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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
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Oscar Stradinger Office Congressional Relations DISCHARGE OF RAD 10ACT!YE EFFLUENT FROM THE MONTICELLO PUWT l We assume that the qvestion regarding discharge of 50,000 gallo'is of I radioactlye 11guld into the Mississippi River refers to an occurrence in 1971. Enclosed is a copy of a report of inspection of that matter.
The report answers both parts of your question. Copies of this report were furnished the Honorable Wendell R. Anderson. Governor of Minnesota, with a letter dated December 17, 1971, and Mr. Ed Tonat. Legislative Assistant to Congressman Joseph Karth, with a letter dated January 18.
1972.-
please let es know if we can be of further assistance.
{
D. F. Knuth. Director Regulatory Operations
Enclosure:
As stated cc: L. M. Nntring L. V. Gossick J. F. O' Leary bec: B. H. Grier, R0:III, w/o encl.
J 9212030563 730817 PDR ADOCK 05000263 0 PDR omcr > ......h0. ETB.. . . . ..... RO - ) .....R0 I . ... . . . . . . . . . . . . . ... . . . . . M19h su= = M.i.99 .am. : c1, ,.CW.. ....mdn ... ,,,, DF,hn.ut, .D,. , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , ,
i om ., . 4/1.Z/73 . BuflZ3....
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.es-a-hus-s s-67s Form AEC-Sl8 (Rev. 9 33) AFCM 0140 I
Enclu ure REPORT rF I1TPTTINT
}tHfrIC EIA D:CiFAit T W 1 rTATION thve-bor 21 - 2% 1971 packground On fioverber 20,1Wl, tir. C. E. Ierson, Cuperintendent of the f6rthern States P:ver C:.epony's Ibnticello Nuclear P:ver Station infor=ed the Division of Conpliance, Ilecion III office, Glen Ellyn, Illinois, by telephone that a planned diccharge of about 10,000 collons of water containir.3 radioactive tuterial had been mde to the l'iccionippi River durina the evening of N:vceber 19,1C/fl. Mr. Larson etntcd that the calculated concentration of radioactivity in the water diccharged to therivervoo745x10-10uci/ml. nio conecntration in leon than 11 of the litit specified in their AID licence for the diccharge of liquid vacte containing unidentified radioicotopes. 11r. Iaroon also stated that he had heard on the nevo media that the 111nneapolis and St. Fmtl vater supply intake gates vould be closed for a period of time becauce of the diccharge, based en the recoczendation of the !!innesota State Health Dcpsrt=ent. Mr. Larson stated that he van informir.g the AEC because of the coverage being given this mtter by the neva cedia.
(The air licence does not require the licensee to notify the AEC of liquid discharges which are planned and vbich have radioactive concen-trations that are belov AID license limits.)
A special inspection was conducted at the Fbnticello rite by inspectors i
from the Region III Ceepliance office during the period of Ibvember 21 i
I through tiover.ber 24 to obtain detailed infor ntion on the discharge of j
liquid vaste from bbnticello. Re inforention voich follovo sum::arizes the findings of the Division of Compliance inspectors baced on their l
selective examiration of recordo and procedures, interviews with plant personnel, and direct observation.
! Inr.pection Tindinas i
l he lbuticello reactor had been shut down on Friday, !bve:ber 12, for l
n planned mintenance period of about three days. As a recult of i eurveillance tents perforned during the first part of this outage, the licensee determined that draining the torus, which normlly contains about 500,000 gallons of water, vas required to permit inopection and l
repair work within the torus. Die necessitated extending the planned
! tainterance period. The major portion of the torus water was transferred to liquid storage space within the plant but the volume of vnter to be stored exceeded the availnble storage capacity by about 50,000 gallona.
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o m er > , , , , , , . , , , , . . . . . , . , ,, , , , , , , , , , , . . . . , _ , , , , , , , , , , , , , , , , , , , , , , , , , ,_ , , , , ,
sunae > . . . . . . . . , , . . . . , , -_ _ , , , , , , , , , , , , , , , , ,
carr > , . . . . . . . . . . . . .
i ,
j '
-t-I 1
i On Friday, November 19, the licensee decided to discharge the excess J
veter to the river.
Procedures for the discharge of the torus water were pretared and approved by the Monticello plant staff. These procedurco required 4 - that t.11 vater being released be proccceed through a Povdex deminer-aliter / filter prior to diccharde. Standard procedures require an analytieni determination of the radioactivity contained in a sample of water to be released prior to its discharge. The procedures 4 followed in dincharging the water from }bnticello were reviewed by the Compliance inspectors and found to be consistent with the plan for handling of liquid vaste described in the Tiral Gafety Analysis Report submitted by the licensee as a part of the application for an AIU operating license.
De initial batch of water dischar6ed frca )tonticello was made up slarast entirely of toruo water and vus released from the plant start-ing at 7:20 p.m. on Friday, !bve ber 19 The licensee's records showed that this batch contained 675h callonn. We licensee analyzed a sample of this batch prior to its diccharge and provided the Minnecota Pollution control Agency with a similar cample for their analysis. A cample was also provided to the Compliance inspectors for indepcodent analycis by the AE. De results of thece sample
- analyses are given in Table I. Pased on the licenece's cample
- analycic, which is consistent with the other analyses, the total radioactivity contained in the initial batch releaned was determined 1
by the licensee to be 132.4 uC1. The concer.tration of this activity after dilution in the water of the discharge canal was calculated by -
the licencee to be 7.45 x 10-10 uCi/ml. These calculations to determine the activity concentration released to the river were reviewed and verified by the Compliance inspectors. The Am license limit on activi-l ,
ty concentration for instantaneous release of unidentified isotopes in liquid vaste, the nest restrictive limit applicable in this case, is 1 x 10'I uC1/mi above background. The activity concentration of the release, therefore, was substantially below the applicable AIC limit.
Subaequent to the discharge of the initini batch of water, the licensee determined that the total activity to be released from the plant would be less if water were diccharged from the fuel storage pool rather than from the torus. De remaining torus water could then be transferred to -
the fuel storage pool to replace the water discharged. A modified i procedure to transfer water from the fuel storage pool for discharge L
to the river was prepared and approved by the licensee. A total of-
, l omce > . . . . . . . . . . . . . . . . . ... c .. . . . . . . . . . . . . . . . . . . .
j mme . . . . . . . . . . . . . . . . . . . . . . ...... . - . . . . . . . . . . . . . ...................... . . . . . . . . . . . . . . ..
i em . . . . . . . .. . . . . . . . . . .. . . . . . . . . . _ . _ . . . _ . . . . . . . . . . . . . . . . . . _ . . . .
.. . - p -
. i .
4 four batches of water from the fuel storage. pool, consistina of 33,636 2 gallons, van discharced during the period from !bycober 21 through
) Nove=bor 24, 1971. The results of cnmple tnalyses for these four batches are (it an in inble I. ne activity concentration in each of these batches
. var. lu.s than in the initial batch.
5 The total volume of voter discharged to the river, excluding normal laundry vaste, durin.3 the period from liovember 19 throuch 16vember 24, 1M1, uns h2,393 gallons containing a total activity of 215 6 uC1.
During the came period, the volums of norm 1 Imundry vante discharged
- urr hSCO gallons of vator containing 1.6 uCi of activity.
?
- 'lec from the diccharge canal campler, which represented a
' taople of diocharge carni vater for the period from !bvember 15 r.ber 22, 1971, vere obtained. These camples were analyzed by the lia " , the Minnecota Ivilution Agency, and the AEC. W e results of
+h" ; .aalynss reported in uCi/ml vere as follows:
j MP MV- ATX!
I Grofs gacma 4.3 x 10'9 5 6 x 10-9 NA i Oross beta 6.8 x 10'9 9 0 x 10-9 1.6 x 10~0 H-3 2 x 10-6 gg (axyo-6 Canana isotopic MA NA all(1 x 10 4 NA - r.ot anal,yzed Dese recults are nsted to be in the range of the natural ~ background acti <ig in }!ississippi River water.
4 Conclusion No items of te, .: ompliance with N ' requiremonta vere observed to have cccurred within .ne scope of the Avesber 21-24 inspection at tbuticello.
J i
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su. mar > .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,, . , , , , , , , , , , , _
l _ ._
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r TABLE I i
LIQUID RELEASES FilC:I ICITTICELLo ICJCLEAR ICWER STATION ;
IFMER 19 - 24,157/1 Entch ! ,
No./Dato Results of Cample fnalysis
- Ecurce ActivityConcentration(uC1/ml) Total Datch -
V.,1 u -- USP MPCA AFU Activity ; ,
966/n/19 Torus Vater cross caem cross Beta 4.0 x 10-6 3 3 x lo-6 h.1 x 10-6 m
NA 3 3 x 10-6 132.4 uCi l ll. j ,
8754 sal. H-3 m m 1 74 x .'.0-3 :
I-131 3.4 x 10-6 3 7 x lo-6 2 3 x 10-6 : : j 1 co-58 6.0 x 10-7 4.2 x 10-7 6 3 x 10-7 i cs-137 nA NA 1 3 x 177 : -
co-60 NA M 2.4 x 10-7 i E 974/n/21 cross cat =a 8.75 x 10-7 1.04 x lo-6 NA 27 8 uCi ;ij l 72 x 10-7 Ibel Ibol Vater crocs Beta NA 1.6 x 10-6 . t Sho9 Sal. 1-131 7.88 x 10-7 8.2 x 10-7 5.o x 10-7 .
I Co-58 8 75 x 10-8 2.2 x 10-7 1 3 x 10-7 !
j H-3 NA E 1 33 x 10-3 .x Ie-133 m n 2 7 x 10-6 ; ,,
t =
978/n/22 crosa camm 3 84 x 10-7 4.8 x 10-7 n 12.2 uCi ,
Ibel Pool Vater Crocs Beta a.5 x 10-7 NA 1.0 x 10-6 ;
8409 gal. I-131 3.84 x 10-7 k.8 x 10-7 1 5 x 10-7 .
Co-53 IM RA 7 7 x 10-8 .'
H-3 E UA 1 3 x 10-3 :
Xc-133 NA KA 1 3 x 104 . 5 x
987/n/23 cross cocma 1.07 x 10-6 9 9 x lo-T KA 34.0 uCi y Ebel Pool Water orosa Beta NA NA E .
i E4c9 gal. 1-131 8.8 x 10-7 9 4 x 10-7 nA , , , @
Co-58 1 9 x 10-7 5 0 x 10-8 nr y yg3 g aa :
.' 992/11/24 crocs cac:s 2.89 x 10-7 2 7 x 10-7 Pbel 15o1 Water I-131 NA 9 2 uCi b 2.89 x lo-7 2 7 x 10-7 NA 4 8409 E31. E l 2
. UA - f'ot aralyzed
. J'
_ . . _ _ .