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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20216G4221999-09-27027 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 ML20212H2031999-09-27027 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 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 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 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 ML20215L3101987-05-0707 May 1987 Staff Requirements Memo Re Commission 870430 Affirmation/ Discussion & Vote in Washington,Dc on SECY-87-68A Concerning Order to Rescind 861020 Order Directing Licensee to Show Why OL Should Not Be Modified.Order Signed on 870501 ML20211N7961987-02-19019 February 1987 Requests Consideration of Encl Util 861223 Request That 860228 Application for Extension of Duration of Licenses DPR-57 & NPF-5 Be Given Higher Review Priority.Util Requests Completion of Review by 870331 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20210T3791986-10-0202 October 1986 Notification of 861017 Meeting W/Utils in Bethesda,Md to Discuss Issues Affecting Operating Reactors & NRC ML20211N8311986-10-0101 October 1986 Proposes Listed Schedule for Completion of Reviews of OLs Extensions for Listed Facilities Based on Low Priority of Effort.Plant Sys Branch Will Coordinate Responses & Recipients Will Be Provided W/Integrated Plant SERs ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20211E5131986-06-0606 June 1986 Discusses Inputs for SALP 6 Assessment for Dec 1984 - Mar 1986,due on 860618.Inputs Should Be Typed on 5520 Sys & Remain on Sys Until SALP Board Meeting Held.Listing of Insps Conducted During Assessment Period Encl ML20155F1941986-04-10010 April 1986 Summarizes Operating Reactor Events Meeting 86-11 on 860407 Re Events Since 860331.List of Attendees,Discussion of Events,Status of Assignments & Assigned Completion Dates for Items Encl.Response Requested for Incomplete Assignments ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20198G2001985-11-0505 November 1985 Recommends Issuance of IE Info Notice Re Possible LOCA at High/Low Pressure Interface After Fire Damage Occurs in Control Room.Problem Discovered During Fire Protection re-review ML20087A8311984-03-0505 March 1984 Forwards Monticello Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Evaluation & Monticello Nuclear Power Plant Full-Scale Joint Emergency Exercise on 830223, Final Rept ML20207L3491983-11-30030 November 1983 Advises That Scheme Described in Licensee 830929 Request for Extension of Date for Complying w/10CFR50.54 Unsatisfactory. Mods May Result in Shift Supervisor Spending Less Time in Control room.Davis-Besse Proposal Also Unacceptable ML20058G6051982-07-13013 July 1982 Forwards Draft Ltr Clarifying Confusion During LANL 820706-09 Site Visit to Collect Data for Vital Area Analysis Program.Concerns Re Releasing of Data Resolved.Future Visits Will Be Endowed W/Official Imprimatur ML20148F1051978-10-24024 October 1978 Forwards Memos Re Recent Problems in Pipe Support Base Plate design.(ANO:7811020332,7811020336, & 7811020343.) ML20148G2271978-10-24024 October 1978 Forwards 780929 Memo Re Results of Recent Fire Protec Res Test Conducted at Underwriters Lab. (See ANO: 7810050359, 7810050373.) 1999-09-27
[Table view] |
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[.
PR June 2, 1972 Dudley Thompson, Chief, Operational Safety Branch, L MONTICELLO MANAGEMENT APPRAISAL From May 22 through May 26, 1972, I was a member of the inspection team making a management inspection of Northern States Power (NSF) Monticello Plant. Following are the team members:
Max Hildreth, CO, Headquarters, team leader Robert Dodds, CO, San Francisco Robert Carlson, CO, Newark Carl Seyfrit, CO, Chicago, assigned inspector Leo Higinbotham, CO, Newark John Sears, OSB, L It is planned that some team members will continue the inspection by visiting NSP's home office on June 7-8, 1972, and a final report to NSF top management will be made- by some team members, and possibly other Regulatory representatives, a week or two later.
For management inspections of this type, CO recoassends that each team member be excused from other work so that he can devote 5 man-weeks to preparation; inspection, appraisal and report writing. In'this instance, Carl Seyfrit assembled, for each team member, 2 volumes (each as big as the Washington phone book) of back up material. Max Hildreth broke the total job up into a amber of different areas of interest, and assigned each man a portion of these jobs. I was assigned to the team only 2 days before the inspection so that I did not have the back up material. My assigned areas were Baergency Plans, Industrial Security, Adequacy of Abnormal Operating Procedures, and Competence of Operating Crews. A brief stannary of my findings - follows.
- 1. Emergency Plans I visited both the Principal and the Alternate Emergency Assembly Shelters, the Control Room, the Energency Room of the M aticello Big Lake Hospital, examined emergency kits, reviewed NSP correspond-ence with' local agencies, and reviewed a draft Minneso'.a State Plan.
Not all local agencies have confimed their as-Lasent to assist in writing.
No decisional aids are available (e.g. isopleths).
Hospital arrangements appear to be adequate. The only high volume CFFtCE > . . . . . . . . . . . . . . . - . . . . . . . ~ . . . .
- - - - - - - - - - - - - - - - *~-- "~" "- - - " * " ~ " * " * "
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"""E* 9212070407 760602 - // .2 7 3 PDR ADOCK 05000263 DATE> l. .. . . . . .
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Form AEC-Ste t.Rev. 9+53) AECM 0240 e.o .u-se-auss.: 4es-67s u.... .. . -
D. Thompson i air samplers available must be opersted on 110 VAC, and the only
{ vehicles with 110 VAC power outlets are stationed at St. Claud approximately half an hours travel from the plant.
4 I urged the Health Physicist to rewrite the plan to comply with all aspects of 10 CFR 50 Appendix E and its Guide, and suggested that he consult the connecticut Yankee plan for a model. I also suggested that he consider procuring battery operated air samplers.
- 2. Security Plan i
j Monticello's original plan included only a lighted perimeter fence and s key system for opening gates in the fence and doors in the building.
~
+
Monticello now employs two armed Pinkerton guards on shift, around the clock, 7 days a week. All outside doors and gates are locked. The shif t supervisor controls all keys.
i Plant physical layout has cooling towers near the river, then the security fence with one light at mid point. Just inside the fence is a one story warehouse which extenda nearly the whole length of the fence, except for truck access space on both sides of the j
warehouse. The guard's shack is about 100 feet still further into l
the security area, about even with one end of the warehouse. I visited the site about 3 a.m. on a rainy night when the effluent i from the cooling towers was blowing toward the warehouse. The l
whole area was blanketed in vapor and concealment appeared to be no problem.
{
The fence at the intake structure stopped about 10' short of the end of the sea wall on each side of the intake. . The purpose of the blank space was said to afford access to clean out the area i in front of the intake.
I made the following suggestions.
- a. A derailer should be installed on the tracka entering the i
plant area. Monticello agreed.
b.
The fence at the intake structure should be extended to com-l plate the barrier. Other arrangesenta can be made.for cleaning in f ront of the intake. NSP's Security Manager agreed and l
i stated that the D00 inspector had made the same sunnestiam.
omer > . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . .
SURNAME > . .. . .. ..
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Form AEC.Sta (Rev. 9.53) AECM 0240 *** 4htestars-a 44ms
4 i
D. heapsen ! \'.
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! e. The fence behind the warehouse is vulnerable. So warehouse j itself can be used as a barrier if a fence is installed from each of its ends across the truck access space. We NSF i
Security Manager stated that he would have a response to this idea within two weeks'.
- 3. Adequacy of Abnormal Operating procedures.
t Each of the transients analyzed in the FSAR is cove ed by an l Abnormal Operating Procedure, in a separate section of the j operations Manual.
t The procedures in the Operations Manual are categorized by
- system, and each system includea.a tabulation of annunciator i alarms relative to that system. . The tabulation includes'the name I of the system and sub-systems, the loestion of the annunciator
! unit on the panel, the location and type of sensor, and the corrective action to be taken in response to the alarm. operators are not required to memorise the immediate corrective action in j
response to alarms. No drills are conducted, on shift, en either i
abnormal operating procedures or responses to alarms. In the i stasmary meeting, I pointed out- that such drills would be a require--
! ment in the new version of Technical Specifiaations.
1 i
j 4. Competence of Operating Crews.
i l
Judgeset of competence is subjective. I did this part of.eg job i by evaluating the tools-svailable to the operator and by observing
)
ed conversing with all- levels of operators during routine opera-
{
tion and during shift change.
i Voltase A of the Operators Manual contains Administrative Pro--
I.
I eedures. There is no written procedure describing shift turnover.
I observed two shift turnovers. . ome from days to the 3-11, and one from 3-11 to graveyard. Turnover..in both instances, consisted
} of a' walk through by both operators of instr - tation and con-l trols a review of los books by both in concert, and finally an i extended conversation between the two.
~
Volume F of the Operators Manual consists of temporary procedures.
j j.
- The original concept of this document was good; however Volume F i
now consists of - - 250 procedures, some of- which are 2 years-'old.
The Ead Waste system has a separate Control. Room. .There have
- been many minor changes in design since installation. The
. OmCE > . . . , ~ . . . . . . . . . . ~ ...u.. . . . ~ . . .-- --~~~ ~ . . ~ ~~ ~~
i SURNAME > . . . . . . . . . . . . . .. . . . . . - - . .~ ~ ~~. ~ ~
- - DATE > . . .. .. . - - - . - - -- -- -l-~ "
Form AEC-Sla (Rev.9-33) AECM 0240 m **s-to-site 4-3 soms i
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'- D. Thompson i
i
- operating procedures are not up t6 date. M e plant is now operated l with zero liquid radwaste. The final discharge is a radioactive
- sludge which is used in a concrete slurry and barreled as solid
- waste.
l
, I visited the plant at night _ to observe back shift operations fro:n about 10 p.ni. to 3.a.m. This afforded an opportunity to -
chat privaccly and informally with rural route operators as I f accompanied them on their rounds. ;
j Host surveillance testing is done on the graveyard shif t. Une j shif t supervisor encourages lower grade operators to operate the
! control room knobs and switt hes during testing. Cther shift
[ supervisors and . older 'opers ors discourage such training. The-
! plant laborers, whose title is nuclear plant helper, and who do i the decontamination of the radwaste concrete barrels, feel that
! their yearly 10-hour training in radiation protection is too
} academic, and. consequently they do not retain the information.
4 In attmapting to evaluate crew competence, I took one incident -
i the Ceptember 5, 1971 screa - and tried to reconstruct the event i from docusentation. There were many gaps in the doctamentation.
- The shift supervisor's log of the shift following the-incident i
had the following final entry "Too busy .to keep 's good'1c3."
j I esamined the minutes of the meetings of the Plant _ Operations l Committee and the Safety Audit Committee-(SAC) relative to the Septecaber 5 incident and_ did further spot-checking through these i records. There was more then one_ instance where the loop of
( incident, investigation, evaluation and corrective actior was
! not closed. In- discussing the september 5 incident, the SAC noted that an air failure was the initiating event, and that a previous study of the adequacy-of the plant air system had resulted
! in a asamber of reconseadaticas for improvement, but there had i been no follow through in seeing that the recossendations _were
! carried out. There are no controls for the plant air system in
! the control room, only a recorder. The incident was caused by an
! error by the suailiary operator at the. air cogressorocontrol; the control room operators responded properly.
' My evaluation of operating crew ccupotence:is best stunned up by saying that I had a feeling of ceafidence in the control room.
There appeared to be discipline, immediate response to-alarms, good morale, pride in detailed knowledge of the plant, copperation between shifts.
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- DATE > . . . . . . _. . . . . . . .. . . . . . . . . . . . .. .. ..
Form AEC-5it (Rev. 9 53) AECM 0240 **o .43Me-4:eas-i e43-47s 1
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D. Thompson i
! The data logger properly used, is an entremely useful tool. NBp
- is fortunate in having an extremely competest computer engineer i
who uses the computer to analyze trends, and who manages to keep
. the computer on stream oncept for about two hours per month. - Mere is one problem, since the coaguter does such a good job, the operator's and shif t supervisor's logs suf fer. There does not i seem to be a good positive policy on what information must be logged.
l The Plant Supervisor was responsive in giving each of us his l opinion of upper NSP management competence. He thought that the
} V.P. level had little or no appreciation for nuclear plant problems.
l He has recently hired 8 young engineers all of whom just passed l SRO exams. As yet these enginers do not have clearly defined l
I responsibilities. They maybe reserve troops in case of labor problems - this is an IBEW shop; or the hope may be that they will mature into a strong on-site technical support group, he off-site technical support group - under Lee Mayer, Director of L Nuclear Support Services, still consists only of Mayer and one engineer, he inspection team visit to the NSF home office on June 7-8 will permit further evaluation of technical support.
C- - te oc Mamanement Ascraisal Effort.
Our team consisted of 6 people. We were almost universally agreed that
' there were toomany of us. . ne team should consist of no more than 3_-
mature reactor people, each with an appreciation for the interdependsece of management and operator. he assigned CO inspector should gp_ttbe a member of the team; he is inclined to feel defensive if the team unearths management deficiencies. Detailed inspection of health physics, emergency planaias l
and industr&al security, as was done by Higinbothan and Sears, should not be a part of the team effort - these concerns should be covered by-regular -
l CO inspections.
There was much overlapping in our efforts because there were so many of us.
nis resulted in many of us discussing the same topic with the sanas NSP man, but from a different view point. Some overlap is useful, since a finding by one may be reinforced by anothers investigation. For example, almost all of us found some example of a lack of " gap-closing" on the part of NSP.
We all agreed that this was the most serious management deficiency.
My principal contribution was investigation of- the lower grade operator situation. I volunteered for this ' effort, since it did not seem to be emphasized in the team plana. M is area is sometimes neglected, but I believe that it is important to get the operator's opinions on how upper and middle management policies are translated into- the kind of procedures -
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Form AEC-310 (Rev,9 53) MCM 0240 e.o .43--s*- stees-t 44ms
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1 l D. Thompson '
which can be underntood and followed. The team members sust reatud them.
selves regularly of the goal of the effort - management appraisal - and should not get bogged down in lengthy discussions on whether a particular incident should have been reported, or whether an individual item was or was not a 50.59 ite:r, or whether some words in the Tech Specs should be
- changed. Tech Specs changes may result from the inspection, but time at the plant should be devoted to find ing out how the licensee's controls really work.
A fundamental precept of reactor regulation has always been that the licensee has the primary responsibility for safety. The licensee discharges that responsibility through management controls. The regulator should then i fulfill his own resp.sisibility by continuously appraising how licensee l management is performing. The interest of ' the regular inspection program is of ten focused on specific mechanical problems and management aspects are reicgated to the background. P.anagement inspections then are not only useful, but may well be .one of the most important features of the Regulatory program. Independence of the inspection auditors imust be as complete as possible to insure their objectivity.- The final interview with licensee upper management crowns the effort with thorns or gold depending on how the team findings are presented. If there is an overemphasis on legal aspects
, that only results in top management requiring the plant staff to produce more paper to keep the AEC quiet, then we have failed. If instead tha appraisal findings can be presented strictly frein the point of view of
- our mutual interest in safety of operations and results in top management
- taking the necessary measures to assure itself of the couplete validity of i all management controls, then the whole effort has been worthwhile.
i "I
1 John R. Sears operational Safety Branch, 1.
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5URNAME> . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . -
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Form AEC-Ste (Rev.9 53) AECM 0240 *** '43-is-~st eas.: 44s-os i
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