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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212H2031999-09-27027 September 1999 Forwards Operator Licensing Exams Administered at Monticello Nuclear Generating Plant During Wk of 990823.Encl Consists of Facility Submitted Outline & Initial Exam Submittal ML20216G4221999-09-27027 September 1999 Forwards NRC Operator Licensing Exam Rept 50-263/99-301 (Including Completed & Graded Tests) for Tests Administered During Wk of 990823 at Monticello Nuclear Generating Plant ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20202H6671999-02-0101 February 1999 Notification of 990223 Meeting with Util in Rockville,Md to Discuss Need for TR on Util Analytical Methods Used for Other NRC Licensees,Epri Schedule for Completion of CPM3/ Coretran Analysis Topical & Util Transition Plan ML20202H6321999-02-0101 February 1999 Notification of 990224 Meeting with Util in Rockville,Md to Discuss Implications of Util Recently Extended Commitment for Plant ITS Submittal,Nrc Initiative Toward risk-informed TSs & Interfacing ITS Conversion with Other Activities ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20206S6521998-08-18018 August 1998 Informs That During 980708-10 ACRS 454th Meeting,Several Matters Were Discussed & Listed Repts & Letters Completed. Executive Director Also Authorized to Transmit Noted Memos ML20236U7851998-07-24024 July 1998 Informs That During 453rd & 454th Meetings of ACRS on 980603-05 & 0708-10,NRC Reviewed GE Nuclear Energy Program Associated W/Extended Power Uprates for Operating BWRs & Application for NSP for Power Level Increase for MNGP NUREG-1635, Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr1998-07-0707 July 1998 Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr ML20249A8041998-06-15015 June 1998 Notification of 980630 Meeting W/Util in Rockville,Md to Discuss Issues Related to Conversion to Improved Std TSs for Monticello Nuclear Generating Plant ML20248D7081998-05-26026 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend Supporting Monticello Power Uprate Program ML20216C3931998-05-11011 May 1998 Notification of 980521 Meeting W/Northern States Power Co & GE in Rockville,Md to Discuss Status of Staff Review of Proposed Power Uprate Program for Plant ML20217F2561998-03-20020 March 1998 Notification of 980330 Meeting W/Util to Discuss Licensee Response to Staff Request for Addl Info on Licensee Uprate Program.Meeting Will Be Held in Rockville,Md ML20198Q1881998-01-13013 January 1998 Forwards Nonproprietary Version of Montecello & Cooper Trip Rept to PDR ML20198N0251998-01-12012 January 1998 Discusses 971215-16 NRR Audit of Monticello Strainer Test. Tests Were Established to Develop Data for Strainer Design Installed in NPP ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20216F9711997-09-0505 September 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Current Issues Re Environ Qualification of Equipment at Plant ML20210T1371997-09-0303 September 1997 Notification of 970910 Meeting W/Ge & Southern Co in Rockville,Md to Discuss Status of Boiling Water Reactor Power Uprate Program ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20129B6031996-10-18018 October 1996 Notification of 961105 Meeting W/Util in Rockville,Md to Discuss Contents of NSP License Amend Request Supporting Plant Power Upgrade Program NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20059H5891994-01-24024 January 1994 Notification of 940202 Meeting W/Util in Rockville,Md to Discuss Plans for Implementation of Rwl Mod as Required by NRC Bulletin 93-003 ML20057B4721993-09-15015 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Installation of Water Level Monitoring Instrumentation at Plant ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20127K6681992-11-20020 November 1992 Undated Memo Discussing Status of Field Erected Reactor Vessel Fabrication Review ML20055D5791990-06-27027 June 1990 Requests Position on Allowability of Radios or Tape Players in Control Room of Nonpower Reactors ML20155G7431988-06-0707 June 1988 Forwards F Miraglia 880527 Memo for Review & Requests Proposed Priorities for Actions on Project Manager Rept by C.O.B. 880609 ML20154Q1661988-05-27027 May 1988 Discusses Updating Project Managers Rept (Pmr) in Accordance W/New Priority Ranking Sys.Mods Have Been Made So That Pmr Will Now Accept New Priority Data.Old Priority Data Will Be Deleted During Wk of 880530.Sample Data Format Encl ML20148A7571988-03-14014 March 1988 Forwards Project Directorate III-1 Slides for 880317 Briefing of Executive Team.Slides Marked P Primary Slides Directorate Plans to Show.Other Slides Backup for Possible Ref ML20236P7451987-11-13013 November 1987 Reviews Latest Performance Indicators to Determine Whether Indicators Can Be Used to Ascertain Quality Performance.Five of Six Plants Achieving Very Good Quality Performance While One Plant Achieving Good Quality Performance ML20211N7961987-02-19019 February 1987 Requests Consideration of Encl Util 861223 Request That 860228 Application for Extension of Duration of Licenses DPR-57 & NPF-5 Be Given Higher Review Priority.Util Requests Completion of Review by 870331 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20210T3791986-10-0202 October 1986 Notification of 861017 Meeting W/Utils in Bethesda,Md to Discuss Issues Affecting Operating Reactors & NRC ML20211N8311986-10-0101 October 1986 Proposes Listed Schedule for Completion of Reviews of OLs Extensions for Listed Facilities Based on Low Priority of Effort.Plant Sys Branch Will Coordinate Responses & Recipients Will Be Provided W/Integrated Plant SERs ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20211E5131986-06-0606 June 1986 Discusses Inputs for SALP 6 Assessment for Dec 1984 - Mar 1986,due on 860618.Inputs Should Be Typed on 5520 Sys & Remain on Sys Until SALP Board Meeting Held.Listing of Insps Conducted During Assessment Period Encl ML20155F1941986-04-10010 April 1986 Summarizes Operating Reactor Events Meeting 86-11 on 860407 Re Events Since 860331.List of Attendees,Discussion of Events,Status of Assignments & Assigned Completion Dates for Items Encl.Response Requested for Incomplete Assignments ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20198G2001985-11-0505 November 1985 Recommends Issuance of IE Info Notice Re Possible LOCA at High/Low Pressure Interface After Fire Damage Occurs in Control Room.Problem Discovered During Fire Protection re-review ML20087A8311984-03-0505 March 1984 Forwards Monticello Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Evaluation & Monticello Nuclear Power Plant Full-Scale Joint Emergency Exercise on 830223, Final Rept ML20207L3491983-11-30030 November 1983 Advises That Scheme Described in Licensee 830929 Request for Extension of Date for Complying w/10CFR50.54 Unsatisfactory. Mods May Result in Shift Supervisor Spending Less Time in Control room.Davis-Besse Proposal Also Unacceptable ML20058G6051982-07-13013 July 1982 Forwards Draft Ltr Clarifying Confusion During LANL 820706-09 Site Visit to Collect Data for Vital Area Analysis Program.Concerns Re Releasing of Data Resolved.Future Visits Will Be Endowed W/Official Imprimatur ML20148F1051978-10-24024 October 1978 Forwards Memos Re Recent Problems in Pipe Support Base Plate design.(ANO:7811020332,7811020336, & 7811020343.) ML20148G2271978-10-24024 October 1978 Forwards 780929 Memo Re Results of Recent Fire Protec Res Test Conducted at Underwriters Lab. (See ANO: 7810050359, 7810050373.) ML20125A4051978-09-0101 September 1978 Responds to Bajwa 780831 Request for Review of Nonradiological Ets.Several Critical Inconsistencies Still Exist Between Fes Findings & ETS 1999-09-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212H2031999-09-27027 September 1999 Forwards Operator Licensing Exams Administered at Monticello Nuclear Generating Plant During Wk of 990823.Encl Consists of Facility Submitted Outline & Initial Exam Submittal ML20216G4221999-09-27027 September 1999 Forwards NRC Operator Licensing Exam Rept 50-263/99-301 (Including Completed & Graded Tests) for Tests Administered During Wk of 990823 at Monticello Nuclear Generating Plant ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20202H6321999-02-0101 February 1999 Notification of 990224 Meeting with Util in Rockville,Md to Discuss Implications of Util Recently Extended Commitment for Plant ITS Submittal,Nrc Initiative Toward risk-informed TSs & Interfacing ITS Conversion with Other Activities ML20202H6671999-02-0101 February 1999 Notification of 990223 Meeting with Util in Rockville,Md to Discuss Need for TR on Util Analytical Methods Used for Other NRC Licensees,Epri Schedule for Completion of CPM3/ Coretran Analysis Topical & Util Transition Plan ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20206S6521998-08-18018 August 1998 Informs That During 980708-10 ACRS 454th Meeting,Several Matters Were Discussed & Listed Repts & Letters Completed. Executive Director Also Authorized to Transmit Noted Memos ML20236U7851998-07-24024 July 1998 Informs That During 453rd & 454th Meetings of ACRS on 980603-05 & 0708-10,NRC Reviewed GE Nuclear Energy Program Associated W/Extended Power Uprates for Operating BWRs & Application for NSP for Power Level Increase for MNGP NUREG-1635, Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr1998-07-0707 July 1998 Informs That During 453rd Meeting on 980603-05,ACRS Discussed Several Matters & Completed Listed Repts & Ltr ML20249A8041998-06-15015 June 1998 Notification of 980630 Meeting W/Util in Rockville,Md to Discuss Issues Related to Conversion to Improved Std TSs for Monticello Nuclear Generating Plant ML20248D7081998-05-26026 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend Supporting Monticello Power Uprate Program ML20216C3931998-05-11011 May 1998 Notification of 980521 Meeting W/Northern States Power Co & GE in Rockville,Md to Discuss Status of Staff Review of Proposed Power Uprate Program for Plant ML20217F2561998-03-20020 March 1998 Notification of 980330 Meeting W/Util to Discuss Licensee Response to Staff Request for Addl Info on Licensee Uprate Program.Meeting Will Be Held in Rockville,Md ML20198Q1881998-01-13013 January 1998 Forwards Nonproprietary Version of Montecello & Cooper Trip Rept to PDR ML20198N0251998-01-12012 January 1998 Discusses 971215-16 NRR Audit of Monticello Strainer Test. Tests Were Established to Develop Data for Strainer Design Installed in NPP ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20216F9711997-09-0505 September 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Current Issues Re Environ Qualification of Equipment at Plant ML20210T1371997-09-0303 September 1997 Notification of 970910 Meeting W/Ge & Southern Co in Rockville,Md to Discuss Status of Boiling Water Reactor Power Uprate Program ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20129B6031996-10-18018 October 1996 Notification of 961105 Meeting W/Util in Rockville,Md to Discuss Contents of NSP License Amend Request Supporting Plant Power Upgrade Program NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20059H5891994-01-24024 January 1994 Notification of 940202 Meeting W/Util in Rockville,Md to Discuss Plans for Implementation of Rwl Mod as Required by NRC Bulletin 93-003 ML20057B4721993-09-15015 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Installation of Water Level Monitoring Instrumentation at Plant ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20127K6681992-11-20020 November 1992 Undated Memo Discussing Status of Field Erected Reactor Vessel Fabrication Review ML20055D5791990-06-27027 June 1990 Requests Position on Allowability of Radios or Tape Players in Control Room of Nonpower Reactors ML20155G7431988-06-0707 June 1988 Forwards F Miraglia 880527 Memo for Review & Requests Proposed Priorities for Actions on Project Manager Rept by C.O.B. 880609 ML20154Q1661988-05-27027 May 1988 Discusses Updating Project Managers Rept (Pmr) in Accordance W/New Priority Ranking Sys.Mods Have Been Made So That Pmr Will Now Accept New Priority Data.Old Priority Data Will Be Deleted During Wk of 880530.Sample Data Format Encl ML20148A7571988-03-14014 March 1988 Forwards Project Directorate III-1 Slides for 880317 Briefing of Executive Team.Slides Marked P Primary Slides Directorate Plans to Show.Other Slides Backup for Possible Ref ML20236P7451987-11-13013 November 1987 Reviews Latest Performance Indicators to Determine Whether Indicators Can Be Used to Ascertain Quality Performance.Five of Six Plants Achieving Very Good Quality Performance While One Plant Achieving Good Quality Performance ML20215L3101987-05-0707 May 1987 Staff Requirements Memo Re Commission 870430 Affirmation/ Discussion & Vote in Washington,Dc on SECY-87-68A Concerning Order to Rescind 861020 Order Directing Licensee to Show Why OL Should Not Be Modified.Order Signed on 870501 ML20211N7961987-02-19019 February 1987 Requests Consideration of Encl Util 861223 Request That 860228 Application for Extension of Duration of Licenses DPR-57 & NPF-5 Be Given Higher Review Priority.Util Requests Completion of Review by 870331 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20210T3791986-10-0202 October 1986 Notification of 861017 Meeting W/Utils in Bethesda,Md to Discuss Issues Affecting Operating Reactors & NRC ML20211N8311986-10-0101 October 1986 Proposes Listed Schedule for Completion of Reviews of OLs Extensions for Listed Facilities Based on Low Priority of Effort.Plant Sys Branch Will Coordinate Responses & Recipients Will Be Provided W/Integrated Plant SERs ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20211E5131986-06-0606 June 1986 Discusses Inputs for SALP 6 Assessment for Dec 1984 - Mar 1986,due on 860618.Inputs Should Be Typed on 5520 Sys & Remain on Sys Until SALP Board Meeting Held.Listing of Insps Conducted During Assessment Period Encl ML20155F1941986-04-10010 April 1986 Summarizes Operating Reactor Events Meeting 86-11 on 860407 Re Events Since 860331.List of Attendees,Discussion of Events,Status of Assignments & Assigned Completion Dates for Items Encl.Response Requested for Incomplete Assignments ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20198G2001985-11-0505 November 1985 Recommends Issuance of IE Info Notice Re Possible LOCA at High/Low Pressure Interface After Fire Damage Occurs in Control Room.Problem Discovered During Fire Protection re-review ML20087A8311984-03-0505 March 1984 Forwards Monticello Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Evaluation & Monticello Nuclear Power Plant Full-Scale Joint Emergency Exercise on 830223, Final Rept ML20207L3491983-11-30030 November 1983 Advises That Scheme Described in Licensee 830929 Request for Extension of Date for Complying w/10CFR50.54 Unsatisfactory. Mods May Result in Shift Supervisor Spending Less Time in Control room.Davis-Besse Proposal Also Unacceptable ML20058G6051982-07-13013 July 1982 Forwards Draft Ltr Clarifying Confusion During LANL 820706-09 Site Visit to Collect Data for Vital Area Analysis Program.Concerns Re Releasing of Data Resolved.Future Visits Will Be Endowed W/Official Imprimatur ML20148F1051978-10-24024 October 1978 Forwards Memos Re Recent Problems in Pipe Support Base Plate design.(ANO:7811020332,7811020336, & 7811020343.) ML20148G2271978-10-24024 October 1978 Forwards 780929 Memo Re Results of Recent Fire Protec Res Test Conducted at Underwriters Lab. (See ANO: 7810050359, 7810050373.) 1999-09-27
[Table view] |
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JUI.13 1978 MEMORANDUM FOR: Voss A. Moore, Jr., Assistant Director for Environmental Projects, DSE , x FROM: Brian K. Grimes, Assistant Director for Engineering and Projects, DDR
SUBJECT:
PROPOSED EINIRONMENTAL TECHNICAL SPECIFICATIONS FOR MONTICELLO NUCLEAR GENERATING PLANT PLANT NAME: Monticello Nuclear Generating Plant DOCKET NUMBER: S0-263 RESPONSIBLE BRA.'4CHES: EP-1; ESB; ORD-3 DSE PROJECT MANAGER: S. Bajwa D0R PROJECT MANAGER: R. Bevan TAC NUMBER: 7587 We have reviewed the proposed Monticello non-radiological environmental technical specifications (ETS) and have found that they are inconsistent with the FES findings in several important areas. While it is not neces-sary that the two be consistent, it is necessary that the inconsistencies be evaluated as to envir9nmental impact and the conclusion reached that the findings of the FES are not invalidated by the changes. This evaluation and conclusion should be prepared as an Environmental Impact Appraisal (EIA) supporting the proposed ETS. We cannot make a judgment on the ecceptability of these ETS and, in particular, the inconsistencies without having the EIA.
We rec, rt that an EIA be prepared and circulated for technical review with the 1 ' -
aaft ETS.
In w m 'y and conclusions section of the FES, requirements are recom-men < - "N incorr a ted in the license for t',e protection of the environ-ment. N voposed ETS do not adopt these recommendations. Furthermore, our r % w -
the licensee's annual reports indicated that the licensee's monito W vrograms generally did not address these areas; thus, implementa-tion of appropriate monitoring programs,as suggestc4 in the FES, may be needed before final conclusions can be drawn. Under a contract from NRC, Battelle-Pacific Northwest Laboratory (PHL) reviewed the licensee's annual reports and found many significant problems with their monitoring programs which support.s our finding that it may not be feasible to do an adequate impact appraisal with the information available to justify some of the in-consistencies between the proposed ETS and the FES. Some of these incon m _
sistencies, however, may be justifiable from a generic standpoint as the W[C Conte::t: W. Pasciak, EEB/00R
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l state-of-the-art of impact prediction has greatly improved since the FES ,
was originally written. A thorough review and environmental analysis should '
! be made to determine exactly which areas may require further monitoring, and these monitoring programs shculd be included in the draft ETS. 3 g; Enclosure 1 outlines specific areas of the FES that should be addressed in j the environmental impact appraisal, along with a discussion of problems that are likely to be encountered in doing these appraisals. We will coordinate-
- with DSE in this evaluation as necescary. ,.
, y ,
In addition to assuring we are discharging our NEPA responsibilities, we are concerned that failure to follow up on FES recorsnendations could make us vulnerable in any hearing situation associated with the FTOL issuance.
/s/
Brian K. Grimes Assistant Director for Engineering and Projects Division of Operating Reactors
Enclosure:
As stated w
cc: V. Stello
- h. DISTRIBUTION:
, ehut g on E. Adensan Central Files T. Cain EEB/ Reading R. Ballard B. Grimes G. Lear ll. Pasciak R. Samworth l H. Berkson l J. Lehr e R. Reid -
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- s RETYPED PER B. GRIMES - SEE ATTACHED YELLOW FOR PREVIOUS CONCUP,RENCES *
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2 MEMORMIDUM FOR:
Voss A. Moore, Jr., Assistant Directo for Environmental Projects, DSE FROM: Brian K. Grimes. Assistant Direct for Engineering and Pmjects, DOR '-
SUBJECT:
PROPOSED ENVIRONMENTAL TECHNI SPECIFICATIONS FOR MONTICELLO NUCLEAR GENERATIN PLANTt PLANT NAME: Montice lo Nuclear Generating P ant DOCKET NO.: S0-263 RESPONSIBLE BRANCHES:\{P-1; ESB; ORB-3 DSE PROJECT MANAGER: S.\Bajwa DDR PROJECT MANAGER: R.Kevan TAC N0.: 7587 \
. N We have reviewed the proposed hontic llo non-radiological environmental technical specifications (ETS) And fave found that they are inconsistent with the FES findings in severa1\i$portant areas. While it is not neces-sary that the two be consistent, y is necessary that the inconsistencies be evaluated as to environmental imRact and the conclusion reached that the findings of the FES are not inya idalgd by the changes. This evaluation and conclusion should be prepar d as an Environmental Impact Appraisal (EIA) supporting the proposed ETS. t is imphssible to make a judgment c4 the ac-ceptability of these ETS and, in particubr, the inconsistences without hav-ing the EIA to review. We uest that ad EIA be prepared and circulated for technical review with the la est draft ETS.
In the summary and conclus%ns section of the ES, requirements are recom-mendedtobeincorporated/nthelicensefort protection of the environ-ment. The proposed ETS d not adopt these rec ndations. Furthennore, our review of the licens 's annual reports indi ted that the licensee's monitoring programs gen ally did not address thes areas; thus, it may be impossible to do an acc ptable evaluation in these eas without implementing appropriate monitoring programs as suggested in the S. Under a contract from NRC, Battelle-Pa ific Northwest Laboratory (PNL) viewed the licensee's '
annual reports and f nd many significant problems with . heir monitoring pro- ,
grams which supports our finding that it may be impossib? to do an adequate impact appraisal wi the information available to justif some of the incon-sistencies between he proposed ETS and the FES. Some of t ese inconsisten-cies, however, may justifiable from a generic standpoint s the state-of-the-art of impact rediction has greatly improved since the FtS was originally written. A thorough review and environmental analysis should be made to
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determine exactly which eas may require furthe monitoring, and these monitoring programs should' e included in the/draf t ETS.
! Enclosure 1 outlines specific reas of t ES that'should be addressed in -
- the environmental impact appraital, alo with a discussion of problems that are likely to be encountered in d ng these appraisals. We will co-l ordinate with DSE in this evaluati n s necessary. . ; ;, ;j 4 <
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, 2 e r\ ,
'c f' l Bria~ K. Grimes Assistant Director for ngineering and Projects Divisio of Operating Reactors j'
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1
Enclosure:
As stated ,
, cc: V. Stello 1
D. Eisenhut s ,
,' O. Knighton DISTRIBUTION:
t-E. Adensam N T. Cain CentralTiles i R. Dallard EEB Reading G. Lear B. Grimes \
R. Samworth , ' W. Pasciak H. Berkson J. Lehr V. Moore /
S. Bajwa S. Lewis'(0 ELD)
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j Enclosure 1 i
i Items that should be discussed in an Environmental Impact Appraisal Supporting Issuance of FTOL for Monticello Nuclear Generating Plant In the Sumary and Conclusions section of the FES, p. iii, Item No. 7, it states that "after weighing the environmental, economic, technical and other benefits of the Monticello Nuclear Generating Plant against environmental costs and considering available alternatives, it is concluded that the action i called for is conversion of the provisional operating license to a full term operating license for the facility subject to the following conditions for pro-tection of the environment." These five conditions are listed below along with j comments as to how they should be handled in the environmental impact, appraisal.
7 (a) "The Applicant shall operate the plant in such a manner that the maxi-mum temperature of the river, as a result of plant operation, does not exceed 90*F over more than one-half the surface width of the river at any time." The a
NPDES Permit allows discharges during April through October cf 95 F. The ap-l praisal must either assure that this 95 F discharge limit will not cause the 90*F FES limit to be exceeded, perhaps through a hydrologic evaluation, or must de-
- scribe the impact that will occur with the 95 F limit, and show that it is either insignificant or show that it does not change _the cost-benefit analysis. Our brief review of the annual reports indicated that the licensee did not_ perform a study addressing this question. It appeared that most of the monitoring tran-sects were located too far downstream to answer this question. Furthermore, the model they developed is apparently inadequate. Battelle-Pacific Northwest Laboratory reviewed it* (p. 60) and concluded that "in general, the model predic-tions are not representative of the river surface therma} distribution." If an f.
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, - 2-j j appropriate analysis cannot be made addressing this question, whether by i means of the hydrologic approach, modeling approach, or some other approach, i
- a monitoring program should be included in the ETS to obtain the necessary' i
i information and, as in the handling of Oyster Creek ETS, LCOs should be im-4
! posed in this area.
l l 7(b) "The Applicant shall obtain data to ascertain whether or not corrective i
action need be taken to reduce the possible loss of biota due to the intake j structure." We have reviewed the licensee's results and discussions in the l annual reports. While it appears that there are enough data available on' fish =
impingement, the licensee did not compare these data to information on fish populations and fishing catch results to ascertain whether the impact levels are acceptable. Such a comparison is an important part of answering this
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- question and should be part of the environmental impact appraisal. If the I
historical impingement rate is not acceptable from the impact standpoint when
! projected into the future, modifications to the proposed ETS should be made i
l as appropriate. If further monitoring were required as a result of high pre-dicted impact, data from other river-located plants may help in designing a l
monitoring program.
7(c) " Planned plant shutdowns shall b programmed such that the rate-of water
! temperature reduction will not'cause excessive fish kills-in the-discharge-canal." The NPDES-Permit does not have a limit on rate of temperature change of discharge water. In such cases, it is current practice to-impose such a condition as an LCO,-or, by means of the evaluation to show that such a l
limit is not necessary and that this conclusion of the FES is no longer valid, i ll R
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t We have briefly reviewed the licensee's annual reports in this area and have i .
j found that they do not specifically address this question, nor may the data j be available in them to do so. In the Battelle-Pacific Northwest Laboratory i
review of the licensee's data * (p. 121),~they stated that "the river popula-
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i l tion estimates .... are both poor and inappropriate (displaced too far in time) to use as an aid in estimating cold shock effects. Thus, it appears that some i
j further action by NRC is necessary in this area. The available data should be reviewed and this review should be included in the environmental impact l appraisal along with the basis supporting the proposed action. Imposing'LCOs i along with a monitoring program may be the appropriate action in this' area, i
! 7(d) "The Applicant shall define a comprehensive environmental- monitoring i
program for inclusion in the Technical Specifications which are. acceptable to the Staff for determining environmental effects'of plant operation."
Batte11.e-Pacific Northwest Laboratory reviewed this report
- and concluded j that (p. 53), in general, the impacts predicted in the Environmental State-ment have not been verified by the data collected fromfthe monitoring prograins.
4 They also stated that "If more consideration was given Lto a sampling design.
that is statistically oriented. ... then answe'rs to-predicted FES impacts could possibly be attained through'a highly quantitative Environmental Techni-cal Specification." The Battelle study was completed in November 1976 so
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data from the last few. years of monitoring were not reviewed. The basis for
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.their conclusions should. be addressed in the appraisal. .As the licensee's analysis =does not verify the FES findings, an analysis should be provided with the. appraisal which does. or appropriate montioring. programs should be included; in the FES. '
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7(e) "If other harmful effects or evidence of irreversible damage are de-4 tected by the monitoring programs, the Applicant will provide an analysis of the problem and a proposed course of action to alleviate the problem."
The monitoring programs in the proposed ETS should be evaluated to deter-mine whether they are adequate to detect such effects. Our review of them indicates that the proposed programs may be inadequate for this purpose.
, The appraisal should describe the areas for which the monitoring is ade-quate to detect possible irreversible damage caused by plant operation, and areas where the monitoring programs should be improved to provide a minimum level of monitoring in ar'eas where possible irreversible damage may occur in the distant future.
In addition to these conditions described in the summary and conclusions, 1
there are recommendations made throughout the FES. Those which are not being implemented through the proposed ETS program should be discussed in the EIA and bases for their omission should be presented, t
4 Evaluation of Monticello Nuclear Power Plant, Environmental Impact Pre-dictions, Based on Monitoring Progrars. Battelle-Pacific Northwest Laboratories, November 1976. BNWL-2150.
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