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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] |
Text
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1 MAY 11 1971
[$ &b 5 Donald F. Knuth, Chief, Boiling Water Rosctors Branch No. 1 Division of Reactor Licensing PROTECTION FACTORS FOR THE USE OF RESPIRATORY EQUIPMENT
' From time to time we are asked by licensees that allowance be made for the use of respiratory protective equipment, persaant to 10 CFR Part 20.103(c)(1) and (3). Attached is the recent Change No. I to the Technical Specifications for the Monticello Nuclear Generating Flant (Docket No. 50-263). The contents were proposed by the.
Division of Radiological and Environmental Frotection and received the concurrence of the Office of the General Counsel. Whenever
,- a licensee asks for allowances to be made for the use of respiratory.
protective equipment, to be consistat, I recommend that the attached be incorporated in the Technical Specifications until they are officially published in the Federal Register.
'Dritindi ttenWey ykter .nsnmyn Victor Benaroya, Project leader Boiling Water Reactors Branch No.1 Division of Reactor Licensing
Enclosure:
Change No. 1 to Monticello Tech Specs Distribution:
Docked _8**J .
DRL Reading BWR-1 File Pt. Morris, DRL j
FSchroeder, DRL i Asst. Dirs., DRL Br. Chiefs, DRL BGrimes, DRL j RKlecker j DVollmer VBenaroya, DRL.
1 omer> . DRL ,:,BWR-1,,,,,,, , , , , , , , _, _ , , , , , _ , , __,_ , , , , , , , , _ _ , ,
VBenaro a:ks I
$URNAMr > ,,Kf,f.h.1 , , , , , , , , , , _ , , , , , , , , , , , , , , , _ , , , , , , , , , , , , , ,
04rr > .1 5/10/7.1.. . . , , ,
Form AEC=318 (Rev. 9-63) v.s. sovumutwr eminTins crria i nse- o-ss.4ss tl # '
9212100241 710S11 PDR ADOCK 05000263- PDR-p
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j[%'+, UNITED STATES 4" ' N [S ATOMIC ENERGY COMMISSION l
- d .*. '. J wase eTou, o.c. rous Idi April 28, 1971 f
Docket No. 50-263 Northern States Power Company ATTN: Mr. Arthur V. Dienhart
' Manager of Engineering 414 Nicollet Mall Minneapolis, Minnesota 55401 Change No. 1 License No. DPR-22 Gentlemen:
Your letter dated March '15,1971, requested authority to assign protection factors to the use of* respiratory equipment and to make them part of the Tcchnical Specifications of Provisional Operating License No. DPR-22 for .
the Monticello Nuclear Generating Plant E-5979.
4 During our review of the proposed change, we informed your staff that certain modifications were necessary to meet our regulatory requirements.
On the basis of our review of your proposed change, as modified, we have con-cluded that the change does not present significant hazards considerations not described or implicit in the Monticello Safety Analysis Report and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the Monticello Nuc1 car Generating Plant E-5979 in the proposed manner.
Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, the Technical Specifications of Provisional Operating License No. DPR-22 are hereby changed as set forth in Attachment A to this letter.
Sincerely,
. M1 a Peter A. Morris, Director Division of Reactor Licensing
Enclosure:
Attachment A - Change to
- Technical Specifications i
O p amoo.
.- . -. -~ .. - . - -
. l
.e O_ 1 ATTAC@ENT A Change No. I to Technical Specifications Provisional Operating License No. DPR-22 l 's Northern States Power Company
Change Specifications 6.2B in its entirety to read:
"6.2 B Radiation control procedures shall be maintained and made availabic to all station personnel. These procedures shall show permissibic radiation s
exposure, and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be_ organized, with the following exceptions, to meet the requirements of 10 CFR 20."
- a. Paragraph 20,203 " Caution signs, labels, signals and controls."
In lieu of the " control device" or alarm signal required by paragraph 20,203(c) (2), each high radiation area in which the intensity of radiation is-1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area l and entrance thereto shall be controlled by requiring issuance l
of a Radiation Work Permit and any individual or-group of
- individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
The above procedure shall also apply to each high radiation area
' ' in which the intensity of radiation is greater than 1000 mrem /hr, g except that locked doors shall be provided to prevent unauthorized i entry into these areas and the keys to these locked doors shall be i- maintained under the administrative control of the Shif t Foreman on duty.
P
- b. Pursuant to 10 CFR 20.103(c)(1)' and (3), allowance may be made-for the use of respiratory protective equipment in conjunction ,
with activities authorized by the operating. license for this
, plant in determining whether individuals in restricted area are exposed to concentrations in excess of the' limits specified in Appendix B, Table I, Column 1, of 10. CFR 20, subject to the following conditions and limitations: - .
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- c. Notwithstanding any exposure limit provided herein, the licensee shall, as a precautionary procedure, use_ process or other engineering controls, to the extent practicable, to limit concentrations of radioactive materials in air to Icvels below those which delimit an airborne radioactivity area as defined. in 6 ?0.203(d)(1) .
- d. When it is impracticable to apply process or other engineering controls to limit concentrations of radioactive materials to levels below those which delimit an airborne radioactivity area as defined in 8 20.203(d)(1), and respiratory protective equipment is used to limit the inhalation of airborne radicactive material, the licensee may make allowance for such use in estimating exposures of individuals to such materials providcd:
- 1. Intake of radioactive material by any individual within any -
period of seven consecutive days will not 'exceec' that which would result from inhalation 1/2/3/ of such material 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week, at uniform concentrations specified in Appendix B, Table I, Column 1 of 10 CFR Part 20,
- 2. Respiratory protective equipment'is selected and used so that the peak concentrations of airborne radioactive material inhaled by an individual wearing the equipment do not exceed the per-tinent values specified in Appendix B, Table I, Column 1 of.
this part. For the purposes of this subparagraph the concentration of radioactive material that is inhaled when respirators are worn 1/ Since the concentration specified f or tritium oxide vapor assumes equal intakes by skin absorption and- inhalation, the total intake permitted is twice- that which would result from inhalation alone at the concentration specified for 113 S in Appendix B, Table I, Column 11 for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
2/ .For radioactive materials designated "Sub" in the1" Isotope" column-of the table, the concentration value specified is based upon exposure to the material as an external radiation source. Individual exposures to these materials shall be accounted for as part of the limitation on individual dose in a 20.101. These materials shall be subject to applicable precautionary procedures of paragraph c. above.
3/ For modes of intake other than inhalation, such intakes must be con-trolled, evaluated, and accounted f or by techniques and procedures as may be appropriate to the circumstances of the occurrence with proper con-sideration of critical organs and'11miting doses, i
- s. w L. . . . .
r < r- - - . . . . . . . .. .
3 may be initially estimated by dividing the_ ambient airborne con-centration by the prot.ection f actor specified' in Table I attached s
hereto'for the respiratory protective-equipment worn. If the.
intake of radioactivity .is later determined by other measurements i to have Feen greater than that initially estimated, the greater quantity shall be used in evaluating exposures; if it is less than that initially estimated, the lessor quantity may be used in evaluating exposures.
i
- 3. The licensec advises each respirator _ user that he may leave the ,
area at any time for relief frv n respirator use in case of equip-ment maliuhetion, physical or psychological discomfort, or any other condition that.might cause_reduct;Ju in the protection =
afforded the wearer.
C The licensee maintains a respiratory protective program adequate 4.
to. assure that the requirements of, paragraphs _1. and 2. , above ,
are met.
Such a program shall include:
' (a) Air sampling and other surveys sufficient to identify the hazard, to evaluate individual exposures, and-to permit proper selection of respiratory protective equipment.
(b) Written procedures to assure proper selection, supervision, and training of personnel using such protective equipment.
(c) Written procedures.to assure the adequate fitting.of respirators; and the testing of respiratory protective equipment f or operability immediately prior to use. -
(d) Written. procedures for maintenance'to assure _ full effective-ness of respiratory protective equipment, including issuance, cleaning and decontamination, inspection, repair, and storage._
(e) Written operational and administrative procedures for proper use of respiratory protective equipment including provisions for planned limitations on working times as necessitated by operational conditions.
_________._.___________________.___________.__.___.__.________._____.m.___._ . _ . _ _ . _ _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
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(f) Bioassays and/or whole body counts af -individuals, and l j
other surveys, as aporripriate, to evaluate individual exposures and to' assess protection actually provided.
j
? (g) Records sufficient to permit periodic esuluation.of the
- adequacy of the respiratory protective program.
- 5. The licensee uses equipment approved by tbc'U. S. Eureau of ,
Mines under its. appropriate Approval Schedules as set forth in l
' Table I below. Equipment not approved under U. S. Bureaa of 1 Mines Approval Schedules.may be used only if the licensee has evaluated the equipment and can demonstrate by testing, or .
j on the basis of reltable test information, that tie material _'
i least-and performance characteristics of the equipment are at l
j l
]
equal to those efforded by'U. S. Bureau of Mine9 approved.
l equipment of the same type, as specified in Table I below. .,
e Unless otherwise authorized by the Commit.sion, the. licensee i 6.
- does not assign protection _ factor.1 in excess of those specified in Table I below in selectinc and using respiratory protective
! equipment. J
+
i 7. These spacifications with respect to the' provisions of E 20.103
~
shall be superseded by cdoption of proposed changes to 10 CFR 20,
) Section 20.103, which would make this specification unnecessary.
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TABL2 I TO SPECIFICATION 6.2 3 ~ ~
PROTECTION FACTOR 3 FOR RESPIRATORS
~
' PROlECTION FACTORS 2/ l GUIDFS TO SELECTIG*4 0F EQUIPMENT l -
SURLAU OF iTINIS APPh'AL SCHEDULES
- DESCRIPTION MODES 1/ AND VAPORS M!D lFOREQUIP!:EtlT CiPABLE OF PRO'.'IDIiG A :
GASE3 EXCEPT l t EAST EQUIVALEf:. PROTt:CTION FACTORS 2 TRITIUM OXIDE 3j *or schedule saperseding for equipnent of type lirted l _ .
I. AIR-PURIFYING SESPIRATORS Facepiece, half Wask 4/ 7/ 11P 5 21B 30 C'T s14.4(b){4) ,
100 21B 30 CFR 514.4(S)(5); 14F 30 CFR 13 :
Facepiece, full 7/ NP II. aim 03PHERE-SUPPLYING i
~ RE519 RAT 03 !i
- 1. Airline respirotor 193 30 CFR s 12.2 c Type C i) 100 EGiet.e half'sask CF ,
1,000 ISB 20 CFR S 12.2 c Typc C,1) l 4 Facepiece, full CF 108 30 CFR 9 12.2 c Type C(ii)
'Facepiece, full 7/ D 500 Facepiectr, full ~~ FD 1,000 TypeC(iii) 5/
l 19t150 CFR 9'12,2 6/ c Hood CF
[]
Su1t CF
[/ ...
- 2. Sel f-conta! qed Treathirg(SCBA)
~
apparatus i Facepiece, full 7/ D 500 13E 30 CFR 5 ll.4(b (i) 1,000 13ti 30 CFR s 11.4(b (fj)
Facepiece, full - PD 13E 30 CFP 5 ll.4(b Facepiecs, fall R .1,000 .
III. 'COMPlNATIOP RE5PIRATOR Protection factor- 19B CFR 512.2(e) or applicable Any com6ilfiitfon of air- se.hedules as listed above purifying and atmosphere- for type and mode supply!rg respirator of operatiori as listed above __
'1f,2/,3/,4],f/Sf,_7f,[fhasenotesareonthef?llowingpages]
1 M See the following symbols:
CF: continuous flow 0: demand NP: negativepressure(i.e.,negativephaseduring inhalation)
PD: pressuredemand(i.e.,alwayspositivepressure)
PP: positive pressure R: recirculating (closedcircuit)
U (a) For purposes of this specification the protcetien factor is a measure of the degree of protection afforded by a respirator, defined as the ratio of the concentration of airborne radio-active material outside the respiratory protective equipment to that inside the equipment (usually inside the facepiece) under conditions of use. It is applied to the ambient airborne concentration to estimate the concentration inhaled by the wearer according to the following formula:
knbient Airborne Concentration Concentration Inhaled = Protection factor (b) The protection factors apply:
(i) only for trained individunis waaring properly fitted respirators used and maintained under supervision in a well-planned respiratory protective program.
(ii) for air-purifying respirators only when high efficiency
[above 99.9% removal efficienc Mines type dioctyl phthalate (y test]
00P) by U.particulate S. Bureau of filters and/or sorbents appropriate to the hazard are used in atmospheres not deficient in oxygen.
(iii) for atmosphere-supplying respirators only when supplied with adequate respirable air.
E Excluding radioactive cont minants that present an absorption or submersion hazard. For thi.ium oxide approximately half of the intake occurs by absorption through the skin so that an overall protection factor of not more than approximately 2 is appropriate.
when atmorrhere-supplying respirators are used to protect against tritium ox1de. Air-purifying respirators are not recomended for 1.m.,
use against tritium oxide. See also footnote 5/, below, concerning supplied-air suits and hoods, g
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e
S Under chin type only, llot reconnended for u:,e where it might be possibic for the ambient airborne concentration to reach instantaneous values greater than 50 times the pertinent values in Appendix B Table I, Column 1 of 10 CFR, Part 20, b/ Appropriate protection factors must be determined taking account of the design of the suit or hood and its permeability to the 110 protection f actor greater contaminant under conditions of use.
than 1,000 shall be used except as authorized by the Comission.
El 16 approval schedules currently available for this equipment.
Equipment must be evaluated by testing or on basis of available test information.
U Only for cleon-shaven faces.
Il0TE 1: Protection f actors f or respirators, as may be approved by the-U. S. Bureau of 111nes according to epproval schedules for respirators to protect against airborne radionuclides, may be used to the extent that they do not exceed the protection factors listed in this Table. The protection factors in this Table may not be appropriate to circumstances where chemical or otherrespiratory hazards exist in addition to radioactive hazards. The selection and use of respirators for such circumstances should take into account approvals of the U. S. Bureau of Mines in accordance with its applicable schedules.
140TE 2: Radioactive contaminants for which the concentration values in Appendix B. Table I of this part are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations. Under such circumstances, limi-tatior.s on occupancy may have to be governed by external dose limits, t
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