bradshaw June 25,1999 Letter A-149 A.1.16 l l l .l A.1 Comments and Responses -l l A.1.1 General Comments in Support of License Renewal l l The record of the public meetings and comment letters contains 22 comments that express general l support for CCNPP license renewal (A29, A30, A33, A34, A35, A36, A38, A39, A44, A49, A60, A61, l A62, A63, A64, A65, A66, B7,88, B9, B10,0). Common reasons for supporting license renewal l included: I . . l
- BGE's environmental stewardship (A33, A36, A61, A63,87); j j.* economic benefits to the community and hardship if shut down (A30, A39, A49, A63, B9); ;
l
- social benefit to the community through the activities of CCNPP employees (A30, A44, A49, A60);
l
- air quality (A35, A38, A61, A64, 87, B8,0); and l
- high replacement costs (B10).
October 190' A-8 NUREG-1437, Supplement 1
Appendix A I Th;se comments are generalin nature and do not provide new information. Therefore, no further l cviluation was required, and no changes to the SEIS were made as a result of these comments. l 1 A.1.2 General Commants in Opposition to License Renewal l 1 The record includes ten comments that express general opposition to nuclear power and license l r;newal (A18, A50, AS4, A55, A56, A57, B1, H, I, J). Reasons for opposing license renewal include l l = unacceptably high risk of accidents (A18, A50, A56, B1, I, J); l
- availability of more benign power generation attematives (A18, A56, B1, H); l
- nuclear waste (AS4, A57 H); and l
= health concems (A55, A56). l l These comments are general in nature, and do not provide new information. Therefore, no further l cv;luation was required, and no changes to the SEIS were made as a result of these comments. l l A.1.3 License Renewal Review Process l l The record contains 18 comments and questions related to the license renewal process (A1, A2, AS, l A6, A7, A8, A9, A16, A17, A26, A40, A46, A57, A58, B11, K1, K2, L1, L4). Two comments (A58, B11) l describe the open nature of the review process. The other comments take issue with various aspects l of the review process. Common themes in the adverse comments and questions related to the license l r;newal process include l l . limitations on public input (A6, A7, A8); l
- changes in the process (A2, A17, A26, A40); l
- limitations on scope (A16, A46, K2, L4); l e adequacy of the BGE application (A5, L1); l
- lack of objectivity of the staff evaluation (K1); and l
- other(A9, A57). l l
Th3 adequacy of the license renewal review process is not within the scope of the environmental review l r;lited to CCNPP license renewal. It was established by rulemaking that included public notice and l comment. Any new challenge to the process is outside the scope of this plant-specific environmental l revi;w. l l The specific adverse comments are addressed below. l I Comment: l l Three of the adverse comments (A6, A7, A8) deal with limitations on public input. Two of the l comments (A6, A7) suggest that one opportunity for public hearing has been dropped from the l process, and the third comment (A8) states that the public only has 30 days to review a document I that the NRC estimates will take 22 man-years to review. l l NUREG-1437, Supplement 1 A-9 October 1990
Appendix A l Response: l l The license renewal process involves separate environmental and safety reviews, which together l account for the 22 Full-Time Equivalents (FTEs) estimated for the NRC review. This SEIS is part l of the environmental review. Environmental reviews are conducted at various stages of plant l construction and operation. The staff conducted an environmental review for CCNPP at the l operating license stage, during which the draft environmental statement was available for l comment. This environmental review is being conducted at the license renewal stage. In the l review process for license renewal, the public had opportunities to participate in the scoping l process and in review of the draft SEIS. ; I l The public had access to the license renewal application shortly after it was docketed. A 60-day , l scoping period during which comments were solicited began approximately one month after the I l application was docketed, and a scoping meeting for the CCNPP environmental review occurred l about one month later. The draft SEIS was published approximately nine months after docketing, l after which a 75-day opportunity for comment was provided. l l These comments did not result in modification of the SEIS text. l l Comment: l l There were three comments or questions (A1, A2, A17) related to changes in the environmental l review process. These concerned the status and background behind the change in classification l of high-level waste transportation from a Category 2 issue to a Category 1 issue. There were two l other comments (A26, A40) that asserted that there was an earlier application for license renewal l that caused the NRC to change the license renewal process to ensure renewal of the license. l l Response: l l The NRC addressed the questions concerning the status and background behind the change in l classification of high-level waste transportation from a Category 2 issue to a Category 1 issue at l the April 6,1999, public meeting. The staff indicated that the proposed rule was an NRC initiative. l The draft SEIS addressed this issue in Section 6.1.1, " Transportation of Radiological Waste," l because the rule had not been finalized. Now that the rule has been amended, as discussed l below, the issue is a Category 1 issue. Section 6.1 of this report now reflects this reclassification. l l The Commission revised its environmental protection regulations (10 CFR Part 51) for license l renewal on December 18,1996 (61 FR 66537). The amendment was based on the analyses and l conclusions reported in NUREG-1437, " Generic Environmental Impact Statement for License l Renewal of Nuclear Plants"(GEIS)(May 1996). in response to the comments received on a l version of the rule published on June 5,1996 (61 FR 28467), the Commission made the following l statement: l l As part of its effort to develop regulatory guidance for this rule, the Commission will l consider whether further changes to the rule are desirable to generically address: (1) l the issue of cumulative transportation impacts and (2) the implications that the use of October 1999 A-10 NUREG-1437, Supplement i
Appendix A higher bumup fuel have for the conclusions in Table S-4. After consideration of these j issues, the Commission will determine whether the issue of transportation impacts l should be changed to a Category 1. l I in SECY-97-279, entitled " Generic and Cumulative Environmental Impacts of Transportation of l High-Level Waste (HLW) in the Vicinity of a HLW Repository," dated Decemoer 3,1997, the NRC l staf' informed the Commission that it was the staff's preliminary view that the supplemental l cnalyses of the generic and cumulative impacts of the transportation of HLW and of the l implications of higher fuel burnup for transportation impacts supports a reasonable technical and l legal determination that transportation of HLW is a Category 1 issue and may be generically l r; solved and adopted in a license renewal application. In a Staff Requ;rements Memorandum l (SRM) dated January 13,1998, the Commission directed the NRC staff to proceed with rulemaking l . to amend 10 CFR 51.53(c)(3)(ii)(M) to categorize the impacts of transportation of HLW as a l l Category 1 issue. In a memorandum dated July 1,1998, the NRC staff informed the Commission l of its plans for amending 10 CFR Part 51. l l The Commission published the proposed rule for a 60-day public comment period on February 26, l 1999 (64 FR 9884). The Commission also published a notice of availability of NUREG-1437, l Vol.1, Addendum 1, " Generic Environmental Impact Statement for License Renewal of Nuclear l Power Plants: Main Report Section 6.3 ' Transportation,' Table 9.1 ' Summary of findings on l NEPA issues for license renewal of nuclear power plants,' Draft for Comment," (February 1999) l (64 FR 9889) (Addendum 1 to the GEIS). Although the public comment period for the proposed l rule and the draft Addendum to the GEIS ended on April 27,1999, in response to concems l cxpressed by stakeholders about the length of the comment period, in developing the final rule and l final version of Addendum 1 to the GEIS, the staff considered comments dated as late as June 25, l 1999, and received in early July 1999. l l In the SRM to SECY-99-202, " Final Rule - Changes to Requirements for Environmental Review for l l Renewal of Nuclear Power Plant Operating Licenses (10 CFR Part 51)," dated August 3,1999, the l Commission approved issuance of the final rule and release of the supporting Addendum 1 to the l l GEIS. The Commission revised the environmental protection regulations on September 3,1999, l (64 FR 48496) and the rule became effective on October 4,1999. The notice of filing of the Final l Addandum 1 to the GEIS was published on September 17,1999 (64 FR 50507). l l CCNPP is the first U.S. nuclear power plant to undergo the NRC license renewal process under l j NRC's 10 CFR Part 51, " Environmental Protection Regulations for Domestic Licensing and Related l Regulatory Functions," with regard to the renewal of nuclear power plant operating licenses. The j licensee of Yankee Rowe considered applying for renewal of its operating license but discovered ] significant safety problems in the initial phases of its investigation and terminated the action. The l Yankee Rowe decision has not affected the license renewal process. l l These comments did not result in modification of the SEIS text. However, the text of the SEIS has l been changd to be consistent with the final rule. l , l NUREG-1437, Supplement 1 A-11 October 1999
Appendix A l Co.nment: l l There were four adverse comments (A16, A46, K2, L4) related to limitations placed on the scope of l the environmental review. All of these comments contain explicit or implicit objections to reliance l upon the GEIS determination for Category 1 issues in the absence of significant new information, ; j and two comments (A46, L4) specifically mention high-level waste issues, which are Category 1 I l issues. I l Response: l l . l l The environmental review process, which is set forth in 10 CFR Part 51, implements the National l Environmental Policy Act of 1969 (NEPA). It provides for public notice, public input on the scope of l the review, and public comment on the environmental analysis. In 10 CFR 51.95(c)(4), the l Commission states that the NRC staff, adjudicatory officers, and the Commission shallintegrate l the conclusions regarding the environmental acceptability ohhe licenso renewal action, as l amplified by the supporting information in the GEIS for issues designated as Category 1 (with l certain exceptions) or resolved as Category 2, information developed for those open Category 2 l issues applicable to the plant in accordance with 10 CFR 51.53(c)(3)(ii), and any significant new l information. Accordingly, it should not be necessary to review a Category 1 issue in the context of l an individual application unless there is significant new information on the issue. l l The environmental review process provides for the preparation of generic environmentalimpact l statements to avoid the time and expense of repeated reviews of essentially the same material. l Wher. an environmentalissue has been resolved generically, there is no need to conduct another l detailed review of the sarne issue with respect to a particular application unless there is s,ignificant l new information related to some aspect of the issue. The GEIS addresses and draws generic l l conclusions on 69 environmentalissues associated with license renewal. These are the Category 1 issues. l l l BGE's review of Category 1 issues (listed in 10 CFR Part 51, Subpart A, Appendix B, Table B-1) is l limited to the search for and evaluation of significant new information. If the staff finds significant l new information regarding a specific Category 1 issue, reconsideration of the conclusions on that l issue is limited in scope to assessment of the relevant new and significant information. The scope l of the assessment does not include review of other facets of the issue that are not affected by the l new information. l l Both the BGE staff and the NRC staff implemented processes for reviewing information related to l the issues generically dispositioned in the GEIS and did not Ond any significant new information l with respect to any Category 1 issue. In addition, there was no sinnificant new information l received during the comment period from members of the public. Consequently, in this document, l which is a supplement to the GEIS, the staff relies on the analysis and conclusions in the GEIS for l thor,e issues. l l This document also addresses those issues that require plant-specific evaluation. It includes more l detailed information on issues that required plant-specific evaluation, such as the effects of CCNPP October 1999 A-12 NUREG-1437, Supplement 1 i
Appendix A operation on the aquatic environment, rather than on issues for which a gener,c determination was l made in the GEIS, such as the effects of operation on human health. l l These comments did not result in modification of the SEIS text. I I Comment: l l I Two comments (AS, L1) contain assertions that the BGF, application was incomplete and l inaccurate. One of these comments (A5) cited supplements to the application as an indication that l
&n incomplete and inaccurate report was submitted by BGE. The other comment (L1) asserts that l the BGE application fails to justify the need for power 15 years from now. l )
l ! Response: l j l l The BGE application was reviewed upon receipt by the NRC staff. The staff determined that the l l application was complete and acceptable for docketing purposes. Since the initial review of the l I application, the staff has continued the review, conducted a site visit, and held public meetings with l BGE on various subjects covered in the application. As a result of these additionalinteractions, the j staff ioentified areas where additional information was needed for its review. Appendix C lists the l ! correspondence in which NRC has requested and BGE has provided this additional information. l ! The staff's requests for additional or clarifying information does not imply that the application was l incomplete when docketed. Rather, the requests for additional information reflect the normal l interchange that occurs whenever a large and complex evaluation is submitted for review. l l In accordance with 10 CFR 51.95(c)(2), neither BGE or the NRC is required to evaluate the need l for power in connection with the environmer,ta! review associated with license renewal. The l Commission has set forth the need for the proposed NRC action in the GEIS. It is: l l The purpose and need for the proposed action (renewal of an operating license) is to provide an l option that allows for power generation capability beyond the term of a current nuclear power l plant operating license to meet future system generating needs, as such needs may be j determined by State, utility, and, where authorized, Federal (other than NRC) decisionmakers. l l These comments did not result in modification of the SEIS text. l l Comment: l l The record contains two additional comments related to the licensing process (A9, A57). One of l these comments (A9) contained a question related to petitioning to close CCNPP, and the other l (A57) contained a request to NRC to immediately develop a process to deny license extensions to l nuclear power plants. l l Rxponse: l l NRC regulations [in 10 CFR 2.206(a)) provide: "Any person may file a request to institute a l proceeding pursuant to S 2.202 to modify, suspend, or revoke a license, or for other such action as l NUREG-1437, Supplement 1 A-13 October 1999 l l
Appendix A l- may be proper." The regulations continue, stating that "[t]he requests shall specify the action l requested and set forth the facts that constitute the basis for the request." The license for CCNPP l is subject to the provisions of 10 CFR 2.206 I l The NRC staff considers license renewal applications under 10 CFR Parts 51 and 54. The l outcome of the NRC's review is not pre-detamined. An applicant must comply with the NRC's l regulations; otherwise the application will be denied. The processes in 10 CFR Parts 2,51, and 54 } l provide for both granting and denying applications to renew licenses for nuclear power reactors. I l These comments did not result in modification of the SEIS text. l l Comment: l l One comment (K1) asserts that the draft SEIS appears to be unfairly biased, stating that the staff's l acceptance of the Commission's Waste Confidence' Rule [10 CFR 51.23(a)] demonstrates a j willingness to accept uncertain and unproven technology on the one hand, while failing to accept l energy technologies represented by renewable energy sources as a viable replacement of the l power produced by CCNPP on the other. l l Response: I l The Commission has established a process separate from the license renewal review process for l addressing the issue of a high-level waste repository for storing spent fuel generated by reactors in j the United States. During the promulgation of 10 CFR 51.23 (the Waste Confidence Rule) in 1990, l the Commission stated that it would review its Waste Confidence Rule every 10 years (rather than l every five years as provided in the 1984 rulemaking)(55 FR 38475). Challenges or comments on l the rule will be considered when the Commission reconsiders its Waste Confidence Rule. l l During the promulgation of 10 CFR 51.23, the Commission considered the technical feasibility of l constructing and operating a high-level waste repository. The rulemaking also included the l opportunity for public comment. The basis for the Waste Confidence Rule, incruding the periodic l reconsideration by the Commission, can be found in the rulemaking records [55 FR 38474 l (September 18,1990) and 49 FR 34694 (August 31,1984)). I l In the context of an environmental review, the staff considers the energy source attematives l available at the time it is evaluating the application to renew the license. The staff assesses j technically feasible attematives and discloses their environmental impact. Because facilities that l use renewable energy sources are currently limited to small capacities, the staff does not consider l them capable of replacing large baseload units, such as CCNPP, at this time. Ilowever, that l determination does not preclude such renewable energy sources from being used to replace l CCNPP in the future. The staff has made no determination that renewable energy sources cannot l be viable replacement options for large baseload units in the future, nor is it presuming that l renewable technologies will not be available in the future. The decision to continue CCNPP l operation or replace that power source with other economically and environmentally viaole l technologies is not within the purview of the NRC, and is left to Stato, utility, and, where authorized, l Federal (other than the NRC) decisionmakers. October 1999 A-14 NUREG-1437, Supplement 1
! 1 Appendix A l The Waste Confidence Ru!e is supported by the above cited rulemaking records. In contrast, the l use of renewable energy sources as a replacement energy source for CCNPP at this stage of l development is not supported by a similar body of information (nor does the comment provide such l information). Accordingly, these matters have been considered given the information available at I this time. l l This comment did not result in modification of the SEIS text. l l A.1.4 Refurbishment l 1 The record contains two comments related to refurbishment made by BGE (A10, R79). The first l comment (A10), made by BGE during the public meeting on the aftemoon of April 6,1999 stated that l thera would be no refurbishment that would affect anything outside the perimeter of the power plant. l The second comment (R79) contained in the May 19,1999, letter from BGE reaffirmed its position l stated in the ER that BGE 'has not identified the need to undertake the major refurbishment activities f that the GEIS assumed for license renewal, and no other modifications have been identified that would l l l dir:ctly affect the environment or plant effluents." l l These comments provide clarification of BGE's position on refurbishment. They do not change j information that BGE provided in the application. However, the staff revised Section 2.1.6 and 2.2 of l this report for clarity. l l A.1.5 Ecology l l The record contains seven comments related to ecology (A21, A25, A47, B4, Q1, S1, S2). One l comment (A25) describes studies on fish and shellfish in the Bay, and two comments (Q1, S1) provided l cduitional information on fisheries valuation, special species status, and critical habitats. New l information on fisheries valuation, special species status, and critical habitats included in these l comments has been incorporated in Chapters 2 and 4. Additional species of concern were included in l S:ction 2.2.6, and Section 4.1.2 was expanded to include the new fisheries valuation data. This l cdditionalinformation did not affect the conclusions of the staff. l l Specific comments are addressed below. I l Comment: l l One comment (S2) co.1cemed consultations with the Maryland Department of Natural Resources l (MDNR). The MDNR noted that the forested area on the project contains potential Chesapeake l Bay Critical Area Forest Interior Dwelling Bird Habitat and that consultation with MDNR is required. l l Rh ance: l l BGE's letter to the MDNR dated August 17,1999, documents BGE's consultations with MDNR l regarding potentialimpacts to the Chesapeake Bay Critical Area Forest interior Dwelling Bird l Habitat associated with renewal of the CCNPP operating licenses. BGE stated that, as outlined in l the ER accompanying the CCNPP license renewal application, the anticipated activities of the l NUREG-1437, Supplement 1 A-15 October 1999 l
Appendix A l proposed action (license renewal of CCNPP) would take place within existing structures and l facilities. No additional land disturbances or structural modifications are expected for the purpose l of supporting license renewal. Therefore, BGE expects that operation of the plant through the l' license renewal period (an estimated 20 years) would not impact the Critical Area or potential l interior forest dwelling bird habitat located within site boundaries. l l This comment did not result in modification of the SEIS text. l l Comment: l l Three comments (A21, A47, B4) included questions about the effects of radiological releases to the l environment. Two of the comments (A21, B4) question whether the biological effects of batch l releases of tritium to the Chesapeake Bay have been considered in the SEIS. The other comment l (A47) states that CCNPP has released about 150,000 Ci to the environment, and asks the NRC to l produce studies that show safe [ radiation) thresholds and include tnem in the GEIS. l l Response: ' I l Any releases of tritium to the environment are monitored and eva'aated through the CCNPP l Radiological Environmental Monitoring Program. The staff reviewed the CCNPP Annual Reports { for the last five years and found the levels of releases of all radionuclides (including tritium) l remained within NRC release limits. NRC limits are set to ensure protection of human health, ' l which, based on extensive data, is assumed to be protective of all other biological receptors l (animals and plants). Effects of radiation exposure on human health from all environmental l releases have been extensively evaluated in the GEIS and have been classified as a Category 1 l issue with no significant impact. Operational monitoring data have shown all emissions are well l below those that could cause health effects on humans. See Section A.1.6 of this report for further l discussions of the effects of radiation exposure on human health. l l These comments did not result in modification of the SEIS text. l l A.1.6 Human Health l l There are ten comments in the record related to human health (A15, A16, A24, A31, A32, A37, A48, K2, l LS, Q2). The staff's responses to these comments follow. I l Comment: l l Three of the comments (A31, A32, A37) take the position that the health effects of low-level l radiation have not been shown to be adverse. The results of studies of cancer incidence in the l vicinity of the nuclear facilities are cited in comments A31 and A32. The National Cancer institute l study cited in comment A31 compared cancer before and after startup in the vicinity of 62 nuclear l facilities and did not find higher risks of leukemia and other cancer after reactor startup. The study l cited in comment A32 was more specific to the CCNPP area. Incidences of cancer near the plant l were no greater than in the State, as a whole. Comment Q2 agrees with the staff position that October 1999 A-16 NUREG-1437, Supplement 1
p Appendix A cvidence related to health effects of chronic exposure to extremely low frequency-electromagnetic l radiation is inconclusive at this time. l l Response: l 1 None of these comments required modification of the SEIS. However, Section 4.2.2 on the chronic l l effects of electromagnetic fields has been modified to include the findings of a recent National l Institute of Environmental Health Sciences report that characterizes the scientific evidence linking l electromagnetic fields to leukemia as weak and states "[i]n our opinion, this finding is insufficient to l warrant aggressive regulatory concem." l l Comment: l )' I Two comments (K2, L5) state that the SEIS fails to properly consider the effects of normal l ' operation on human health. In one case, the statement is based on differences in treatment of l human health and aquatic ecology in the SEIS, and in the other, the statement is based on l accumulation of activation products during the renewal term. l I Response: l . I I The radiation effects of normal reactor operation on human health are Category 1 issues. Based l on the analysis in the GEIS, the Commission made a generic determination that the radiation l effects of normal reactor operation during the renewal term on human health would be SMALL. l The staff has not identified any significant new information related to the radiation aspects of l human health in the ER, the scoping process, its independent review, or in either comment that l would call the conclusions in the GEIS into quection. Therefore, the staff relies on these l conclusions as amplified by supporting information in the GEIS related to the radiation effects of l normal operation during the renewal term on human health. l l According to the GEIS, tne components affected by neutron activation during reactor operation l include the reactor intemals and the biological shield. Extemal components are not activated. l , BGE has stated that it does not intend major refurbishment activities. Consequently, the dose from l I activation products during normal operations in the renewal term will be negligible. Doses from l ) activation products during decommissioning are considered exphcitly in Chapter 7 of the GEIS. l According to the GEIS: l 1 Extending operations to 60 years would not increase the shutdown radioactivity level of either a l PWR or BWR to any appreciable extent. This is because most of the radioactivity at shutdown l results from short-half-life radionuclides, such as "Co, that are already in equilibrium by the time 1 40 years of operations have transpired. . . Gamma-emitting "Nb is the most important long-half- l life radionuclide with regard to producing extemal radiation exposure. Based on Figure 7.4 [of l the GEIS), it can be determined that at shutdown "Nb contributes less than 0.001 percent of the j total potential dose. Even though 20 additional years of operation would increase the amount of l "Nb by 50 percent, it would not increase its contribution to the dose much above 0.001 percent. l NUREG-1437,. Supplement 1 A-17 October 1999
Appendix A l l The staff has addressed the human health issues (acute effects of electromagnetic fields l (Section 4.2.1) and chronic effects of electromagnetic fields (Section 4.2.2)] applicable to CCNPP l that are not Category 1 issues to reflect the status of its review to the extent required by the l Commission's regulations. A third Category 2 issue (Microbiological organisms (public l health)(Appendix F)] was determined not to be applicable to CCNPP because this issue concerned l heat dissipation systems that are not installed at CCNPP and bodies of water much smaller than l the Chesapeake Bay. i l l The staff reviewed the Category 2 aquatic ecology issues conceming the radiological effects of l CCNPP to determine whether there will be bioaccumulation of radioisotopes that could become l part of the ingestion pathway leading to man. The staff performed a detailed review to determine l whether station operation resulted in adverse effects on aquatic ecology, which could result in l adverse human health effects through this ingestion pathway. l l Category 2 aquatic e:: ology issues concerning the non-radiological effects of CCNPP on import.1t t l biota, such as heat, impingement, and entrainment, were assessed in compliance with NEPA, l which requires disclosure of those impacts. l l The SEIS treats the effect of normal operation of CCNPP on the more site-specific aquatic ecology l (a Category 2 issue) in more detail than that of the radiation effects of normal operation on human l health (a Category 1 issue) because the plant's effect on human health has already been l addressed ir detailin the GEIS, and no significant new information has been found to call into l question the conclusions in the GEIS. l l These comments do not provide any significant new information regarding the effects of radiation l exposure on human health, which are Category 1 issues. Therefore, these comments did not l result in modification of the GEIS text. l l Comment: l l Four comments (A15, A16, A24, A48) take the position that the operation of nuclear power plants l has adverse effects on human health. Comment A16 expresses concern that the health of l shellfish was considered in more detail than the health of humans. Comment A15 questions l whether there are studies that show that humans living around the plants are not dying earlier l because of radiation releases. The other two comments (A24, A48) cite studies that indicate that l operation of nuclear, power plants may be associated with increased incidences of cancer. i
\
l l Response: I l l The radiation effects of normal reactor operation on human health are Category 1 issues, as l l explained in the previous response. Published radiation standards are used to determine i l permissible levels. The Commission has concluded that the impacts from radiological releases j that do not exceed permissible levels in the Commission's regulations are small. October 1999 A-18 NUREG-1437, Supplement 1
Appendix A l Radiation standards reflect extensive scientific stut, by national and international agencies and I cre conservative to ensure that the public and those working at nuclear plants are protected. The l NRC radiatio'n exposure standards are presented in 10 CFR Part 20. l l Radioactive emissions from a nuclear power plant are consistently very low. BGE continually l monitors the levels of releases at the site to ensure that the releases stay well within NRC release l limits. The effluent limits for nuclear power plants are constantly being reviewed and challenged as l new studies are completed. NRC continually reviews new studies to identify new insights l conceming health effects and incorporate new knowledge into radiological protection standards. l 1 Numerous scientifically designed, peer-reviewed studies of personnel exposed to U.S. l occupational levels of radiation for years (versus life threatening accident doses or medical I therapeutic levels) have not shown any but the slightest effect on human health, and these effects l were from exposures well above the exposure levels of the typical member of the general public j from normal operation of a nuclear power plant. The UCLA study cited in comment A24 is l currently being reviewed by the scientific community. The appropriateness of the statistical l methods used for this type of epidemiological study are under evaluation. Whether the results of l this study have validity will be determined after rigorous analysis, including peer review. l l BGE will continue to be required to meet NRC radiation standards during the renewal term. These l comments did not provide any significant new information regarding the radiation effects of normal l operation on human health, which is a Category 1 issue. Therefore, these comments did not result l in modification of the SEIS text. l l A.1.7 Socioeconomics l l Ths record contains one comment on socioeconomics (A11). The comment is addressed below. l l Comment: I ! l l The comment (A11) asks if the socioeconomic analysis of the effects of license renewal (with l particular reference to public transportation) included the effects of both the additional employees l and the increase in population attributable to the additional employees. l l l l Rxponse: l l The staff considered both direct and indirect impacts in the SEIS, including public transportation. l However, BGE has clearly stated that it does not expect to hire additional employees for operation l during the renewal term and that the 60 worker estimate (from the GEIS) is used as an upper l bound or. maximum. The maximum resulting associated household and population increases in the l l three-county area of Southern Maryland was estimated at 223 households (revised from 192 in the l draft SEIS), anc ubout 643 people in the two counties nearest the plant (St. Mary's and Calvert l Counties). Neither the maximum increase in direct commuter traffic (60 plant employees) or the I general increase in traffic due to an increase in population of less than 1% (643 people) is likely to l be noticeable and, therefore, any impact would be small. l NUREG-1437, Supplement 1 A-19 October 1999 l
Appendix A l Although this comment did not directly result in modification of the SEIS text, the estimated number l of households and residents was updated. Additionally, the SEIS text has been modified to clarify l that BGE does not intend to hire additional employees and that the increase in employees and l resulting increase in population discussed in the SEIS are upper bounds. l l A.1.8 Archaeology and Historic Resources l J l The record contains only one comment related to archaeology and historic resources (R113). That j j comment is addressed below. 1 l l Comment: l l BGE states that the following paragraph in Section 4.4.5 of the Draft SEIS is unsubstantiated and j should be removed (R113) l l Because there is a distinct possibility that undiscovered and wr unrecorded prehistoric and [ historic period archaeological sites exist in the 2300 acre plLt site, as well as currently l undocumented historic structures, additional care must be taken during normal operation or l maintenance to ensure that cultural resources are teot inadvertently impacted. These activities l may include not only operation of the plant itself but also land management-related actions such l as farming, recreation, wildlife habitat enhancement, or maintaining / upgrading access roads l throughout the plant site. I l Response: l l This statement was not intended to be binding on BGE. Rather, it was intended to encourage BGE l to exercise care in identifying cultural resources that could be affected should BGE decide to l undertake activities involving land disturbances or structural modifications, and which BGE does j not not plan, as stated in the application. Accordingly, the statement has been clarified in the l SEIS text to address BGE's concems. l l A.1.9 Impacts of Mining, Milling, and Fuel Manufacture 1 l The record contains two comments related to the impacts of uranium mining, milling, and fuel l manufacture (A55, E4). The staff's response to these comments follow. l l Comment: l l One comment (A55) supports a statement that nuclear power is unsuitable for a society to use to .l produce energy by referring to the deaths of uranium miners from cancer. The other comment
] (E4) states that "[i]t is not possible to ignore the locally-located nationally distributed impacts of the l national burden of continued uranium mining, millir.g, and fuel rod manufacture."
l October 1999 A-20 NUREG-1437, Supplement 1
Appendix A I Rrponse: l l The impacts from the uranium fuel cycle, which includes the occupational exposures to uranium l miners cnd all workers for all phases of the fuel cycle, were evaluated in the GEIS. Given the l l cvailable information, the Commission concluded in Section 6.2.4 of the GEIS that, other than for l j the disposal of spent fuel and high-level waste, the impacts on individuals will be below regulatory l l limits, and therefore, the impacts from the uranium fuel cycle would be SMALL and is a Category 1 l j issue. l l These comments did not provide any significant new information regarding the impacts from the I uranium fuel cycle on human health. Therefore, they did not result in modification of the SEIS text. l l A.1.10 Severe Accident Mitigation Alternatives l l Tha record includes twelve comments related to severe action mitigation attematives (SAMAs) (A12, l A13, A14, A27, A28, A41, A42, A43, A50, A51, E3, L2). These comments generally fallinto four l groups. The first group contains a single comment (A14) that questions whether the effects of l l cccidents are considered environmental effects. The second group, which also contains a single l l comment (E3), deals with dose calculations used in the evaluation of SAMAs. The third group contains j four comments (A12, A13, A50, L2) related to core damage probabilities, and the fourth group contains l six comments (A27, A28, A41, A42, A43, A51) related to the timing of improvements associated with l cost-effective SAMAs. These comments are addressed below. l l l Comment: l l l
. Comment A14 questions whether the effects of accidents are considered environmental effects. l 1
Response: l l The effects of accidents are considered in both environmental and safety reviews for license l renewal. In evaluating the renewal application for the environmental effects of accidents at Calvert l Cliffs, the staff relied on the conclusions and supporting information in the GEIS related to the l effects of design basis and severe accidents. l l Chapter 5 of the GEIS contains a detailed discussion of the possible environmental effects of l postulated accidents within the design basis of the plant. Based on that information, the l Commission concluded that the design basis accidents are a Category 1 issue. The staff has not l identified any significant new information related to design basis accidents in the ER, the scoping l process, its independent review, or in the comments on the draft SEIS that would call into question l the conclusions contained in the GEIS. Thus, the staff concludes that there are no impacts of l design basis accidents beyond those discussed in the GEIS. This conclusion is stated in l Section 5.1 of the SEIS. l l Chapter 5 of the GEIS also contains an evaluation of the environmental effects of postulated l accidents beyond the design basis of the plant. These events include accidents that lead to l damage of the reactor core, i.e., severe accidents. The study concluded that the risk (probability l NUREG-1437, Supplement 1 A-21 October 1999
Appendix A l weighted consequences) from individual nuclear power plants, including Calvert Cliffs, is small and l represents only a small fraction of the risk to which the public is exposed from other sources. At l this time, the only aspect of severe accidents judged to warrant plant-specific consideration as part l of license renewal concems the evaluation of SAMAs. Accordingly, SAMAs are considered in l Section 5.2 of the SEIS. ' l l This comment did not result in modification of the SEIS text. l l Comment: l l One comment (E3) disagrees with the dose calculation methodology used by the staff. It states l that "The averaging over a 50 mile radius is totally inappropriate. Wind rose analysis within a ten l mile radius, with calculations of the spectrum of impacts of the intra-radial high density, clearly l identifiable communities need to be done." l l Response: l l The doses used in the SAMA analysis were calculated using the NRC-developed MELCOR l Accident Consequence Code System (MACCS) and site-specific data for meteorology and l population. The meteorological conditions were established by sampling from a full year of l site-specific weather data, defined in terms of windspeed, wind direction, atmospheric stability, and l rain conditions at various distance from the plant. This accounts for the frequency of wind in each , l direction. The population around the site was distributed by location in a grid consisting of sixteen l sectors, with each sector divided into 14 radial intervals extending out to 50 miles. This accounts l for the site-specific population distribution around the site, such as areas of high population density l and their respective locations. The MACCS code combines this information together with other l factors to estimate the cumulative dose (rather than average dose) to the population residing within l 50 miles of the plant. A distance of 50 miles was selected because existing analyses show that the l large majority of health effects from a severe accident release occur within 50 miles of the plant l site. In addition, this value has been widely used in the analyses of offsite consequences for other l plants, and provides a convenient basis for comparison between plants. l l Thus, the methodology used in the analysis appropriately takes into account the site-specific j meteorological conditions and population distribution in the vicinity of CCNPP. While wind rose l analysis as proposed by the commenter could be another valid approach for estimating dose l consequences, the methodology used by the staff provides a reasonable estimate of the l consequences of an accident for the purposes of identifying and evaluating SAMAs. l l This comment did not result in modification of the SEIS text. l l Comment: l l Four comments (A12, A13, A50, L2) deal with the core damage probability. They assert that the l probability of core damage is unacceptably high and that extending the license breaks a promise l made 25 years ago by increasing the risk to the public beyond tha: Tiginally agreed to. I October 1999 A-22 NUREG-1437, Supplement 1
Appendix A Rrponse: l l It is important to differentiate between core damage frequency and risk. The risk associt 3d with a l severe accident corresponds to the product of the probability of the accident (i.e., core damage l frequency) and the consequences of the accident. The degree of damage to the core can range l over a wide spectrum, from a pin-hole leak in a fuel rod that would result in minimum l consequences in terms of radiation release to a core melt progression resulting in significant l radiological consequences. In addition, core damage events in which the containment building l maintains its leak-tight integrity have minimal offsite consequences. Because the containment is l expected to maintain its leak-tight integrity in the majority of core damage events, there is only a l small likelihood (less than one chance in ten) that a core damage event would result in significant l releases to the environment. Stated in other words, only a small fraction of the core damage l events would result in significant releases and risk to the public. l l The staff assessed the risk posed from core damage events in Chapter 5 of the GEIS. As set forth l in the GEIS, the risk (probability weighted consequences) from individual nuclear power plants, l including Calvert Cliffs, is small and represents only a small fraction of the risk to which the public l is exposed from other sources. The only aspect of severe accidents judged to warrant plant- l specific consideration as part of license renewal concerns the evaluation of SAMAs. The potential l to further reduce risk at Calvert Cliffs was assessed as part of the NRC's assessment of SAMAs l reported in Section 5.2 of the SEIS. As a result of this assessment, several plant enhancements l were identified which would further reduce risk. These enhancements are being further evaluated l by the licensee and NRC as discussed in response to the six comments below. l 1 With regard to the comment that extending the license breaks a promise made 25 years ago by l increasing the risk to the public beyond that originally agreed to, it should be noted that the l regulations in place at the time of the original licensing of Calvert Cliffs (10 CFR 50.51) state that l operating licenses will be issued for a fixed period of time, not to exceed 40 years from date of l issuance. However, the Atomic Energy Act and 10 CFR 50.51 also state that licenses may be l renewed by the Commission upon the expiration of the period. The assertion that the expiration l date in the original license constitutes a promise that the plant will not operate beyond that time is l inconsistent with the Atomic Energy Act. Thus, from a regulatory perspective there was never any l
" written promise" or agreement that the plant would not be permitted to operate beyond the original l 40-year term. l l
These comments did not result in modification of the SEIS text. l l Comment: I There were six comments related to the timing of improvements identified in the SAMA analysis l (A27, A28, A41, A42, A43, A51). The comments expressed concern that SAMAs not related to l managing the effects of aging are not to be implemented as part of license renewal. l l l l NUREG-1437, Supp> ment 1 A-23 October 1999
Appendix A I l Response: I l l The SAMA evaluation identified several plant enhancements that appear to be cost beneficial. l These enhancements do not relate to managing the effects of aging during the period of extended l operation and, therefore,10 CFR Part 54 does not require them to be implemented as part of l license renewal. Moreover,10 CFR 54.30 provides that the licensee's obligation to take measures [ to ensure that licensed activities during the current license term will be conducted in accordance l with the current licensing basis is not within the scope of the license renewal review. Therefore, it l is more appropriate to pursue these enhancements as an issue under the current operating l license, rather than as a license renewal issue. Contrary to the understanding reflected in two of l these comments, consideration of enhancements resulting from the SAMA analysis as license l renewal issues would allow implementation to be deferred until the end of the current operating l term. Consideration of these enhancements as current operating issues would allow for l implementation before the current license expiration date, should it be determined appropriate to l implement'them. The SAMAs are being further evaluated by NRC as part of a staff follow-up effort l related to the Individual Plant Examination studies requested by Generic Letter 88-20. l l These comments did not result in modification of the SElS text.
.I l A.1.11 Operational Safety lasues Associated with Current Operation l
l The record includes five comments related to operational safety issues (A22, A53, B5, C, F). The l issues in the comments include the NRC's policy related to distribution of potassium iodide (A22, B5), l the Y2K computer problem (A53), the risk associated with aircraft collision with the reactors /C, F), and ~l a request for detailed analysis of the risk of catastrophic vessel failure due to the injection of emergency l cooling water (L8). These comments involve concerns that are relevant to current CCNPP operation. l In accordance with 10 CFR 54.30, these issues are outside the scope of license renewal. They have l been referred to the NRC operating plant project manager for disposition. These comments did not l result in modification of the SEIS text. I l A.1.12 Age-related Safety Issues l l The record includes ten comments associated with age-related safety issues (A3, A4, A23, A52, B6, L6, l L7, L8, L9, L10). Nine of the issues deal with metallurgy. Six of the nine issues (A3, A23, A52,86, L7, l L8) deal specifically with embrittlement, and the other two (A4, L9) deal with metal samples and the l reactor vessel surveillance program. One comment (L10) concems age-related degradation of the j reactor control system. The remaining comment (L6) requests that the license extension be more l restrictive, especially regarding age-related materials and maintenance. These comments are outside of l the scope of the staff's review of the environmental effects of renewing the CCNPP licenses. However, j they involve concems that are relevant to the extended operation of the facility and have been referred l to the NRC license renewal safety project manager for disposition. These comments did not result in l modification of the SEIS text. I October 1999 A-24 NUREG-1437, Supplement 1
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Appendix A f A.1.13 Spent Nuclear Fuel l l The record includes five comments related to spent nuclear fuel (A19, A45, A46, B2, E2). One of the l comments (A46) deals with national high-level waste policy, and the remaining four comments (A19, l A45, B2, E2) deal with high-level waste storage and disposal. The comments are addressed below l j l Comment: l l Comment A46 addresses high-level waste policy. It characterizes the nuclear waste policy as l
- bankrupt for 50 years in terms of shuttling the waste around within the fuel pools, exceeding
.. l design capacities now four or five times in some sites, shuttling it off into dry casks that have 20- l year license periods for wastes that will persist for millions of years in geological spans of time, j simply to continue operation...." l l
Response: l 1 The Commission's regulations in 10 CFR 51.23(a) (the Waste Confidence Rule) sets forth the l Commission's position on its high level waste policy.10 CFR 51.23(a) states l l l The Commission has made a generic determination that, if necessary, spent fuel generated in l any reactor can be stored safely and without significant environmental impacts for at least 30 l years beyond the licensed !ife for operation (which may include the term of a revised or renewed l license) of that reactor at its spent fuel storage basin or at either onsite or offsite independent l spent fuel storage installations. Further, the Commission believes there is reasonable l assurance that at least one mined geologic repository will be available within the first quarter of l the twenty-first century, and sufficient repository capacity will be available within 30 years l beyond the licensed life for operation of any reactor to dispose of the commercial high-level l waste and spent fuel originating in such reactor and generated up to that time. l l This comment did not result in modification of the SEIS text. See Section A.1.3 of this report for l further discussion of the Waste Confidence Rule. l l Comment: l l 1 The record contains four comments (A19, A45, B2, E2) that deal with high-level waste storage and l disposal. l l R:rponse: l l Onsite storage of spent nuclear fuel is a Category 1 issue. The safety and environmental effects of l long-term storage of spent fuel onsite has been evaluated by the NRC, and, as set forth in the l Waste Confidence Rule, the NRC generically determined that such storage can be accomplished l without significant environmentalimpact. In the Waste Confidence Rule, the Commission l determined that spent fuel can be stored onsite for at least 30 years beyond the licensed operating l life, which may include the term of a rendwed license. The NRC has a certification process for l casks, regulated by 10 CFR Part 72. l i NUREG-1437, Supplement 1 A-25 October 1999
Appendix A .I l Siting of a waste repository is a separate regulatory action involving the U.S. Department of Energy l (DOE). Characterization of the site under review is projected to be complete by 2002,.and a i j geologic repository is not expected to be ready before 2010 (GEIS). In the interim, onsite spent ] l fuel storage in pools and in dry cask storage facilities continues in accordance with NRC l regulations. Consequently, these comments did not result in modification of the SEIS text. l l l A.1.14 Decommissioning l l The record includes two comments related to decommissioning (A20,83). These responses to these l comments follow. l l Comment: l l The comments indicate concem about eventual decommissioning, burial costs, and future care and l protection of the facility. l l Response: l l Decommissioning is a Category 1 issue. Specific issues related to decommissioning-waste l management, socioeconomic effect, radiation doses, air quality, water quality, and ecological l effects-are addressed in Chapter 7 of this SEIS. The staff did not identify any significant new l infomiation in the ER, the scoping process, its independent review, or review of the comments to l the draft SEIS that would call into question the conclusions set forth in the GEIS. Therefore, the l staff relies upon the conclusions as amplified by the supporting information in the GEIS. No l modifications were made to the text of the SEIS on the basis of these comments. l l A.1.15 Alternatives l l The record contains six comments directly related to altematives (A59, B12, E1, G, L3, Q3). Three of l the comments (A59, B12, Q3) provide information about alternatives considered in the draft SEIS. The l information supplied in comment Q3 discusses the effects of recent developments that affect the l selection of alternatives in Maryland, including recent changes in property tax laws, deregulation, air l cmission offsets, and BGE conservation programs. Information from this comment has been l incorporated in Chapter 8 of this report. I l Three of the comments (E1, G, L3) object to the various aspects of the discussion of attematives in l Chapter 8. These comments are addressed below. I l Comment: l l One comment (L3) objects to the conclusion related to demand-side management as part of the l conservation attemative in Section 8.2.4.11. The comment asserts that conservation technology is l a viable replacement altemative to CCNPP. It also asserts that utility deregulation could result in l cheaper alternatives to the facility. October 1999 A-26 NUREG-1437, Supplement 1
Appendix A Response: l l The text of Section 8.2.4.11 has been revised to include new information regarding utility l deregulation. However, as stated in the revised text of Section 8.2.4.11, it is not clear that utility l deregulation will result in an increase in cost-effective conservation; moreover, utility-sponsored l conservation is declining. l 1 Comment: l
, l Two comments (E1, G) suggest that the SEIS should consider fuel cells as an attemative. l l
R:Oponse: l l Section 8.2.4.12, which discusses fuel cells, has been added to the SEIS. l I A.1.16 Miscallaneous I l Th3 r: cord contains five comments that do not fall within any of the other categories (M, N, P, R, T). l Ona of the comments (R), submitted by BGE, supports the staff approach and conclusions, and l contains a list of 170 specific comments. Most of the specific comments are technical clarifications, l i corrections to information in the SEIS, or suggested changes in format and presentation of the SEIS. l l R:sponses to the specific comments are provided in Table A.2. These comments are the subjects of l l S:ctions A.1.17 and A.1.18, respectively. l l Three of the comment letters (M, P, T) appear to have been placed on the CCNPP docket in error. l Comment letter M was submitted by BGE as a comment on a rulemaking. The letter was forwarded to l j tha correct docket. Comment letter P, which supports the GEIS conclusions on the effects of l transportation of high-level waste, may also have been intended as a comment on the rulemaking. I Simil:rly, comment letter T (submitted after the close of the comment period for the draft SEIS) also l cppears to have been submitted in response to the rulemaking and was forwarded to the correct l dock:t. I I Finilly, one comment (N) provided two Intemet URLs (Universal Resource Locator [ address]) for a l commercial concern providing services related to nuclear waste storage. The NRC does not l rccommend or otherwise endorse the offerings of the concem. l l l 4 A.1.17 Technical Clarifications and Corrections l 6 l Tra list of 170 specific comments included with comment R are technical enhancements or correction l , of information such as plant dimensions, document dates, and plant-specific terminology. Of the l l specific comments provided, those in the following list fit this category: l l l l R2,R4,R12,R15,R16,R20,R22,R26,R28,R29,R30,R31,R32,R35,R36,R47,R51,R57,R61, l R64, R65, R84, R89, R92, R95, R100, R107 R108, R109, R110, R111, R115, R116, R119, R130, l t NUREG-1437, Supplement 1 A-27 October 1999
Appendix A l ' R132, R133, R135, R136, R137, R138, R139, R140, R141, R142, R143, R144, R152, R153, R155, l R159,R166,R168,R170. l l A separate log of BGE's specific comments and the NRC responses is attached as Table A.2. l l A.1.18 Format and Presentation (spelling, grammar, references, clarity, etc.) I l Many_of the specif!: comments included with comment R suggested changes for clarification or l accuracy and correction of typographical errors. The following comments fit this category and the l referenced text was corrected, clarified, or resolved. l l R1, R3, R5, R6, R7, R8, R9, R10, R11, R13, R14, R17, R18, R19, R21, R23, R24, R25, R27, R33, l R34,R37.R38,R39,R40,R41,R42,R43,R44,R45,R46,R48,R49,R50,RS2,RS3,R54,RSS,RS6, l R58,R59,R60,R62,R63,R66,R67,R68,R69,R70,R71,R72,R73,R74,R75,R76,R77,R78,R80, l R81,' R82, R83, R85, R86, R87, R88, R90, R91, R93, R94, R96, R97, R98, R99, R101, R102, R103, l R104, R105, R106, R112, R114, R117, R118, R120, R121, R122, R123, R124, R125, R126, R127, l R128, R129, R134, R147, R149, R150, R151, R154, R156, R157, R158, R160, R161, R162, R163, l R164,R165,R167,R169. l The specific comments and NRC responses are included in Table A.2. l l Comments D and Q4 also included specific comments of this nature. In each case, the text of the SEIS l has been modified in response to the comment. i October 1999 A-20 NUREG-1437, Supplement 1
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