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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20206H3921999-05-0606 May 1999 Notification of 990518 Meeting with Util in Rockville,Md to Discuss Util Presentation of Technical Evaluation Performed in Support of License Amend Request Which Would Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20199J0641998-12-30030 December 1998 Notification of 990119 Meeting with Duquesne Light Co in Rockville,Md to Discuss Status of Licensing Actions/ Activities Currently Being Reviewed by NRC & of License Amend Requests Expected to Be Submitted in Near Future ML20198G9941998-12-22022 December 1998 Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor Operated Valves Program ML20196H1391998-12-0404 December 1998 Informs That Encl RAI Was Transmitted on 981204 to F Ferri of Dl.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20195G4501998-11-10010 November 1998 Rev 1 to Notification of Significant Licensee Meeting 98-87 with Util on 981116 to Discuss NRC Presentation of Osti Exit Followed by Util Presentation on Unit Restart Plant Performance ML20155K3451998-11-0505 November 1998 Notification of Significant Licensee Meeting 98-87 with Util on 981116 in Beaver Valley Power Station,Emergency Response Facility Conference Room A,For NRC Presentation of Osti Exit & Dl Presentation on Unit Restart Plan Performance ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154D5611998-10-0505 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980817-21 ML20154D4481998-10-0505 October 1998 Forwards Exam Rept with as Given Written Exam for Test Administered on 980817-21 at Unit 2,for Processing Through Nudocs & Distribution to NRC Staff IR 05000334/19983001998-08-17017 August 1998 Forwards NRC Operator Licensing Exam Rept 50-334/98-300OL for Exam Administered on 980420-24 & 0518 ML20236X5981998-08-0404 August 1998 Notification of 980820 Meeting W/Util in Rockville,Md to Discuss Proposed Submittal of Improved Std TS ML20236K9051998-07-0101 July 1998 Notification of Significant Licensee Meeting 98-65 W/Util on 980716 to Discuss Plant Status & Preparations for Plant Restart IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples1998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20236N6351998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20247D1541998-05-0505 May 1998 Notification of 980519 Meeting W/Duquesne Light Co in Shippingport,Pennsylvania to Discuss NRC SALP of Beaver Valley Power Station for Period of 960929-980321 ML20248L6081998-03-0505 March 1998 Forwards Exam Rept W/As Given Written Exam for Test Administered on 971215-18 at Facility ML20248L6621998-03-0505 March 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility ML20212G4791997-10-28028 October 1997 Forwards SER Accepting Licensee 970213 Request Re Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20149G3261997-07-18018 July 1997 Notification of 970805 Meeting W/Util in North Bethesda,Md to Discuss Plans & Schedules for Resolution of 10CFR50.61 Updated Info for Pressurized Thermal Shock Evaluation IR 05000334/19970031997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam Repts 50-334/97-03OL & 50-412/97-03OL (Including Completed & Graded Tests) for Tests Administered on 970317-21 & 970428- 0502 ML20149D2891997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317 ML20149D2851997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317-21 ML20148E1881997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-60 W/Util on 970623 to Discuss Surveillance Test Program Apparent Violations ML20138Q1171997-02-27027 February 1997 Rev 1 to Notification of Significant Licensee Meeting 97-20 W/Util on 970307 in King of Prussia,Pa to Discuss Plant Configuration Control Issues Related to Component Mispositionings ML20135D1271997-02-20020 February 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970304 to Discuss Plant Configuration Control Issues Re Component Mispositionings ML20133D6221997-01-0202 January 1997 Rev 3 to Notification of Significant Licensee Meeting 96-128 W/Util in King of Prussia,Pa Re Predecisional EC to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20132E7361996-12-17017 December 1996 Notification of Significant Licensee Meeting 96-462 Rev 2 W/Util on 961230 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4601996-12-0606 December 1996 Notification of Significant Licensee Meeting W/Util on 961219 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4921996-12-0404 December 1996 Notification of 961219 Significant Licensee Meeting 128 W/Util in King of Prussia,Pa to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20141M6491996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review1996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20129E7161996-09-30030 September 1996 Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484 ML20059K7871994-01-0606 January 1994 Notification of Enforcement Conference 94-06 W/Util on 940118 to Discuss EDGs Solid State ATC Timer/Relays ML20059C3261993-12-28028 December 1993 Discusses Suggestion for More Efficient Use of NRC & Licensee Resources NUREG-1231, Forwards Documents Referenced in Suppl 16 to NUREG-09331993-11-29029 November 1993 Forwards Documents Referenced in Suppl 16 to NUREG-0933 ML20058E4201993-11-26026 November 1993 Notification of Significant Licensee Meeting 93-157 W/Util on 931202 to Discuss AIT Exit Meeting ML20059K5501993-11-0808 November 1993 Notification of Significant Licensee Meeting 93-146 W/Util on 931115 in King of Prussia,Pa to Discuss Training Program Improvement Following Initial Exam Results from May 1993 ML20059K2711993-11-0303 November 1993 Discusses 931027 Operating Reactors Events Briefing Conducted to Inform Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931020. List of Attendees Encl ML20059H1381993-11-0202 November 1993 Notification of 931110 Meeting W/Util in Rockville,Md to Discuss Dlc Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059J4471993-11-0202 November 1993 Notification of Cancellation of 931110 Meeting W/Util in Rockville,Md to Discuss Util Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059G1271993-11-0202 November 1993 Notification of Significant Licensee Meeting 93-139 W/Util on 931119 in King of Prussia,Pa to Discuss Enforcement Conference Re Open Containment Penetration During Refueling ML20056G8161993-08-23023 August 1993 Notification of Significant Licensee Meeting 93-111 W/Util on 930902 to Discuss Plant Operator Training Program ML20202H7351993-07-22022 July 1993 Informs That Investigation Re Potential Wrongdoing Initiated by OI on 930223,under Case 1-93-008 Being Closed.Evaluation of Facts & Circumstances Surrounding Issues Indicate That No Underlying of Regulatory Requirements Exist ML20044G4131993-05-21021 May 1993 Submits Daily Highlight.Notification of 930527 Meeting W/ Util in Rockville,Md to Discuss Licensing Action Schedules & Priorities ML20034G7311993-03-0808 March 1993 Notification of 930324 Meeting W/Util & NUMARC in Rockville,Md Re Licensee Presentation to NRC Describing Plans to Revise Emergency Action Levels 1999-07-12
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20212F5401999-09-24024 September 1999 Staff Requirements Memo Re 990924 Affirmation Session Concerning SECY-99-236, Firstenergy Nuclear Operating Co, Local 29 Petition to Waive Time Limits in 10CFR2.1305 & Suppl Comments ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20206H3921999-05-0606 May 1999 Notification of 990518 Meeting with Util in Rockville,Md to Discuss Util Presentation of Technical Evaluation Performed in Support of License Amend Request Which Would Revise TS Limiting Safety Sys Setpoints to Be More Conservative ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20199J0641998-12-30030 December 1998 Notification of 990119 Meeting with Duquesne Light Co in Rockville,Md to Discuss Status of Licensing Actions/ Activities Currently Being Reviewed by NRC & of License Amend Requests Expected to Be Submitted in Near Future ML20198G9941998-12-22022 December 1998 Forwards Request for Addl Info Re Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor Operated Valves Program ML20196H1391998-12-0404 December 1998 Informs That Encl RAI Was Transmitted on 981204 to F Ferri of Dl.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20195G4501998-11-10010 November 1998 Rev 1 to Notification of Significant Licensee Meeting 98-87 with Util on 981116 to Discuss NRC Presentation of Osti Exit Followed by Util Presentation on Unit Restart Plant Performance ML20155K3451998-11-0505 November 1998 Notification of Significant Licensee Meeting 98-87 with Util on 981116 in Beaver Valley Power Station,Emergency Response Facility Conference Room A,For NRC Presentation of Osti Exit & Dl Presentation on Unit Restart Plan Performance ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154D5611998-10-0505 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980817-21 ML20154D4481998-10-0505 October 1998 Forwards Exam Rept with as Given Written Exam for Test Administered on 980817-21 at Unit 2,for Processing Through Nudocs & Distribution to NRC Staff IR 05000334/19983001998-08-17017 August 1998 Forwards NRC Operator Licensing Exam Rept 50-334/98-300OL for Exam Administered on 980420-24 & 0518 ML20236X5981998-08-0404 August 1998 Notification of 980820 Meeting W/Util in Rockville,Md to Discuss Proposed Submittal of Improved Std TS ML20236K9051998-07-0101 July 1998 Notification of Significant Licensee Meeting 98-65 W/Util on 980716 to Discuss Plant Status & Preparations for Plant Restart ML20236N6351998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples1998-06-0505 June 1998 Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples ML20247D1541998-05-0505 May 1998 Notification of 980519 Meeting W/Duquesne Light Co in Shippingport,Pennsylvania to Discuss NRC SALP of Beaver Valley Power Station for Period of 960929-980321 ML20248L6621998-03-0505 March 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam for Test Administered on 971215-18 at Facility ML20248L6081998-03-0505 March 1998 Forwards Exam Rept W/As Given Written Exam for Test Administered on 971215-18 at Facility ML20212G4791997-10-28028 October 1997 Forwards SER Accepting Licensee 970213 Request Re Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20149G3261997-07-18018 July 1997 Notification of 970805 Meeting W/Util in North Bethesda,Md to Discuss Plans & Schedules for Resolution of 10CFR50.61 Updated Info for Pressurized Thermal Shock Evaluation ML20149D2851997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317-21 IR 05000334/19970031997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam Repts 50-334/97-03OL & 50-412/97-03OL (Including Completed & Graded Tests) for Tests Administered on 970317-21 & 970428- 0502 ML20149D2891997-07-14014 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317 ML20148E1881997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-60 W/Util on 970623 to Discuss Surveillance Test Program Apparent Violations ML20138Q1171997-02-27027 February 1997 Rev 1 to Notification of Significant Licensee Meeting 97-20 W/Util on 970307 in King of Prussia,Pa to Discuss Plant Configuration Control Issues Related to Component Mispositionings ML20135D1271997-02-20020 February 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970304 to Discuss Plant Configuration Control Issues Re Component Mispositionings ML20133D6221997-01-0202 January 1997 Rev 3 to Notification of Significant Licensee Meeting 96-128 W/Util in King of Prussia,Pa Re Predecisional EC to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20132E7361996-12-17017 December 1996 Notification of Significant Licensee Meeting 96-462 Rev 2 W/Util on 961230 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4601996-12-0606 December 1996 Notification of Significant Licensee Meeting W/Util on 961219 to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20149M4921996-12-0404 December 1996 Notification of 961219 Significant Licensee Meeting 128 W/Util in King of Prussia,Pa to Discuss Plant Operation W/Two of Three Power Operated Relief Valve Block Valves Shut for Extended Period of Time ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review1996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20141M6491996-10-0404 October 1996 Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review ML20129E7161996-09-30030 September 1996 Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484 ML20059K7871994-01-0606 January 1994 Notification of Enforcement Conference 94-06 W/Util on 940118 to Discuss EDGs Solid State ATC Timer/Relays ML20059C3261993-12-28028 December 1993 Discusses Suggestion for More Efficient Use of NRC & Licensee Resources NUREG-1231, Forwards Documents Referenced in Suppl 16 to NUREG-09331993-11-29029 November 1993 Forwards Documents Referenced in Suppl 16 to NUREG-0933 ML20058E4201993-11-26026 November 1993 Notification of Significant Licensee Meeting 93-157 W/Util on 931202 to Discuss AIT Exit Meeting ML20059K5501993-11-0808 November 1993 Notification of Significant Licensee Meeting 93-146 W/Util on 931115 in King of Prussia,Pa to Discuss Training Program Improvement Following Initial Exam Results from May 1993 ML20059K2711993-11-0303 November 1993 Discusses 931027 Operating Reactors Events Briefing Conducted to Inform Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931020. List of Attendees Encl ML20059G1271993-11-0202 November 1993 Notification of Significant Licensee Meeting 93-139 W/Util on 931119 in King of Prussia,Pa to Discuss Enforcement Conference Re Open Containment Penetration During Refueling ML20059J4471993-11-0202 November 1993 Notification of Cancellation of 931110 Meeting W/Util in Rockville,Md to Discuss Util Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20059H1381993-11-0202 November 1993 Notification of 931110 Meeting W/Util in Rockville,Md to Discuss Dlc Safety Assessment Program & Basis for Schedule Extension for Testing of MOVs ML20056G8161993-08-23023 August 1993 Notification of Significant Licensee Meeting 93-111 W/Util on 930902 to Discuss Plant Operator Training Program ML20202H7351993-07-22022 July 1993 Informs That Investigation Re Potential Wrongdoing Initiated by OI on 930223,under Case 1-93-008 Being Closed.Evaluation of Facts & Circumstances Surrounding Issues Indicate That No Underlying of Regulatory Requirements Exist ML20044G4131993-05-21021 May 1993 Submits Daily Highlight.Notification of 930527 Meeting W/ Util in Rockville,Md to Discuss Licensing Action Schedules & Priorities 1999-09-24
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AUG2 3 S Central Files HFEB Files VMoore HFEB Members MEMORANDUM FOR:
George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing FRW1:
Voss A. Moore, Chief Human Factors Engineering Branch Division of Human Factors Safety
SUBJECT:
IN-PROGRESS AUDIT MEETING OF BEAVER VALLEY P0miER STATION, UNIT 2, DETAILED CONTROL R00ft DESIGH REVIEW Duquesne Light Company (DLC) is required by Supplement I to NUREG-0737 to conduct a Detailed Control Room besign Review (DCRUR) of the Beaver Valley Power Station Unit 2 (BY-2) prior to licensing.
The staff has reviewed and consnented on the BV-2 Program Plan and has conducted a brief on-site in-progress audit July 26 and 27,1984.
Results of tne audit indicate that the 8V-2 DCRDR is proceeding in a manner that will satisfy tne requirements of Supplement I to NUREG-0737.
The staff did identify several concerns that were brought to the attention of the applicant. A major concern is in the differences between the Unit 1 and Unit 2 control rooms since the applicant indicated a desire to apply for dual-unit licensing of its operators.
Those differences will require careful evaluation to detemine if a potential exists for inducing operator error.
Although the Function and Task Analysis process appears to oe satisfactory, the staff is concerncd that (1) a human factors specialist is used cnly as a reviewer and has no direct input to the analysis, and (2) selected event sequences to be evaluated may not cover all emergency operations.
A full evaluation of the BV-2 DCRDR will be accomplished following subuittal of the Sunnary Report, scheduled for June 1,1985.
Contact:
R. J. Eckenroda x24862 Y
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George W. Knighton AUG 2 31984 The enclosed report presents the results of the in-progress audit meeting of the DCRDR program for BV-2.
Please transmit the report to DLC for their use.
Voss A. Moore, Chief Human Factors Engineering Branch Division of human Factors Safety
Enclosure:
As Stated cc:
M. Ley W. Troskoski, R. I R. Peterson, LLNL D. Beckham R. Starostecki
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Nuclear Regulatory Commission In-progress Audit Report Beaver Valley Power Station, Unit 2 BACKGROUND Duquesne Light Company (DLC) is performing a Detailed Control Room Design Review (DCRDR) of the Beaver Valley Power Station, Unit 2 (BY-2) in accordance with the requirements of Supplement 1 to NUREG-0737.
By letter dated August 8,1983 DLC submitted a DCRDR Program Plan. Staff review comments on the plan were submitted to the Division of Licensing December 12, 1983, along with a request for an in-progress audit meeting when the applicant was beginning the task analysis phase of the DCRDR.
DISCUSSION An onsite in-progress audit of the DCRDR activities was cnducted by the staff on July 26 and 27, 1984. The audit consisted of a visit to the BV-2 j
control room to review its status and similarity to the Unit 1 control room, and a meeting to discuss the details of the applicant's review processes as requested by the staff in a letter dated January 23, 1984.
Control Room Visit s
The control room visit verified that there are many differences between Unit 1 and Unit 2 control rooms.
The importance of these differences and their significance with respect to operator performance and dual unit licensing of operators must be carefully investigated. A report is being prepared by DLC which documents the distance deviation in the location of each control and display in one unit with respect to the like control and display in the other unit. This report, however, does not take into account the direction of the relocation and reversals in position can occur.
For example, two switches may be shown.in the report as having been moved only four inches each.
If the four-inch move is in opposite directions the result may be a reversal of switch location with respect to the other unit, or a very large distance between switches in which case it is likely that something else has been installed.
This type of difference between units can be expected to leao to operator error.
The staff audit verified that this type of difference does exist.
Another significant difference exists between annunciator systems.
Unit 2 has approximately one half the number of tiles as Unit 1 and the tile identification scheme is different between units.
Several video displays are to be installed in Unit 2 in place of annunciator panels still in Unit 1.
New instrumentation has been developed since BV-1 went into operation and some of this new equipment (e.g., automatic bypassed and Inoperable Status Indications, ICC instrumentation) is being installbd in Unit 2.
The Boron Injection System is different and it appeared that some instrumentation related to boron concentration has been deleted from Unit 2.
l
o CRDR Meeting The agenda and list of attendees for the CRDR meeting are provided in l
Attachments 1 and 2.
The purpose of the meeting was for DLC to present responses to the NRC review coments to the Program Plan for BV-2, and to 1
review, in detail, the DLC System Review and Task Analysis (SRTA) j methodology.
The staff's Program Plan comments, addressed by DLC at the meeting, were in the following areas i
1.
Qualifications of review team members and level of involvement in review tasks 2.
Human factors specialists' involvement in detailed planning 3.
Need for more than one human factors specialist in the many review tasks 4.
Description of the data base and data base management system 5.
Description of the standardized fonns/ checklists to be used 6.
DLC reference material should include conventions and standard abbreviations 7.
Independence of function and task analysis (F&TA) from other review tasks 8.
Everyts to be considered in the F&TA 9.
Event-based vs function-based emergency operating procedures (E0Ps) 10.
Specific E0Ps to be considered in the F&TA 11.
Information and control requirements and characteristics to be detennined from F&TA 12.
Function and task analysis methodology 13.
Control room inventory of instrumentation 14.
Control room inventory forms 15.
Verification methodology and tools
- 16. Human factors guidelines and criteria to be used in the control room survey
17.
Process for identifying and recording human engineering discrepancies (HEDs)
- 18. State of control room in which survey will be conducted l
19.
Implementation schedule for correction of HEDs l
20.
HED assessment methodology
- 21. Selection of design improvements traceability i
22.
Criteria for selection of design improvements
- 23. Methodology to ensure that improvements correct the HED without introducing new HEDs
- 24. Approach to coordinating the DCRDR with other post-TMI activities 25.
Control room modifications resulting from post-TMI actions.
With the exception of item No. 11, all responses were satisfactory to the staff.
The oetails of the definition of information, display, and control requirements (Item No. 11) have not yet been finalized by DLC.
CONCLUSION i
Based on the presentations made at the DCRDR meeting and the documentation reviewed, it is the staff's opinion that DLC is proceeding on a program of control room review and improvement that will enhance the safety of operations in BV-2.
l The major concern resulting from this meeting was that, because of the desire to dual-license operators on both BV 1 and BV-2, a concerted effort be made to coordinate design improvements between control rooms.
Differences already exist between the control rooms and their significance, with respect to operator performance, needs to be determined.
Related to this concern is the fact that the plant specific simulator will be of the Unit 1 design.
Since Unit 1 already has experienced operators, it appears that more benefit would be gained by having a Unit 2 simulator since all operators will need training on Unit 2.
The Function and Task Analysis process appears to be satisfactory.
Two concerns still exist:
- 1) that a human factors specialist is used only as a reviewer and does not have direct input into the analysis, and 2) that i
sequences not on the current list (e.g., Station Blackout) will be identified and evaluated.
TENTATIVE AGENDA Beaver Valley Unit 2 Detailed Control Room Design Review l
In-Progress Audit DATE:
July 27, 1984 l
TIME:
8:00 a.m. - 1:30 p.m.
LOCATION:
Robinson Plaza II Large Conference Room I.
Introduction to BVPS-2 Control Room Design Review A.
Presentation of the following:
1.
CRDR organization (Core and Support Team) 2.
Detailed implementation flow diagram 3.
Overall schedule II. NRC Comments to Program Plan l
A.
Discuss DLC responses (except for SRTA related) l B.
Present and discuss the following:
l l
1.
Data collection forms l
2.
HED evaluation criteria l
III. SRTA Presentation l
A.
SRTA schedule B.
SRTA methodology C.
Discuss NRC comments /DLC responses (SRTA related)
IV.
Conclusion A.
Sumary remarks B.
Address any additional NRC coments I
PERSONNEL IN. ATTENDANCE BEAVER VALLEY POWER STATION UNIT 2 N mC 0F PROJECT CONTROL ROOM DESIGN REVIEW - NRC MEETING Pup ost or uttTING ROBINSON PLAZA g,7g
,ygy,y 77. igat LocArfoN NWC ORGANIZATION T I TLE/ RESPONSI BI LI TY idm.rce. T. TALLEY ESSEK HF SPEGAUST-Co2E TEM men 86Q i % fc q k'c u w y id u 2..
sen, t cuc.uote -cece cum YILLTAM 0.
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