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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
[Table view] |
Text
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UNITED STATES v,
g NUCLEAR REGULATORY COMMISSION
- j WASHINGTON, D. C. 20555
%,,,,,/
WL 3 1985 Docket No.:
50-412 APPLICANT:
Duquesne Light Company FACILITY:
Beaver Valley Power Station, Unit 2
SUBJECT:
DIRECTOR, DIVISION OF LICENSING, DECISION ON THE APPEAL OF THE REQUIREMENTS ON FIRE SUPPRESSION IN THE CABLE SPREADING ROOM I.
Introduction a.
Background on this Backfit Appeal Issue i
In the draft Safety Evaluation Report (SER) for Beaver Valley Power Station 2 (BVPS-2) dated February 23, 1984, the staff had informed Duquesne Light Company (DLC) that the automatic, total flooding, carbon dioxide (CO ) primary fire suppression system in the cable spreading room 2
with backup permanent hose stations did not conform to the Standard Review Plan (SRP). After reviewing the draft SER, the applicant, in their letter to the NRC dated May 30, 1984, identified the staff's requirements on fire suppression in the cable spreading room as a backfit l
referencing NRC Manual Chapter 0514 (0514) issued as Generic Letter 84-08 dated April 4, 1984.
DLC requested that the staff requirements be submitted to NRC j
management for review.
On June 18, 1984, the Assistant Director of Licensing (ADL) met with DLC to discuss the status of significant licensing issues, and on September 19, 1984, the NRC sent a letter to DLC to establish an appeal meeting on fire suppression in the BVPS-2 cable spreading room.
An appeal meeting was established for September 26, 1984, but due to misunderstanding of the approach to be used at the meeting, the parties were unsuccessful in holding an appeal meeting.
By telephone on October 1, 1984, the ADL discussed with DLC the
~
procedure for future appeal meetings in order to closely follow the procedures of 0514, and a follow-up meeting was held with DLC on October 5, 1984 to further discuss backfit and appeal procedures.
3 By letter dated November 6, 1984, the ADL provided information to the applicant on requirements and safety significance for nine backfit items including
)
fire suppression in the cable spreading room.
By letter dated November 20, 1984, DLC requested further clarification of the ADL information.' Clarifica-tion was provided by the ADL on January 10, 1985.
On February 13, 1985, the applicant documented their final position on fire suppression in the BVPS-2 1
i
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8509010275 850703 PDR ADOCK 05000412 F
PDR i
l i
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cable spreading room and requested that a backfit appeal meeting be held in accordance with 0514.
The first stage backfit appeal meeting was held on February 26, 1985.* As a result of this appeal meeting, the Director, Division of Licensing decided a site visit was necessary to obtain first hand information to complement the information provided in the appeal meeting.
The site visit was made on March 13, 1985.
II.
Decision a.
Procedural Requirements On March 10, 1982, the Commission approved the final rule, 10 CFR Part 50.34(g), "Conformance with the Standard Review Plan (SRP)".
This rule requires applicants, whose applications were docketed after May 17, 1982, to identify and describe "all differences in design features, analytical techniques and procedural measures proposed for a facility and those corresponding features, techniques and measures given in the SRP acceptance criteria. Where such a difference exists, the evaluation shall discuss how the alternative proposal provides an acceptable method of complying with those rules or regulations of Commission, or portion thereof, that underlie the corresponding SRP acceptance criteria." Since BVPS-2 was docketed May 18, 1983, the rule applies to BVPS-2.
The applicant and staff at the February 28, 1984 backfit appeal meeting agreed that this requirement applied to BVPS-2 In the case of this fire suppression in the cable spreading room issue, the staff expected DLC to address the procedural requirements of the rule by providing the justification for their deviation from the SRP. DLC's position as stated in their May 30, 1984 letter to the NRC, was that the fire suppression system in BVPS-2's cable spreading room conforms to the SRP therefore, there is no deviation, hence, no justification is required.
The lack of understanding of what was required was due to the difference in interpretation of the SRP.
The staff stated that automatic water system should be utilized (also the use of foam is acceptable) as the primary suppression and anything but water (or foam) required a justification for the deviation.
DLC position was that gas systems were included in the SRP because the SRP mentions the need to compensate for losses through drains when gas systems were installed and that gas systems had been accepted by the staff at numerous operating reactors.
^ According to 0514, the first stage of appeal would be held by the Division of Licensing at the Assistant Director's level, followed by Director, Division of Licensing, for a second stage of appeal if needed.
The Director, Office of Nuclear Reactor Regulation, directed that the first stage of the BVPS-2 backfit appeal shall be held at the Division Director's level so that the appeal process would be moved immediately to a higher NRR management level and would eliminate one level of VRR appeal.
.-4
~
~
y
- t A decision is required on which is the better interpretation in order to decide whether or not a deviation from the SRP exists.
Based on the staff presentation in the February 28, 1985 appeal meeting, the past practices in staff reviews and considering the fact that the SRP is a staff document developed to ensure uniformity of staff safety reviews, I am persuaded that the better interpretation of the SRP is that utilization of only a gas system a deviation from the SRP.
Therefore, a justification for the deviation must be provided.
For BVPS-2 those items that required justification are as follows:
1.
In the BVPS-2 cable spreading room, deviation from the SRP by using automatic gaseous fire suppression as the primary system versus automatic water suppression.
2.
In the BVPS-2 cable spreading room, the deviation from the SRP 3 foot by 8 foot access criteria in certain locations.
For example, there are areas where movement in passageways is partially blocked by horizontal girders, where low overhead areas require an individual to stoop in order to continue forward and where aisles between cable trays require care to avoid snagging fire fighting equipment on structural protusions.
The information in DLC's February 13, 1985 submittal, the information provided in the transcribed backfit appeal meeting of February 28, 1985 along with the first hand information I obtained from the March 13, 1985 site visit have provided the information needed to satisfy the 10 CFR 50.34(g) procedural requirement.
The acceptability of the DLC justification is addressed in the next section.
b.
Technical Requirements The staff's position is that, in accordance with Section 9.5.1 of the SRP, primary fire suppression in the cable spreading room should be an automatic water system.
The staff noted that there are reasons why and how water became the agent for primary fire suppression.
These reasons have developed from lesssons learned from experiences on other fires, for example, the Browns Ferry fire.
These experiences have identified CO, asphyxiation and toxicity concerns, reduced CO., availability concerns (system may need to be shut off while people are wBrking in areas where a C0 system has been installed) and that C0 maybe somewhat less reliable than p
7 sprinklers because it does not remove too much heat.
DLC's position, as documented in the transcribed minutes of the February 28, 1985 appeal meeting, is:
"that the primary fire suppression for the cable spreading room is an automatic total flooding CO system with hose stations and fire brigade.as.the backup to 2
the CO system.
2
- SRP Section C.7.c. states "the primary fire suppression in the cable spreading room should be an automatic water system....
When gas systems are installed, drains should have adequate seals or the gas extinguishing systems should be sized to compensate for losses through the drains."
i
n - '
DLC believes that the C0 g
7 system with the hose stations as backup provides an equivalent level of safety for the specific conditions of the Beaver Valley 2 cable spreading room.
The level of safety is achieved by the defense-in-depth approach.
More specifically, DLC has an alternate shutdown capability totally separated and electrically independent from the cable spreading room, and this alternate shutdown system can bring the plant to a safe shutdown condition.
The CO system and its backup hose stations are all designed to meet NFPA 2
codes And, finally, Duquesne Light contends that it has adequate access and fire fighting conditions in the cable spreading room to extinguish any fire hazard in that room."
Based on my review of the applicant's February 13, 1984 letter, from information presented in the February 28, 1985 backfit appeal meeting on fire suppression in the cable spreading room, from first hand information I gathered in the March 13, 1985 site visit and from information available to me in technical reports, I note the following factors which fe med the basis for my decision.
1.~
The National Fire Protection Association Code-12 (NFPA-12) recog-nizes and recommends the use of total flooding CO systems, similar 2
to the type being used in BVPS-2, for suppressing cable insulation fires.
It should be noted that the National Fire Protection Asso-ciation Code is a nationally recognized standard accepted by the NRC.
Members of the Association are from industry, government and testing laboratories.
2.
BVPS-2 has a backup manual fire fighting capability with hose stations and a trained fire brigade.
3.
Cable fire tests run by Sandia and reported in NUREG CR/3656 showed that CO was an adequate suppression agent in extinguishing cable fires.
2 4.
The BVPS-2 cable spreading room area ~is separated by fire rated barriers from the rest of the plant and will contain a total burnout of insitu combustibles (FSAR, Amendment 2, Table 1).
4 5
For any fire in the cable spreading area, safe shutdown should not be affected because alternative shutdown capability is available independent of the cable spreading area (FSAR).
6.
Early warning detection is provided to alert the fire brigade (FSAR).
7.
The northwest corner of the cable spreading room has a very dense concentration of cable trays and direct access to this area by the fire brigade is limited.
8.
On my site visit of March 13, 1985, I observed two exercises in which fire i
fighters managed to go through the most difficult passageways in the cable spreading room. The fire fighters were fully equipped in their appropriate gear and on one of the two exercises their face masks were darkened simulate a blackout due to heavy smoke. With face masks darkened, the fire fighters relied extensively on the human factor considerations for accessibility under these more demanding conditions.
III. Conclusion Upon reviewing the information presented by the staff and DLC, I have concluded that the automatic total flooding C0 system with hose stations 7
and fire brigade as the backup to the CO,3 system is adequate except as listed below. Furthermore, the fire protection program in the BVPS-2 cable spreading room has in general, adequate defense-in-depth.
Also, I conclude that personnel accessibility in the BVPS-2 cable spreading room, although clearly not close to being ideal, was demonstrated for the i
existing passageways. However, in order to provide for reasonable assurance j
that adequate accessibility exists for passageways during periods of limited visibility, DLC should implement the recommendations provided by DLC's Human Factors expert in their letter to the NRC dated April 25, 1985. Furthermore, the temporary ramps and platforms needed to facilitate passage should be replaced with permanent installations that are of sufficient size and design to allow safe passage of the fire fighter. Training of the fire brigade should include walkthroughs in full equipment with anticipated conditions of limited visibility, impaired comunications and high temperature. Simulation of these conditions either in the cable spreading room or at a fire training facility would be acceptable.
Based upon first hand information from the March 13, 1985 site visit and J
the information provided by the NRR and DLC staff, I do not conclude 3
there is reasonable assurance of hose stream access into the dense concentration of cable trays in the northwest corner of the cable spreading room. Therefore, I consider this a deviation from the SRP and a justificaion acceptable to the staff is required.
IV. Appeals Decisions made herein may be appealed to the Director, Office of Nuclear
Originst signed by Distribution Hugh L Thompson, Jr.
<EEEE7fTE% Attorney, OELD NRC PDR GWKnighton HDenton Hugh L. Thompson, Director LPDR VNerses DEisenhut Division of Licensing NSIC JLee RCushman LB3 Readfjig JRTourtellote MJClausen GMyer DLfl SHChestnut JKnight HThompson:mj VStello TNovak 7/ 3 /85 ThCox FMiraglia PPolk WJohnston JAustin i
q J '.
- Reaver Valley Mr. John J. Carev Vice President,' Nuclear Duquesne Light Company Robinson Plaza Building, No. 2, Suite 110 PA Route 60 Pittsburgh, Pennsylvania 15205 Gerald Charnoff, Eso.
Mr. R. E. Martin, Mananer Engineering Jay E. Silberg, Eso.
Beaver Valley Two Proiect Shaw, Pittnan, Potts & Trowbridge Duquesne Light Company 1800 M Street, N.W.
Robinson Plaza Buildina No. 2, Suite 110 Washington, DC 20036 PA Route 60 Pittsburgh, Pennsylvania 15205 Mr. C. W. Ewing, Quality Assurance Zori Ferkin Manager Assistant Counsel Quality Assurance Department Governor Energy Council Duquense Light Company 1625 N. Front Street P. O. Box 186 Harrisburg, PA 15105 Shippingport, Pennsylvania 15077 Mr. John J. Carey Vice President, Nuclear Duquense Light Company Director, Pennsylvania Emergency P. O. Box 4 Management Agency Shippingport, Pennsylvania 15077 Room B-151 Transportation & Safety Building Harrisburg, Pennsylvania 17120 Mr. T. J. Lex Mr. Thomas Gerusky Westinghouse Electric Corporation Bureau of Radiation Protection Power Systems PA Department of Environmental l
P. O. Box 355 Resources Pittsburgh, Pennsylvania 15230 P. O. Bax 2063 i
Harrisburg, Pennsylvania 17120 l
Mr. P. RaySircar Stone & Webster Engineering Corporation BVPS-2 Records Management Supervisor
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P. O. Box 2325 Duquesne Light Company Boston, Massachusetts 02107 Post Office Box 4 i
Mr. Glenn Walton U. S. NRC John A. Lee, Esq.
P. O. 181 Duauesne Light Company Shippingport, Pennsylvania 15077 1 0xford Centre 301 Grant Street Mr. Thomas E. Murley, Regional Admin.
Pittsburgh, Pennsylvania 15279 U. S. NRC, Region I 631 Park Avenue King of Prussia, Pennsylvania 15229 i
i 1
1 1
9*
/ *, a Mr. E. F. Kurtz, Jr., Manager Regulatory Affairs Beaver Valley Two Proiect Duquense Light Company Robinson Plaza Buidling No. 2 Suite #210
'PA Route 60 Pittsburgh, Pennsylvania 15205