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| | issue date = 09/10/1979 | | | issue date = 09/10/1979 |
| | title = Submits Detailed Comments on Des | | | title = Submits Detailed Comments on Des |
| | author name = MEIREOTTO L E | | | author name = Meireotto L |
| | author affiliation = INTERIOR, DEPT. OF | | | author affiliation = INTERIOR, DEPT. OF |
| | addressee name = REGAN W H | | | addressee name = Regan W |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000387, 05000388 | | | docket = 05000387, 05000388 |
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| {{#Wiki_filter:REGULA TUR INFORMATION DISTRIBUTION | | {{#Wiki_filter:REGULA TUR INFORMATION DISTRIBUTION 'KM (RIDS) |
| 'KM (RIDS)ACCK'SSION NBR:7909130493 DOC~DATE: 79/09/10 NOTARIZED: | | ACCK'SSION NBR:7909130493 DOC ~ DATE: 79/09/10 NOTARIZED: NO DOCKET FAClL:50-387 Susquehanna Steam Electr ic Station~ Unit l~ Pennsylva 05000387 50-388 Susquehanna Steam Electric Stations Unit Zg Pennsylva 050 AUTH.NAME AUTHOR AFFILIATION |
| NO DOCKET FAClL:50-387 Susquehanna Steam Electr ic Station~Unit l~Pennsylva 05000387 50-388 Susquehanna Steam Electric Stations Unit Zg Pennsylva 050 AUTH.NAME AUTHOR AFFILIATION | | ~KIREDTTO>L ~ E ~ InteriOrEUept ~ Of RECIP ~ NAME REC?PIKNT AFFILIATION REGAN g (0 ~ |
| ~KIREDTTO>L | | H ~, Envir onmental ProJ ects Branch 2 SUBJECT; Submits detailed comments on CODE: COOZS TITlE:- |
| ~E~InteriOrEUept | | COPIES RECEIVEO:LTR KnVir OnsCOmmentS DES'ISTRIBUTION ENCL g SIZEt NOTES: E/i/> Z 4eoMsOwWMM w&W &4'ESAR |
| ~Of RECIP~NAME REC?PIKNT AFFILIATION REGAN g (0~H~, Envir onmental ProJ ects Branch 2 SUBJECT;Submits detailed comments on DES'ISTRIBUTION CODE: COOZS COPIES RECEIVEO:LTR ENCL g SIZEt TITlE:-KnVir OnsCOmmentS 17 BC KP~~W AD jl1Oo R~1 05 PM/'EE'CF/18 IA~/B'Q ACTION: NOTES: 4 E/i/>Z<2 8&4'ESAR 4 ALL R%874'8~R~/Co''dzauT//@Jr eoMsOwWMM w&W WoOMW eWw w W&sQMW~Wa PNWWwW4y&a~WMWwey&WMNN'WwW~WMWMWWNN A Wm&MRS wA RECIPIENT COPIES RECIP IENT COPIES ID CODE/NAME LTTR EN L IO COOK/NAME. | | < 2WoOMW8eWw 4 ALL R %874' 8 R w W&sQMW~Wa PNWWwW4y&a~WMWwey&WMNN'WwW~WMWMWWNN ~ ~ /Co''dzauT//@Jr A Wm&MRS wA RECIPIENT COPIES RECIP IENT COPIES ID CODE/NAME LTTR EN L IO COOK/NAME. LTTR ENCL ACTION: 05 PM /'EE'CF/ 17 BC KP~ ~W 18 IA ~/ B'Q AD jl1Oo R~ 1 INTERNAL'1 G 02 NRC POR 07 IFK 09 ENON SPEC BR 10 CST BNFT ANL 11 TA/EOO. |
| LTTR ENCL INTERNAL'1 G 07 IFK 10 CST BNFT ANL 12 AD SITE.TECH 15 EFLT TRT SYS 19 DIR DSE AD SITE ANALY EXTERNAL: 03 LPDR 20 NATL LAB 02 NRC POR 09 ENON SPEC BR 11 TA/EOO.14 ACDENT ANALY RAD ASST QH AD ENVIRON l'KCH OELD 04 NSIC ACRS L,Ng 4 QJg SEP 14 1979 G'OTAL IvUHBKR OF COPIES REQUIRED: LTTR~ENCL~5 ghee oc<United States Department of the Interior OFFICE OF THE SECRETARY WASHINGTON, D.C.20240 79/632 PEP g 0 1979 Mr.William H.Regan, Jr.Chief, Environmental Projects Branch 2 Division of Site Safety and Environmental Analysis Nuclear Regulatory Commission Washington, D.C.20555 | | 12 AD SITE. TECH 14 ACDENT ANALY 15 EFLT TRT SYS RAD ASST QH 19 DIR DSE AD ENVIRON l'KCH AD SITE ANALY OELD EXTERNAL: 03 LPDR 04 NSIC 20 NATL LAB ACRS L,Ng 4 QJg SEP 14 1979 IvUHBKR OF COPIES REQUIRED: LTTR ~ ENCL ~5 G'OTAL |
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| ==Dear Mr.Regan:==
| | ghee oc < |
| The draft environmental statement for-Susquehanna, Steam Electric Station (SSES)Units 1 and 2'as been reviewed by this Department and we have the following comments.The comments are organized by page number.in, the document..Pa e 2-28 and Pa e-4-33 We are concerned that the draft statement does not adequately address archeological and historic concerns.There appears to be.a need for further investigation of significant properties in the area and identification of their relationship to the project.This applies to properties already on the National Register and any potential properties in the area but not yet evaluated.
| | United States Department of the Interior OFFICE OF THE SECRETARY WASHINGTON, D.C. 20240 79/632 PEP g 0 1979 Mr. William H. Regan, Jr. |
| On page 4-33, the draft states that"given the present inadequacies regarding cultural resource inventory and data, the staff cannot make a determination to the effect that the plant's operation will have no adverse effects on cultural resources that may be eligible for inclusion in the National Register.However, it is unlikely that the plant's operation will affect resources that are currently listed in the National Register (located in excess of 16 km from the plant property)..." The draft is unclear regarding the impact the plant and transmission corridors will have on properties close to the project site.Of particular concern are McClintock Hall, the Denison House,~and Catlin Hall.We urge the NRC to undertake a complete archeological and historic survey of the area in accordance with the requirements of 36 CFR 800 and Executive Order 11593.Names of persons qualified to undertake this survey may be obtained by contacting the State 909>go P(o@0 Historic Preservation Officer (SHPO}for Pennsylvania, Edward Veintraub, Executive Director, Historical Museum Commission, P.O.Box 1026, Harrisburg, PA 17120.Results of the survey should be included in the final document.Also in consultation with the SHPO the NRC should, determine if any of those properties identified in the survey are eligible for listing in the National Register.Zf they are determined to be eligible, the procedures and process of 36 CFR 800.4 and 5 must be followed to completion. | | Chief, Environmental Projects Branch 2 Division of Site Safety and Environmental Analysis Nuclear Regulatory Commission Washington, D.C. 20555 |
| ~Pa e 3-8 Sulfuric acid will be used to control scale formation. | | |
| As noted in the statement the system will be operated at a positive satura-tion index to minimize the addition of acid.without this control on acid usage, the discharge could carry over four times the sulfate concentration of the receiving waters.This could aggravate an already stressed situation since the Susquehanna exhibits high and variable sulfate concentrations. | | ==Dear Mr. Regan:== |
| Zn the same manner that alternative levels of acid addition have been discussed, we suggest that alternate methods of scale and corrosion control should be looked at.The final statement should present an environmental evaluation of such methods as organic or hydrochloric acids or mechanical means~Pa e 4-9 Since the intake structures for this plant have.been constructed, the final statement should discuss what sampling program is proposed and when it would be implemented. | | |
| to determine levels of entrainment and impingement, during all expected.flow conditions, of Susquehanna River fish and aquatic invertebrates. | | The draft environmental statement for- Susquehanna, Steam Electric Station (SSES) Units 1 and 2'as been reviewed by this Department and we have the following comments. The comments are organized by page number. in, the document. |
| Further, the final statement should include a discussion of the possible actions the licensees will take to modify the project to protect such aquatic resources in the event significant adverse impacts occur from entrainment, impingement, or streamflow diversion for consumptive use (50 cfs average).Pa e 4-12 The staff concludes that no adverse environmental impacts, other than atmospheric plumes and snowfall, will occur as a result of the operation of the cooling towers at the SSES.The licensees propose to construct a reservoir (Pond Hill)to provide makeup water during low flow conditions in the Susquehanna River.The final statement should be revised to indicate some adverse environ-mental impact will occur with the operation of the cooling towers and related reservoir. | | .Pa e 2-28 and Pa e- 4-33 We are concerned that the draft statement does not adequately address archeological and historic concerns. There appears to be. |
| Construction of the dam and reservoir will destroy terrestrial wildlife habitat and reservoir filling operations will impact Susquehanna River aquatic invertebrate and fish populations through impingement,, entrainment, streamflow regulation, and consumptive use of such flows.~Pa e 5-2 We agree with the staff that the applicant should monitor groundwater both upgradient and downgradient on a monthly basis.We note that the potential for radionuclide contamination.of groundwater is implied on page D-1 of Appendix D,(item 1.6);however, figure 4.1 (p.4-13)does not indicate groundwater as an exposure pathway to humans.~Pa e 6-4 The conclusion that"the environmental risks due to radiological accidents are exceedingly small and need not be.considered further" ignores the probability and the consequences of core-melt accidents ('p.6-4, par.1)., As was explained in the environmental statement for the Palo Verde Nuclear Station (NUREG-0522, 1979), this"realistic analysis" is based on procedures in the Proposed Annex to Appendix D, 10 CFR Part 50, which specifically exclude the evaluation of core-melt accidents. | | a need for further investigation of significant properties in the area and identification of their relationship to the project. |
| Environmental damages resulting from a core-mel't accident can be devastatingly severe and conclusions concerning environmental risks that ignore these accidents must be questioned. | | This applies to properties already on the National Register and any potential properties in the area but not yet evaluated. |
| We believe that site-specific evaluations of the full range of potential accidents should be a part of the site selection process for nuclear power stations.The section on Postulated Accidents Involving Radioactive Materials enumerates"Several of the more significant findings" of the Lewis Report (p.6-3).The three findings summarized exclude the final finding of that report: There have been instances in which NASH-1400 has been misused as a vehicle to judge the acceptability of reactor risks.In other cases it may have been used prematurely as an estimate of the absolute risk of reactor accidents without full reali-zation of the wide band of uncertainties involved.Such use should be discouraged.(NUREG/CR-0400, p.x).A footnote to table 6.2 states that"These calculations do not take into consideration the experience gained from the accident at the Three Mile Island site on March 28, 1979" (p.6-3, footnote A).However, this provides no guidance on the possible magnitude or even the direction of the errors that may exist in the radiological consequences that are shown in the table.The largest estimated dose to population in a 50-mile radius from any accident shown in the table is 37 man-rem.Until such time as the table can be revised, it might be helpful to note that the estimated dose to the population within a 50-mile radius of the Three Mile Island site was calculated to be 3,300 man-rem (NUREG-0558), p.2, par.2).The populations within that radius are not greatly different for the two sites, being 2,164,000 people in the case of the Three Mile Island site and projected to be 1,517,123 people within 50 miles of Susquehanna Steam Electric Station in the year 1980 (ER, table 2.1-8).~Pa e B-5 Table B.2 (page B-4)shows that 1,236 acres of forest and farmland will be required as rights-of-way for construction of a new transmission line system.The forested area could be managed effectively for wildlife if preferred vegetation and cover for grazing wildlife species were planted.Their feeding activities would help control revegetation of nuisance woody vegetation and reduce the need for clearing and herbicide applications. | | On page 4-33, the draft states that "given the present inadequacies regarding cultural resource inventory and data, the staff cannot make a determination to the effect that the plant's operation will have no adverse effects on cultural resources However, that may be it is eligible for inclusion in the National Register. |
| We recommend that Appendix B discuss the possibility of using plantings recommended by the Pennsylvania Gaae Commission for.all forested areas cleared during transmission line construction. | | unlikely that the plant's operation will affect resources that are currently listed in the National Register (located in excess of 16 km from the plant property) . . ." The draft is unclear regarding the impact the plant and transmission corridors will have on properties close to the project site. Of particular concern are McClintock Hall, the Denison House, ~ and Catlin Hall. |
| We hope these comments will assist the preparation of the final.neer Lar y E.Meierotto SE CRETARY}} | | We urge the NRC to undertake a complete archeological and historic survey of the area in accordance with the requirements of 36 CFR 800 and Executive Order 11593. Names of persons qualified to undertake this survey may be obtained by contacting the State P(o@ 0 909> go |
| | |
| | Historic Preservation Officer (SHPO} for Pennsylvania, Edward Veintraub, Executive Director, Historical Museum Commission, P.O. Box 1026, Harrisburg, PA 17120. Results of the survey should be included in the final document. Also in consultation with the SHPO the NRC in the survey should, are determine eligible for if any of those properties identified listing in the National Register. |
| | Zf they are determined to be eligible, the procedures and process of 36 CFR 800.4 and 5 must be followed to completion. |
| | ~Pa e 3-8 Sulfuric acid will be used to control scale formation. As noted in the statement the system will be operated at a positive satura-tion index to minimize the addition of acid. without this control on acid usage, the discharge could carry over four times the sulfate concentration of the receiving waters. This could aggravate an already stressed situation since the Susquehanna exhibits high and variable sulfate concentrations. |
| | Zn the same manner that alternative levels of acid addition have been discussed, we suggest that alternate methods of scale and corrosion control should be looked at. The final statement should present an environmental evaluation of such methods as organic or hydrochloric acids or mechanical means |
| | ~Pa e 4-9 Since the intake structures for this plant have. been constructed, the final statement should discuss what sampling program is proposed and when it would be implemented. to determine levels of entrainment and impingement, during all expected. flow conditions, of Susquehanna River fish and aquatic invertebrates. Further, the final statement should include a discussion of the possible actions the licensees will take to modify the project to protect such aquatic resources in the event significant adverse impacts occur from entrainment, impingement, or streamflow diversion for consumptive use (50 cfs average). |
| | Pa e 4-12 The staff concludes that no adverse environmental impacts, other than atmospheric plumes and snowfall, will occur as a result of the operation of the cooling towers at the SSES. The licensees propose to construct a reservoir (Pond Hill) to provide makeup water during low flow conditions in the Susquehanna River. The final statement should be revised to indicate some adverse environ-mental impact will occur with the operation of the cooling towers |
| | |
| | and related reservoir. Construction of the dam and reservoir will destroy terrestrial wildlife habitat and reservoir filling operations will impact Susquehanna River aquatic invertebrate and fish populations through impingement,, entrainment, streamflow regulation, and consumptive use of such flows. |
| | ~Pa e 5-2 We agree with the staff that the applicant should monitor groundwater both upgradient and downgradient on a monthly basis. We note that the potential for radionuclide contamination .of groundwater is implied on page D-1 of Appendix D,(item 1.6); however, figure 4.1 (p. 4-13) does not indicate groundwater as an exposure pathway to humans. |
| | ~Pa e 6-4 The conclusion that "the environmental risks due to radiological accidents are exceedingly small and need not be. considered further" ignores the probability and the consequences of core-melt accidents |
| | ('p. 6-4, par. 1)., As was explained in the environmental statement for the Palo Verde Nuclear Station (NUREG-0522, 1979), this "realistic analysis" is based on procedures in the Proposed Annex to Appendix D, 10 CFR Part 50, which specifically exclude the evaluation of core-melt accidents. Environmental damages resulting from a core-mel't accident can be devastatingly severe and conclusions concerning environmental risks that ignore these accidents must be questioned. We believe that site-specific evaluations of the full range of potential accidents should be a part of the site selection process for nuclear power stations. |
| | The section on Postulated Accidents Involving Radioactive Materials enumerates "Several of the more significant findings" of the Lewis Report (p. 6-3). The three findings summarized exclude the final finding of that report: |
| | There have been instances in which NASH-1400 has been misused as a vehicle to judge the acceptability of reactor risks. In other cases it may have been used prematurely as an estimate of the absolute risk of reactor accidents without full reali-zation of the wide band of uncertainties involved. Such use should be discouraged. (NUREG/CR-0400, p. x). |
| | A footnote to table 6.2 states that "These calculations do not take into consideration the experience gained from the accident at the Three Mile Island site on March 28, 1979" (p. 6-3, footnote A). However, this provides no guidance on the possible magnitude or even the direction of the errors that may exist in the radiological consequences that are shown in the table. The largest |
| | |
| | estimated dose to population in a 50-mile radius from any accident shown in the table is 37 man-rem. Until such time as the table can be revised, it might be helpful to note that the estimated dose to the population within a 50-mile radius of the Three Mile Island site was calculated to be 3,300 man-rem (NUREG-0558), p. 2, par. 2). |
| | The populations within that radius are not greatly different for the two sites, being 2,164,000 people in the case of the Three Mile Island site and projected to be 1,517,123 people within 50 miles of Susquehanna Steam Electric Station in the year 1980 (ER, table 2.1-8). |
| | ~Pa e B-5 Table B.2 (page B-4) shows that 1,236 acres of forest and farmland will be required as rights-of-way for construction of a new transmission line system. The forested area could be managed if effectively for wildlife preferred vegetation and cover for grazing wildlife species were planted. Their feeding activities would help control revegetation of nuisance woody vegetation and reduce the need for clearing and herbicide applications. We recommend that Appendix B discuss the possibility of using plantings recommended by the Pennsylvania Gaae Commission for. all forested areas cleared during transmission line construction. |
| | We hope these comments will assist the preparation of the final. |
| | neer Lar y E. Meierotto SE CRETARY}} |
|
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant ML20207G5051999-06-0707 June 1999 Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML20203G5821999-02-17017 February 1999 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety. Documents Listed in App D Being Withheld in Part (Ref FOIA Exemption 5) ML20202F4761999-01-29029 January 1999 First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety.App B Records Being Withheld in Part (Ref FOIA Exemption 7C) ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML20195J9101998-11-18018 November 1998 Forwards Notice of Withdrawal of Application for Amends to Facility Operating Licenses (Notice).Notice Has Been Filed with Ofc of Fr.Amends Would Have Revised TS to Eliminate HPCI Pump auto-transfer on High Suppression Pool Level ML20155F7201998-11-0303 November 1998 Final Response to FOIA Request for Documents.Documents Listed in App B Being Encl & Being Released in Entirety. Documents Listed in App C Being Withheld in Part (Ref Exemption 7C) ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998 Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21 ML18030A1001998-10-12012 October 1998 Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized ML18030A4311998-09-29029 September 1998 Forwards Rev 27 & 28 to SSES Emergency Plan ML20151W4951998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs for Region I IR 05000387/19980081998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved ML18030A0991998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved ML18026A4961998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations IR 05000387/19980031998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations ML20202F5501998-07-17017 July 1998 Responds to PP&L Corp Auditing Repts 739459-97,739459-1-97 & 739459-2-98 Re SSES Investigations Into Missed Alarm Tests ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML18030A4291998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue ML18017A2181998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance ML18026A2901998-06-0909 June 1998 Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed ML18026A2891998-05-22022 May 1998 Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods ML18026A4941998-05-12012 May 1998 Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document ML20202H1331998-04-16016 April 1998 Partially Deleted Ltr Re Concerns Raised to NRC Concerning PP&L Susquehanna Facility NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable1998-04-15015 April 1998 Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable ML20216B6811998-04-0101 April 1998 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Being Released in Entirety ML17159A2341998-03-30030 March 1998 Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998 Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML17159A1781998-03-0202 March 1998 Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4. PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998 Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998 Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213 ML20203M5071998-02-26026 February 1998 Final Response to FOIA Request for Documents.Records in App a Being Placed in PDR & Encl.Records in App B Partially Withheld (Ref FOIA Exemption 6) ML20203B5931998-02-23023 February 1998 Ack Receipt of & Wire in Amount of $55,000 in Payment for Civil Penatly Proposed by NRC Ltr . Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized ML18030A1001998-10-12012 October 1998 Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998 Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21 ML18030A4311998-09-29029 September 1998 Forwards Rev 27 & 28 to SSES Emergency Plan ML18030A0991998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved IR 05000387/19980081998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved ML18026A4961998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations IR 05000387/19980031998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations ML18017A2181998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance ML18030A4291998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue ML18026A2901998-06-0909 June 1998 Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed ML18026A2891998-05-22022 May 1998 Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods ML18026A4941998-05-12012 May 1998 Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document ML17159A2341998-03-30030 March 1998 Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998 Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998 Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl ML17159A1781998-03-0202 March 1998 Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4. PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998 Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213 ML20216B7031998-02-22022 February 1998 Partially Deleted Ltr Requesting Copy of OI Rept on Plant, Unit 2,case 1-96-039 PLA-4851, Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing1998-02-18018 February 1998 Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing ML20203M5791998-02-10010 February 1998 Enters Appeal Due to Lack of Response to FOIA Request 97-473 ML18030A0971998-02-0202 February 1998 Forwards Proprietary Response to RAI Re Proposed License Amend 209 to TS Supporting Cycle 11 Reload.Proprietary Info Withheld,Per 10CFR2.790 ML20203G6071998-01-26026 January 1998 Forwards Redacted Version of Pp&L,Inc Corporate Auditings Interim Rept 739459-97,dtd 971015 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept IR 05000387/19970031998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 ML18030A4071998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 ML18017A2931998-01-0606 January 1998 Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998 PLA-4828, Expresses Appreciation for Support Received by Former Project Manager C Poslusny1997-12-29029 December 1997 Expresses Appreciation for Support Received by Former Project Manager C Poslusny IR 05000387/19970041997-12-22022 December 1997 Resolves Commitments Made in Response to NOV Issued As Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval ML18026A4901997-12-22022 December 1997 Resolves Commitments Made in Response to NOV Issued as Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval ML20203M5741997-12-0505 December 1997 FOIA Request for Copy of Latest OI Rept on Susquehanna Ses Including All Exhibits & for Any Other Communication Between NRC & Susquehanna Ses/Pp&L PLA-4818, Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept1997-12-0404 December 1997 Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept 1999-09-08
[Table view] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML18040B2701990-01-12012 January 1990 Forwards Radiological Emergency Preparedness Exercise Evaluation Rept:Susquehanna Steam Electric Station, for Exercise on 890222.Several Areas Requiring Corrective Action & Deficiency Noted ML18040A8611987-12-29029 December 1987 Forwards 870429 Final Exercise Rept for Exercise of Offsite Radiological Emergency Preparedness Plans site-specific to Facility.No Deficiencies Identified.Outstanding Deficiency Identified at Last Exercise Corrected ML20236S4061987-11-19019 November 1987 Concurs W/Nrc Determination That Operation & Maint Activities of Plant Would Not Affect Archeological Sites SES-3,6,8 & 11,considered Eligible for Inclusion in Natl Register of Historic Places ML20214M6511986-08-15015 August 1986 Forwards Susquehanna Steam Electric Station Site-Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification, Satisfying Requirements of Rev 1 to NUREG-0654/FEMA-REP-1 & FEMA-43 ML20153D7481986-02-18018 February 1986 Responds to 860130 Request Re Status of Deficiencies Identified at 850501 Offsite Radiological Emergency Preparedness Exercise.Listed Deficiencies Remain Uncorrected.Postponed Remedial Exercise Not Rescheduled ML20087J8521984-03-15015 March 1984 Notifies That State of PA Eligible for Biennial Frequency for Participation in Radiological Emergency Preparedness Exercise.Change from Annual Exercise Requirement Would Be Supported If Requested by Util ML20076L4201983-06-13013 June 1983 Forwards Evaluation Rept of Radiological Emergency Exercise Conducted on 830323.Deficiencies Cited in Four Areas That Will Require Schedule of Corrective Actions.Extension Until End of June to Furnish Schedule Granted ML20063P4651982-10-0404 October 1982 Responds to Inquiry Re Supplemental Interim Findings on Adequacy of Offsite Emergency Preparedness for Facility. State & Local Emergency Plans Adequate.Conditions Should Be Imposed to Assure Completion of Corrective Actions ML20063L2461982-08-31031 August 1982 Forwards Interim Findings on Offsite Emergency Preparedness at Facility.All Deficiencies Noted in Plan Review & Exercise Evaluation Have Been Corrected,Completed or Scheduled for Completion by Early Jan 1983 ML20054M2301982-06-30030 June 1982 Informs That Written School Plans & Detailed Transportation Plans from Surrounding Municipalities,Submitted in Response to Deficiencies Identified by Susquehanna Aslb,Found to Be Adequate ML18030A4971981-07-0101 July 1981 Verifies Official Filing of EIS (NUREG-0564) for Facilities. Fr Notice of Availability Scheduled to Be Published on 810702.Public Review Period Will Terminate on 810803 ML18030A3021981-06-0808 June 1981 Comments on Des.Insufficient Info Provided Re Flood Plains & Hazards.Fes Should Provide Info Re 25,50 & 100-yr Flood Elevations ML18030A2951981-05-28028 May 1981 Provides Comments on Suppl to Des Re Operation of Facilities.Fes Should Include All Risks from Moderate Frequency Accidents,Infrequent Accidents,Limiting Faults & Severe Core Melt Accidents ML18030A5461981-05-27027 May 1981 Ack 810522 Request for Extension Until 810529 for Submittal of Comments on Des ML18030A5451981-05-18018 May 1981 Comments on 810331 Suppl 2 to Des.Final Suppl Should Assess Potential Impacts to Fish & Wildlife Resources from Nuclear Accident.Active Sand & Gravel Pit & Processing Plant within 3-mile Radius of Low Population Zone Should Be Mentioned ML18030A2881981-05-15015 May 1981 Comments on Des Per 810331 Request.Review Consists of EIS Prepared by Other Agencies in Areas of Electric Power, Natural Gas & Oil Pipeline Industries.No Significant Impacts Exist If Action Undertaken ML18026A3561981-05-14014 May 1981 Comments on Des Per 810508 Request.Review Consisted of EIS Prepared by Other Agencies in Areas of Electric Power, Natural Gas & Oil Pipeline Industries.No Significant Impacts Exist If Action Undertaken ML18030A4831981-04-0808 April 1981 Verifies Official Filing of NRC EIS Draft Suppl 2 (NUREG-0564) for Facility.Fr Notice of Availability Scheduled to Be Published on 810410.Public Review Period Will Terminate on 810525 ML18030A1141980-06-10010 June 1980 Responds to NRC Requests for Comments Re Draft Suppl to Draft Eis.Review Indicates Use of Cowanesque Project Currently Under Const Would Provide Better Water Storage than Building New Reservoir ML18030A0051980-05-30030 May 1980 Forwards Comments on Draft Suppl to Draft EIS Re Operation of Facilities,Specifically Pond Hill Creek Reservoir ML18030A1091980-05-29029 May 1980 Comments on Draft Suppl to EIS Re Facility Operation. Provided That Util Implements Mgt Plans in Consultation W/Pa Fish & Game Commissions,No Objections Offered to Const as Proposed ML18030A4991980-05-27027 May 1980 Submits Comments Re Draft EIS Suppl.Statement Displays Good Environ Assessment & Adequately Addresses Areas within Usda Expertise ML18030A1081980-05-27027 May 1980 Submits Comments Re Des Draft Suppl Review.Clean Water Act Conditions & Mgt Practices Re Proposed Dam Encl.Document Should Address Flood Hazard of Spillway Overtopping ML18030A4351980-05-20020 May 1980 Notifies That Bureau of Radiological Health,Fda,Has Reviewed Draft Suppl to DES,NUREG-0564.No Applicable Comments ML18017A1691980-05-13013 May 1980 Forwards NOAA 800429 Comment Re Des.Geodetic Control Survey Monuments May Be Located in Proposed Project Area.Funding for Project Should Include Cost of Any Relocation Required for Monuments ML18017A1551980-04-30030 April 1980 Comments on NUREG-0564, Draft Suppl to Des: Applicant Should More Fully Investigate Water Quality Problems Associated W/Releases & Present Procedures for Ameliorating Them ML18017A1541980-04-28028 April 1980 Notifies That Draft Suppl to Des Re Proposed Const of Pond Hill Creek Storage Reservoir Adequately Addresses Probable Impacts to Highway Facilities.Requests Evidence of Coordination W/State of PA Dept of Transportation ML20064K0301980-04-17017 April 1980 Requests Info Re NRC Involvement in Archeological Data Recovery Activities for FY79 & Forwards Questionnaire ML18031A2591979-09-10010 September 1979 Submits Detailed Comments on Des ML18031A2541979-08-30030 August 1979 Comments on Des.Suggests Effect of Consumptive Withdrawal on Aquatic Habitat During Prolonged Periods of Low Flow Be Addressed & That Monitoring Program Include Plant Intake & Discharge Flows ML18031A2451979-08-20020 August 1979 Comments on Draft Eis.Sediment & Erosion Control Should Be Discussed Re Certain PA State Regulations & Impact on Farm & Agricultural Land Should Be Displayed ML18031A2411979-08-17017 August 1979 Forwards Comments on Des.Document & Proposal Have Been Classified as Environ Rept 2.DES Contains Insufficient Info to Fully Assess Environ Impact ML18031A2391979-08-14014 August 1979 Discusses Des Re Use of 2,4,5-T Weed Control Agent in rights-of-way.Study of Coal & U Fuel Cycles Should Include Indirect Effect of Mining on Landscape ML18031A2321979-08-0909 August 1979 Submits Comments Re Draft Rept.Rept Did Not Discuss Impact on Existing Highways Re Traffic Traveling to & from Plant ML18031A2091979-07-31031 July 1979 Advises That Evaluation of Des Has Been Completed.Offers No Substantive Comments ML18031A1901979-07-11011 July 1979 Provides Requested Info Re federally-proposed or Listed Endangered Species in PA ML18030A4371973-03-0909 March 1973 Responds to NRC 730119 Ltr Re Request for Comments on Draft Eis.Project Does Not Appear to Represent Hazard to Public Health & Safety 1990-01-12
[Table view] |
Text
REGULA TUR INFORMATION DISTRIBUTION 'KM (RIDS)
ACCK'SSION NBR:7909130493 DOC ~ DATE: 79/09/10 NOTARIZED: NO DOCKET FAClL:50-387 Susquehanna Steam Electr ic Station~ Unit l~ Pennsylva 05000387 50-388 Susquehanna Steam Electric Stations Unit Zg Pennsylva 050 AUTH.NAME AUTHOR AFFILIATION
~KIREDTTO>L ~ E ~ InteriOrEUept ~ Of RECIP ~ NAME REC?PIKNT AFFILIATION REGAN g (0 ~
H ~, Envir onmental ProJ ects Branch 2 SUBJECT; Submits detailed comments on CODE: COOZS TITlE:-
COPIES RECEIVEO:LTR KnVir OnsCOmmentS DES'ISTRIBUTION ENCL g SIZEt NOTES: E/i/> Z 4eoMsOwWMM w&W &4'ESAR
< 2WoOMW8eWw 4 ALL R %874' 8 R w W&sQMW~Wa PNWWwW4y&a~WMWwey&WMNN'WwW~WMWMWWNN ~ ~ /CodzauT//@Jr A Wm&MRS wA RECIPIENT COPIES RECIP IENT COPIES ID CODE/NAME LTTR EN L IO COOK/NAME. LTTR ENCL ACTION: 05 PM /'EE'CF/ 17 BC KP~ ~W 18 IA ~/ B'Q AD jl1Oo R~ 1 INTERNAL'1 G 02 NRC POR 07 IFK 09 ENON SPEC BR 10 CST BNFT ANL 11 TA/EOO.
12 AD SITE. TECH 14 ACDENT ANALY 15 EFLT TRT SYS RAD ASST QH 19 DIR DSE AD ENVIRON l'KCH AD SITE ANALY OELD EXTERNAL: 03 LPDR 04 NSIC 20 NATL LAB ACRS L,Ng 4 QJg SEP 14 1979 IvUHBKR OF COPIES REQUIRED: LTTR ~ ENCL ~5 G'OTAL
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United States Department of the Interior OFFICE OF THE SECRETARY WASHINGTON, D.C. 20240 79/632 PEP g 0 1979 Mr. William H. Regan, Jr.
Chief, Environmental Projects Branch 2 Division of Site Safety and Environmental Analysis Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Regan:
The draft environmental statement for- Susquehanna, Steam Electric Station (SSES) Units 1 and 2'as been reviewed by this Department and we have the following comments. The comments are organized by page number. in, the document.
.Pa e 2-28 and Pa e- 4-33 We are concerned that the draft statement does not adequately address archeological and historic concerns. There appears to be.
a need for further investigation of significant properties in the area and identification of their relationship to the project.
This applies to properties already on the National Register and any potential properties in the area but not yet evaluated.
On page 4-33, the draft states that "given the present inadequacies regarding cultural resource inventory and data, the staff cannot make a determination to the effect that the plant's operation will have no adverse effects on cultural resources However, that may be it is eligible for inclusion in the National Register.
unlikely that the plant's operation will affect resources that are currently listed in the National Register (located in excess of 16 km from the plant property) . . ." The draft is unclear regarding the impact the plant and transmission corridors will have on properties close to the project site. Of particular concern are McClintock Hall, the Denison House, ~ and Catlin Hall.
We urge the NRC to undertake a complete archeological and historic survey of the area in accordance with the requirements of 36 CFR 800 and Executive Order 11593. Names of persons qualified to undertake this survey may be obtained by contacting the State P(o@ 0 909> go
Historic Preservation Officer (SHPO} for Pennsylvania, Edward Veintraub, Executive Director, Historical Museum Commission, P.O. Box 1026, Harrisburg, PA 17120. Results of the survey should be included in the final document. Also in consultation with the SHPO the NRC in the survey should, are determine eligible for if any of those properties identified listing in the National Register.
Zf they are determined to be eligible, the procedures and process of 36 CFR 800.4 and 5 must be followed to completion.
~Pa e 3-8 Sulfuric acid will be used to control scale formation. As noted in the statement the system will be operated at a positive satura-tion index to minimize the addition of acid. without this control on acid usage, the discharge could carry over four times the sulfate concentration of the receiving waters. This could aggravate an already stressed situation since the Susquehanna exhibits high and variable sulfate concentrations.
Zn the same manner that alternative levels of acid addition have been discussed, we suggest that alternate methods of scale and corrosion control should be looked at. The final statement should present an environmental evaluation of such methods as organic or hydrochloric acids or mechanical means
~Pa e 4-9 Since the intake structures for this plant have. been constructed, the final statement should discuss what sampling program is proposed and when it would be implemented. to determine levels of entrainment and impingement, during all expected. flow conditions, of Susquehanna River fish and aquatic invertebrates. Further, the final statement should include a discussion of the possible actions the licensees will take to modify the project to protect such aquatic resources in the event significant adverse impacts occur from entrainment, impingement, or streamflow diversion for consumptive use (50 cfs average).
Pa e 4-12 The staff concludes that no adverse environmental impacts, other than atmospheric plumes and snowfall, will occur as a result of the operation of the cooling towers at the SSES. The licensees propose to construct a reservoir (Pond Hill) to provide makeup water during low flow conditions in the Susquehanna River. The final statement should be revised to indicate some adverse environ-mental impact will occur with the operation of the cooling towers
and related reservoir. Construction of the dam and reservoir will destroy terrestrial wildlife habitat and reservoir filling operations will impact Susquehanna River aquatic invertebrate and fish populations through impingement,, entrainment, streamflow regulation, and consumptive use of such flows.
~Pa e 5-2 We agree with the staff that the applicant should monitor groundwater both upgradient and downgradient on a monthly basis. We note that the potential for radionuclide contamination .of groundwater is implied on page D-1 of Appendix D,(item 1.6); however, figure 4.1 (p. 4-13) does not indicate groundwater as an exposure pathway to humans.
~Pa e 6-4 The conclusion that "the environmental risks due to radiological accidents are exceedingly small and need not be. considered further" ignores the probability and the consequences of core-melt accidents
('p. 6-4, par. 1)., As was explained in the environmental statement for the Palo Verde Nuclear Station (NUREG-0522, 1979), this "realistic analysis" is based on procedures in the Proposed Annex to Appendix D, 10 CFR Part 50, which specifically exclude the evaluation of core-melt accidents. Environmental damages resulting from a core-mel't accident can be devastatingly severe and conclusions concerning environmental risks that ignore these accidents must be questioned. We believe that site-specific evaluations of the full range of potential accidents should be a part of the site selection process for nuclear power stations.
The section on Postulated Accidents Involving Radioactive Materials enumerates "Several of the more significant findings" of the Lewis Report (p. 6-3). The three findings summarized exclude the final finding of that report:
There have been instances in which NASH-1400 has been misused as a vehicle to judge the acceptability of reactor risks. In other cases it may have been used prematurely as an estimate of the absolute risk of reactor accidents without full reali-zation of the wide band of uncertainties involved. Such use should be discouraged. (NUREG/CR-0400, p. x).
A footnote to table 6.2 states that "These calculations do not take into consideration the experience gained from the accident at the Three Mile Island site on March 28, 1979" (p. 6-3, footnote A). However, this provides no guidance on the possible magnitude or even the direction of the errors that may exist in the radiological consequences that are shown in the table. The largest
estimated dose to population in a 50-mile radius from any accident shown in the table is 37 man-rem. Until such time as the table can be revised, it might be helpful to note that the estimated dose to the population within a 50-mile radius of the Three Mile Island site was calculated to be 3,300 man-rem (NUREG-0558), p. 2, par. 2).
The populations within that radius are not greatly different for the two sites, being 2,164,000 people in the case of the Three Mile Island site and projected to be 1,517,123 people within 50 miles of Susquehanna Steam Electric Station in the year 1980 (ER, table 2.1-8).
~Pa e B-5 Table B.2 (page B-4) shows that 1,236 acres of forest and farmland will be required as rights-of-way for construction of a new transmission line system. The forested area could be managed if effectively for wildlife preferred vegetation and cover for grazing wildlife species were planted. Their feeding activities would help control revegetation of nuisance woody vegetation and reduce the need for clearing and herbicide applications. We recommend that Appendix B discuss the possibility of using plantings recommended by the Pennsylvania Gaae Commission for. all forested areas cleared during transmission line construction.
We hope these comments will assist the preparation of the final.
neer Lar y E. Meierotto SE CRETARY