|
---|
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] |
Text
._- . . _ _ _ . . . . - _ _ _ _ _ - . _ - - _. .. - - - - _ - _ .
~
( ( i
(
DISTRIBUTION:
, Docke t Tile w - - :/
DRL Reading l Branch Reading D. J. Skovholt i
-""""" ~
D. L. Ziemann (file)
F. Anderson Domenic B. Vassallo Reactor Project Branch #1 Division of Reactor Licensing TERU Dennis L. Eiemann, Chief Operating tasctor Branch f2, DEL TECHNICAL SPECIFICATIONS FOR RAD 10&CTIVE EFTLUENts (SECTION 3.6) -
NONTICELLO NUCLEAR GENERATING PLANT (UNIT NO. t)
During my regiou of the proposed teshaiset specifiestion for radio-active effluents of the subjoet nucisar plant, some inconsistencies appeared to be present between the specifications en plant stack of-fluents and 10 CFR 20 reguistions. To starify my evaluaties of the proposed specifications, I have prepared a step-by-step analysis of the subject specification and bases with the applisable section(s) of 10 CFR 20. I have discussed the following senserns with Dr. Ferrest Western, RFS, and I. 8pickler, RESTS, DRL. It is my understanding af ter discussing these concerns with 1. Spickler and V. Stelle, RFB #1, DRL, that other BWR plants since Oyster Creek Nuclear Generating Flant (Unit No.1) may have the same proposed technical specificaties for radioactive affluents.
In the following analysis, I have only addressed my comments to the plant stack effluents and the off-gas system as it may relate to normal plant operation. The related consequences resulting from minor accidents should also be reviewed in establishing appropriate specifications for radioactive affluent release limits, i.e., Limiting Conditions for Operation and Limiting Safety System Settings. -
Specification - Section 3.6 - Radioactive Effluents A.1.a. The annual average sentinuous release rate of radioactivity, except halogens and particulates with a half-life greater than 8 days, shall not exceed 0.48 Ci/sec.
Discueston ..
The above limit is based upon a time-averaging analysis of the site for a typical year of meteorological senditions. The limit value seuld result in a whole body dose of 500 area in a given sector and givea
/
ur ,-ex m c r ~~
m m m .z w=w- e' .
9212030662 690218 PDR ADOCK 05000263 A PDR
. ._, - . - - - . - - -- - -- - --- -- -- ' ~ ^~
}
.t.
distance off-site which receives the highest radienstive afflueet eencontratten during a year, the gustity of the radioactive effluent misture would sessist asialy of the noble gases (Ar and Es) and activa.
tien gases and would auslude 1 131 speettiaally and prehably the rematador of the halesens (9s, I and tr).
It is my maderstanding that an analyets by DEL using a sta11er saleuta-tiemal method might result is a redustiam of the proposed limit by a facter of 2,1.s., 0.1 to 0.3 01/ses, for the sans osadittees.
N hases for the limit as derived sente be found in 10 0FR 20, testies 20.196, paragraph (b)(2) if paragraph (b)(1) has been antisfied. I eaanet find where paragraph (b)(1) has been satisfied by the app 1&oast, i.e., "a reassemble effort to minimise the radiomativity in affluents to unrestricted areas".
b limit which would be determined to satisfy the primary regulation J' for effluents, i.e.,10 CFR 20, testies 30.106, paragraph (a), would ;
he approniastely a faster of 10 less than the proposed limit er 0.04 ~
to 0.05 C1/ses escording to BEL analysis of other sites. Asserding to the applicant, the seraal steek emissies este would be less than 0.002 C1/ses or a faster of t0 less than the unlimited release rete to satisfy 10 CFR 20, Sestica 20.106, paragraph (a).
If the applisant requests the propeeed limit for additional operettomal freedom above and beyond that provided by the primary regulation of 10 CFR 20, we might propose that ha make a reassemble effort to minimise the release equivalent to the faster gained by the ps:;:::f ' g' limit. For the quality et the radiomative affluent misture presented by the applicant, a decay period of approminately a bours La the off-gas :-
system prior to stack release would provide a redestion faster of appreminately 10 La the mermal steek emission rate. -
A.1.b. h release rate of radiomativity, easept halogens and partion. " M.
lates with a half life greater than a days, shall not easeed 0.31 01/see for a persed in essess of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> la any seven eenseestive days. ,c?
piacussina
}..
h h above limit is based open astnerelegiaal seeditions of 1 m/ses wind speed during equal periods of stable end unstable condittees q
-m
for the 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and could result in a maximum whole body dose of 100 area off site la the 38W sector. To satisfy the requirement stated by the applicant, i.e., the limit would result in less than 100 mrom whole body dose in any seven day ported, addittomal releases from the steek durias the rematador of the seven days (148 heers) could met be allowed into the gives oestet. k applicant assumes that the quality of the radionettre effinent misture will remata the same as need for the annual average seatinuous relenos rate.
h bases for the limit as derived by the applicant does met estet ta any applisable seetism of it WR 20. b appiteant ases Seeties 20.105 paragraph (b)(3) of 10 CFR 20 as the bases for the limit but this sostion refers to permissible levels of radiation la unrestricted areas met effluent levels. Also, the intent of the referested seatica as discussed with Dr. Westorm was for intermittant operation of s u k equipment as a ray machines, limmer ascelerators and possibly high radiation level sources. h continueue escupancy term was used as describing an area such as a hallway, a sidewalk er an area naar the equipment in use which might be esempted by usunomitered individuals and was met construed to indicate residency or individuals living to permanent quarters off= site. brefore, the use of this section of 10 CFR 20 as a bases for the proposed limit is met justified.
Although a specific regulation is met available as a bases for an upper release limit as proposed, the intent of such a specifisation appears to be reasonable and prudent. As discussed with Dr. Western, the upper release limit should result in a more restrictive yearly average level than the basic annual average emetinuous release rate.
Thus, if the preposed limit is used as a specification, additional restrictions se release levels fe11oving the use of this limit must
, be incorporated into the specification se that the dose level of
$00 mres/ year would met be esseeded in the oester into whiek the release is made. For esemple, as the applisant has determined, the sector affected by the release would resolve 20 percent of its permissible annual dose in to hours. k annual averego eastimoems release rate would therefore be reduced to 80 persant of the applicable spesifica.
tien for the remainder of the year provided such a reduetten was adequate to meet the permissible amamal does level. If releases de occur whiah aneced the sammal average esattamens release rate, such '
release rates, period of time and soster(s) affected should be re.
Ported to DRL and Compliance, for the resord.
~ ,, . -
O b 4
A.1.s. he release rate of radioastivity, omsort halogens and particu.
lates with a half life greater than 8 days, shall not aseeed 1.1 ci/ses for a period La eneses of 15 minutes La any one hour.
181' Hiltt he above limit was detessiaod by the appliaast in tie same way as apostricatten A.1.b. disemesed proviemely. h bases for this limit is 10 CFR 20, seeties 20.195, paragraph (b)(1) and La met applisable as previously disenesad. he above release rate with the limited release time would saly peoult in a 2 area whole body dose for the given oester. therefore, the restriotians required en the ese of the above spesiftsatsen would be en the ammber of times per year that eueh a relaaea rate seuld be used, the 11eenoes should hoop a resord of the times such a release rate le need te deterstne if any given sector wee betag subjected to such releasse more than several times a year.
he bases for the above limit may be aseestated with the aanmal average seatinuous release rate staea the limited estease time se sentrolled by the required delay time to detest the level and elese the off-gae Leetaties valves. stase the sategrated dose sesosisted with euch a release to one11 la semparison to the permissible amenal dose and possible detection uncertainties, a limiting value of twice the samuel average seatinuevo release rate should be adeguate for monitoring purpeees.
A.2. he release of radioactive affluente shall be continuously monitored for gross estivity. If this specificatt6a sammet be met, the reacter shall be placed La the feelated somdition.
, D$essesiva he above spesification dose met Ladisate the type of activity that will be semitered. The maattering Lastrument appears to be a gamme i sciattilaties detester. b refore, rather than grose activity, the speciftsatten should read groes samme estivity to obow that beta will not be detested and auch dioeriminattaa to met, available La the monstertag setup. the quostism rateed by this eyesiftsatten to whether er met the propeeed monstertag unit will be sapable of deter.
mining a differense in the gestity of the radioactive affluente er saly the geestity of grees.samme afflusste.
m __
g, mm oe 1
b h 3
t l
A.3. he annual average continuous release rate of radioactive halogens and particulatas with a half-life greater than 8 days shall not exaeed 3.3 p C1/sec. Malegens and particulates released free the stack shall be collected for monitoring by 1
the en-line sample canister.
Discusstec goveral quostiens arise for the abeve specification eines the halogen release rate limit is sigtificantly lose than the noble gas release 1 rate limit. sines the present instrumentation does met appear sapable of determining quality of the redisestive sfilmeat, a abasse sa the ratto between the noble gas iractien and the halogen fraetien present1y assumed by the applisant (104 1-131) would not be observed until the weekly chareest sampler was removed. Is there any asens available to gamma osan the sanister in place to detemine the rate of build up of activity on the charcoal daily or sostituously? Will there be technical speciftsations en the chareoal sempler, air flow, and associated equipment to provide se escurate analysis of the kategen release rate per weekt the abeve limit dess met appear to be la appropriate units for comparison with the r9nitoring arrangement.
The only measured release rate for halogens from the stack will be in terme of possible gross halogen activity per week for a small l fraction of the total air volume exhausted. It would appear that j many extrapolations and assumptions must be used to detemine if the above specification is being met.
l The previous discussion concerning Specification A.1.a. in respect to the appropriate section of 10 CFR 20 applisable to such effluent limite appears to be pertinent to the halogen manual average continuous release rate. Apparently a total yearly release of 100 C1 of I-131 with the associated halogen radioisotopes in propertionate ratie results in approximately the permissible yearly dose. 31oco this release quantity is small in semparisse with the release quantity of noble gases, the licenses should have a more sensitive detection method than a weekly semple prior to off-gas release to the stask.
W *M" -
^
m, ~M l
l
,~
O k
. 6-If a gamma scan could be made of the canister as previously discussed, a calibration of acceptable build-up rate on the charcoal could be made that was sensitive to changes in off gas quality of radioactive affluents.
F. D. Anderson Operating Reactor Branch f2 Division of Assetor Licensing cc F. Howe, ERSTB, DE D. E ller, RF3 #1, DEL orFICE > ... . . .b . . DE
,.DT)-
4;w SURNAME > _iide r $ OQ !,jjm ,,, DhZiemSDQ_ , , ,, ,, , , ,, , , , , , , , , ,
part > . 2 /13 /69.........l .. 2 //f/M...._. .. . , , _ , . ,,
form A10 3tB (Rn. 9 53) AECM 0240 e a uvseensei ,e, , .a ors u i.es o-in eiv