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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212F5461999-09-23023 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 ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility ML20138Q5391997-03-0404 March 1997 Forwards Documents from 970131,mgt Meeting Between Plant & NRC to Be Sent to PDR ML20134K7501997-02-12012 February 1997 Notification of 970224 Meeting W/Util in Rockville,Md to Discuss Equipment Qualification Based on Recently Revised Containment Analysis 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 ML20147C4881997-01-30030 January 1997 Forwards Four Documents Given to Region III Staff at Meeting on 970124 W/Plant Mgt to Be Placed in PDR ML20129B3411996-08-0505 August 1996 Discusses Review to Estimate Production of Hydrogen by Radiolysis in Sf Storage Cask,Concluding That Radiolysis Not Significant Contributor to Hydrogen Gas Production at Point Beach & Not Expected to Be Source for Other Sf Storage Sys ML20059G7481994-01-11011 January 1994 Notification of 940131 Meeting W/Util in Rockville,Md to Discuss Wepco Upcoming Insp of Control Rod Drive Vessel Penetrations ML20059B1831993-10-25025 October 1993 Notification of 931103 Meeting W/Util in Rockville,Md to Discuss Diesel Generator Installation Project ML20057F1691993-10-0808 October 1993 Notification of 931008 Meeting W/Util in Rockville,Md to Discuss TS Amend Request Re Reactor Coolant Sys Flow ML20059B3261993-09-14014 September 1993 Forwards Llnl 1993 Probabilistic Seismic Hazard Estimates for Plant,Per Util 930908 Request ML20056F3431993-08-10010 August 1993 Provides Summary of Plant IPE Submitted on 930630,per GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20056E9361993-08-0909 August 1993 Discusses Safety Significance of Corrective Actions Taken by Licensee in Response to IE Bulletin 86-003 ML20125B6091992-12-0303 December 1992 Requests Review of Due Date.Request for Revised Due Date Must Have Prior Approval from Appropriate Associate Director or NRR Deputy Director & Must Include Valid Justification ML20128A1971992-12-0101 December 1992 Advises of Closeout of TACs M71758 & M71759, Point Beach 1 & 2 - Reactor Vessel Upper Shelf Energy, Per GL 88-11 & Rev 2 to Reg Guide 1.99, Radiation of Reactor Vessel Matls ML20059A5511990-08-17017 August 1990 Notification of 900905 Meeting W/Util in Rockville,Md to Discuss Util Plans for Installation of Addl Emergency Diesel Generators & Extra Station Batteries ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl ML20248C7551989-08-0303 August 1989 Notification of 890810 Meeting W/Util in Rockville,Md to Discuss Plant Reactor Vessel Integrity ML20206J4561988-11-22022 November 1988 Notification of 881201 Meeting W/Util in Rockville,Md to Discuss Containment Liner Leak Chase Channel Venting ML20151H8881988-04-12012 April 1988 Requests That Div of Reactor Safety Take Lead in Regional Followup Re Problem at Plant & Potential Generic Implications ML20151A2271988-03-28028 March 1988 Forwards Info Package Re Backround Info for Commissioner Carr 880404 & 05 Visits to Kewaunee & Point Beach Sites, Respectively ML20155K2001988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl1988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20154H0451988-03-0202 March 1988 Notification of 880331 Meeting W/Numarc in Rockville,Md to Discuss Differences Between Sandia & NUMARC Analyses of DHR at Plant ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20149G7871988-02-11011 February 1988 Forwards Proprietary WCAP-11666 Re Evaluation for Vibration Induced Fatigue of Steam Generator Tubes.Licensee Committed to Enhanced Primary to Secondary Leakage Reduction Program, Per Util & NRC 871125 Approval.Rept Withheld ML20237D8041987-12-17017 December 1987 Discusses Steam Generator Temp/Pressure Limitations Based on Info from Plant Resident Inspectors.Plant Tech Specs Do Not Adequately Address Max Permissable Pressure for Corresponding Temp ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20236S3591987-11-16016 November 1987 Forwards Licensee Responses to 10CFR21 Notification Re Potential Violation of Component Cooling Water Containment Isolation Function,Per 871106 Request 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 ML20236F0781987-10-28028 October 1987 Forwards NRR Input for SALP Board Meeting Scheduled for 871123 Re Plant ML20236A5401987-10-15015 October 1987 Forwards Draft NRR SALP Input Covering Licensing Activities for Apr 1986 - Sept 1987.Performance Rating of Category 2 Assigned.Comments Received by 871023 Will Be Considered for Incoporation in Final Repts 1999-09-23
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212F5461999-09-23023 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 ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility ML20138Q5391997-03-0404 March 1997 Forwards Documents from 970131,mgt Meeting Between Plant & NRC to Be Sent to PDR ML20134K7501997-02-12012 February 1997 Notification of 970224 Meeting W/Util in Rockville,Md to Discuss Equipment Qualification Based on Recently Revised Containment Analysis 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 ML20147C4881997-01-30030 January 1997 Forwards Four Documents Given to Region III Staff at Meeting on 970124 W/Plant Mgt to Be Placed in PDR ML20129B3411996-08-0505 August 1996 Discusses Review to Estimate Production of Hydrogen by Radiolysis in Sf Storage Cask,Concluding That Radiolysis Not Significant Contributor to Hydrogen Gas Production at Point Beach & Not Expected to Be Source for Other Sf Storage Sys ML20059G7481994-01-11011 January 1994 Notification of 940131 Meeting W/Util in Rockville,Md to Discuss Wepco Upcoming Insp of Control Rod Drive Vessel Penetrations ML20059B1831993-10-25025 October 1993 Notification of 931103 Meeting W/Util in Rockville,Md to Discuss Diesel Generator Installation Project ML20057F1691993-10-0808 October 1993 Notification of 931008 Meeting W/Util in Rockville,Md to Discuss TS Amend Request Re Reactor Coolant Sys Flow ML20059B3261993-09-14014 September 1993 Forwards Llnl 1993 Probabilistic Seismic Hazard Estimates for Plant,Per Util 930908 Request ML20056F3431993-08-10010 August 1993 Provides Summary of Plant IPE Submitted on 930630,per GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20056E9361993-08-0909 August 1993 Discusses Safety Significance of Corrective Actions Taken by Licensee in Response to IE Bulletin 86-003 ML20125B6091992-12-0303 December 1992 Requests Review of Due Date.Request for Revised Due Date Must Have Prior Approval from Appropriate Associate Director or NRR Deputy Director & Must Include Valid Justification ML20128A1971992-12-0101 December 1992 Advises of Closeout of TACs M71758 & M71759, Point Beach 1 & 2 - Reactor Vessel Upper Shelf Energy, Per GL 88-11 & Rev 2 to Reg Guide 1.99, Radiation of Reactor Vessel Matls ML20059A5511990-08-17017 August 1990 Notification of 900905 Meeting W/Util in Rockville,Md to Discuss Util Plans for Installation of Addl Emergency Diesel Generators & Extra Station Batteries ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl ML20248C7551989-08-0303 August 1989 Notification of 890810 Meeting W/Util in Rockville,Md to Discuss Plant Reactor Vessel Integrity ML20206J4561988-11-22022 November 1988 Notification of 881201 Meeting W/Util in Rockville,Md to Discuss Containment Liner Leak Chase Channel Venting ML20151H8881988-04-12012 April 1988 Requests That Div of Reactor Safety Take Lead in Regional Followup Re Problem at Plant & Potential Generic Implications ML20151A2271988-03-28028 March 1988 Forwards Info Package Re Backround Info for Commissioner Carr 880404 & 05 Visits to Kewaunee & Point Beach Sites, Respectively ML20155K2001988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl1988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20154H0451988-03-0202 March 1988 Notification of 880331 Meeting W/Numarc in Rockville,Md to Discuss Differences Between Sandia & NUMARC Analyses of DHR at Plant ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20149G7871988-02-11011 February 1988 Forwards Proprietary WCAP-11666 Re Evaluation for Vibration Induced Fatigue of Steam Generator Tubes.Licensee Committed to Enhanced Primary to Secondary Leakage Reduction Program, Per Util & NRC 871125 Approval.Rept Withheld ML20237D8041987-12-17017 December 1987 Discusses Steam Generator Temp/Pressure Limitations Based on Info from Plant Resident Inspectors.Plant Tech Specs Do Not Adequately Address Max Permissable Pressure for Corresponding Temp ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20236S3591987-11-16016 November 1987 Forwards Licensee Responses to 10CFR21 Notification Re Potential Violation of Component Cooling Water Containment Isolation Function,Per 871106 Request 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 ML20236F0781987-10-28028 October 1987 Forwards NRR Input for SALP Board Meeting Scheduled for 871123 Re Plant ML20236A5401987-10-15015 October 1987 Forwards Draft NRR SALP Input Covering Licensing Activities for Apr 1986 - Sept 1987.Performance Rating of Category 2 Assigned.Comments Received by 871023 Will Be Considered for Incoporation in Final Repts 1999-09-23
[Table view] |
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From: Anthony Huffert To: WNP3.LLG Date: 4/18/97 3:58pm
Subject:
Point Beach Discussion Items As we agreed this morning during our meeti q, attached is a list of discussion items for Point Beach to review in preparation for the 4/28/97 meeting. PERB does not consider the list of items a request for additional information - perhaps those types of question will be generated after the 4/28/97 meeting. i PERB realizes that some of the questions were answered during our meeting today.
However, the licensee should be prepared to discuss those questions with the staff if they arise on 4/28/97.
Although the attached list does not contain questions on control room operator occupancy factors or the ECCS leak rate calculations (which were discussed during our meeting this morning), Point Beach should be prepared to discuss those items also.
Regarding the onsite meteorology issue, PERB would like to hold a telephone conference with Point Beach next Tuesday or Wednesday in preparation for the 4/28/97 meeting.
I Thank you again for the briefing this morning -
Tony Huffert 415-1081 4
ENCLOSURE 1 9704230265 970421 PDR ADOCK 05000266 p PDR
Discussion Items on Point Beach Amendment Requests Control Room
- 1. The 1984 III.D.3.4 analysis described 4 modes of operation for the control room. The licensee's III.D.3.4 analysis presented dose consequence I assessments for 2 modes of operation in their LOCA dose calculation: mode 3 (isclation and filtered recirculation) and mode 4 (filtered makeup and i unfiltered recirculation). It appears that mode 3 was originally the system l default for high radiation signals in the control room, but now mode 4 is the !
system default for that signal. It is noted that recent licensee analyses do not take into account mode 3 operation.
- a. Based on current tech specs and emergency operating procedures, what control room ventilation systen, alignments and what system initiation signals (e.g., control room high radiation, containment isolation, etc.) are used to actuate changes in the control room HVAC system for each cf the following design basis accidents: LOCA, steam generator tube rupture, control rod ejection, main steamline break and locker
- rotor?
- b. What signals and default system configurations were used for these accidents in the III.D.3.4 submittal?
- c. What changes has the licensee made to their modes of operation since 1 the III.D.3.4 submittal? What changes were made to make certain modes j
. of operation unavailable (e.g., mode 3) to mitigate the consequences of these accidents?
- d. What regulatory mechanism was used to review such changes? Were dose calculations made to support the licensee's changes?
- 2. Attachment 3 of the April 2, 1997 letter from the licensee states that a 1994 modification to the control room established a new flow-path from discharge of the control room recirculation fans to a mechanical room that houses HVAC equipment. This flow-path diverts about 700 cfm from the contro's room recirculation flow into the room. The licensee stated that this modification affects mode 2 operation sufficiently that previous analyses for mode 2 should be disregarded,
- a. What is the basis for the new inleakage value of 765.2 cfm for mode 2 operation? How did the licensee arrive at this new inleakage value?
Was it based on the supply of control room air into the mechanical room?
- b. What plant changes were made in 1994? How did the plant changes impact the calculated iodine protection factor (IPF) for mode 2?
- c. Was the mechanical room previously considered part of the control room envelope? If it was not, should it be considered part of the control room envelope, based on the 1994 changes to the system?
- d. What regulatory reviews were performed of these changes? Were dose calculations included to support the licensee's changes?
, 1 i
Discussion Items on Point Beach Amendment Requests (continued)
- 3. The April 2, .1997 letter from the licensee states the IPF for mode 4 is ;
approximately 10.5. . q j
- a. What should the current IPFs be for each of the four modes of i operation? l
- b. How have the IPFs changed since the III.D.3.4 submittal?
- 4. . .The III.D.3.4 analysis' assumed a 95% iodine removal efficiency for the charcoal filters, but the recent analysis assumed only a 90% efficiency.
- a. What should be assumed for charcoal adsorber efficiency based on the tech spec acceptance criteria, actual test protocol, and protocol conditions of temperature and relative humidity?
- b. Did the licensee take into account the system flowrate tolerances (plus or minus 10%) and in-place penetration and bypass leakage when calculating the IPF for each mode?
3 3
- 5. The control room volume increased from 55,195 ft to 65,243 ft since the l III.D.3.4 analysis was submitted. The increased volume may be due to changes '
made in the HVAC system in 1994, which "added" rooms to the control room j envelope. ],
- a. Was the change to the control room envelope volume analyzed by the licensee?
- b. Was this change to the control room reviewed by the NRC? If so, did NRC staff. take into account the additional heat load of the ;
computer room when considering mode 3 for long-term (30 days) i accident mitigation purposes? Did the licensee provide a heat load analysis to NRC for review?
]
- c. By what regulatory mechanism was this change reviewed? 'Were dose !
calculations included. in the licensee's analysis?
- 6. It's PERB's understanding that the licensee upgraded the supply of bottled air for the control room in the early 1990s. PERB/DRPM/NRR needs additional information about this system if credit for use of SCBAs is to be a consideration for dose reduction purposes.
- a. Is the system safety-grade?
- b. What is the source of fresh air?
- c. - How will and air bottles for SCBAs be refilled during an accident and who will perform this task?
- 7. Is the control room rad monitor on the outlet side of the main inlet fans capable of detecting radioactivity for accident mitigation purposes when the HVAC system operates in the recirculation or pressurization modes?
Discussion Items on Point Beach Amendment Requests (continued)
Auxiliary Buildina
- 1. The III.D.3.4 submittal credits the use of the auxiliary building HVAC for
. reducing the calculated doses from the LOCA ECCS pathway. The original submittal assumed a charcoal adsorber efficiency of 95%, but the recent submittal does not take credit for filtered releases.
- a. Is the system safety grade and can it be relied upon for accident mitigation purposes?
- b. Similar to question 4a above, what should be assumed for charcoal adsorber efficiency for this system?
- c. 45 the system capable of operating with an assumed loss of offsite power?
- 2. The licensee recently requested a change in the operation of the effluent radiation monitor for the auxiliary building, which may also serves to actuate the filtration system. How does the licensee's request affect the ability of the system to respond for accident mitigation purposes?
l l
1 l
Control Room HVAC [ heating, ventilation, and air conditioning] Design Mode 1 is the normal HVAC mode, in which 5% of the air flow (1000 cfm) is outside air and 95% (18,800 cfm) is recirculated air. Either fan W1381 and W13B2 supply flow of 19,800 cfm.
Mode 2, which originally consisted of 100% recirculated unfiltered air within the control room, is initiated either by a containment isolation signal or manually from the control room. This design changed when a supply vent was added, during a modification installed in 1994, that allows air from the i control room envelope to exhaust to the room housing the control room HVAC !
equipment. It also introduced a pathway for unfiltered inleakage from the computer room (which is connected to turbine building via ductwork) or I meci.anical equipment room.
Mode 3, manually initiated from the control room, allows filtered recirculated airflow via fans W14A or W14B.
Mode 4, initiated either by a control room radioactivity signal or by manual initiation, supplies 25% of the available flow (4,950 cfm 110%) with filtered <
outside air while the remaining 75% air flow is unfiltered recirculation '
(14,850 cfm).
Control Room Area Radiation Monitor RE-101 (located on the yest wall of control room indicates dose rates) has a range of 0.1 to 10 mr/hr. This monitor initiates a switch to Mode 4. RE-235 is a noble gas monitor and !
RE-234 is the control room iodine monitor (RE-234B control room iodine and noble gas sample system background monitor). Only monitor RE-235 initiates a switch to Mode 4.
Electrical supply per FSAR [ Final Safety Analysis Report] Table 8.2-2 accident unit and common loads include the control room filter fan and control room recirculation fan and an instrument air compressor. The auxiliary building i fans are not part of the EDG [ emergency diesel generator] loads.
Filterina Capability Filter banks 2-inch beds removal efficiencies are Elemental Iodine 90%
Methyl Iodine 90%
Particulate 99%
TS [ technical specification) testing requirements for the control room emergency filtration:
HEPA [high efficiency particulate air] filters and charcoal adsorbers shall be tested and analyzed at least once per year, or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation since the previous test, and following significant painting, fire or chemical release in the control room during filtration operation.
ENCLOSURE 2
4
. i e
\
i Cold D0P testing of the HEPA filter bank shall be performed after each l
! complete or partial replacement of HEPA filters, or after any structural j maintenance on the filter housing. D0P shall be at design velocity
- 20%.
! Per TS 15.3.12 Operability of the control room emergency filtration during j power operation and refueling operation, except as specified in 15.3.12.3 a below, the control room emergency filtration system shall be operable at all
]
times during power operation and refueling operation of either unit.
The results of in-place cold DOP and halogenated hydrocarbon tests, j conducted in accordance with Spec 15.4.11 on HEPA filter and charcoal adsorber banks shall show a minimum of 99% DOP removal and 99%
i halogenated hydrocarbon removal.
- The results of laboratory charcoal adsorbent tests shall show a minimum of 90% removal of methyl iodide. If laboratory analysis results for in-place charcoal indicate less than 90% methyl iodide removal, this specification may
, be met by replacement with charcoal adsorbent which has been verified to 2
achieve 90% minimum removal and which has been stored in sealed containers, and retesting the charcoal adsorber bank for halogenated hydrocarbon removal.
! The results of fan testing, conducted in accordance with specification j 15.4.11, shall show operation within 10% of design flow.
i From the date that the control room emergency filtration is made or
. found to be inoperable, reactor operation or refueling operation of
{ either unit may be continued only during the succeeding 7 days, unless the 1
, system is sooner made operable. l
- If the conditions in the paragraph above cannot be met, the operating i reactor (s) shall be brought to cold shutdown conditions within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> j and refueling operations shall be terminated as soon as practicable.
t j Basis: The control room emergency filtration is designed to filter control i room atmosphere and makeup air during control room isolation conditions. HEPA i filters are installed before the charcoal adsorbers to prevent clogging and to
- remove essentially all particulate material. Charcoal adsorbers are installed to reduce the potential intake of radioactive iodine to the control room
- during accident conditions. If the system is found to be inoperable, there is 3 no immediate threat to the cor. trol room and operation may continue for a
- limited period of time.
- As presented in January 16, 1997, letter, "If the methyl iodide efficiency i falls below 95%, the charcoal adsorbers will be replaced with fresh ones and j be' retested in accordance with applicable TS. DOP and Freon tests must show j >99% DOP and Freon removal.
I Based on a control room volume of 65,243 cubic feet, the inleakage as
- specified in the April 2,1997, submittal as 65.2 cfm for Mode I and 10.0 cfm
- for Mode 4. The licensee assumed 1065.2 cfm for unfiltered inleakage and makeup during Mode I which is greater than the 765.2 cfm that could be assumed in Mode 2.
i
~
)
Iodine Protection Factor (Attachment 3 to April 2, 1997, submittal) for Mode 4 ,
is 10.5 as modeled by the TITAN % computer code. This is less than the factor l 2
of 20 allowed in Murphy-Campe paper for a control room model that only includes filtered intake without any filtered recirculation. J i
l Modification Request (MR)85-025 replaced the original humidifiers to increase I the maximum water flow rate from the demineralized water system to 32.4 lbs/hr l to the control room and 8.3 lbs/ hour to the computer room. Highest humidity I
' was determined to be 55%. Reduced Mode 1 outside air makeup flow from 4950 cfm 1
to 1000 cfm. This did not affect Mode 4 flow of 4950 cfm. '
MR M-620 installed a stand-alone smoke and heat removal subsystem with a dedicated fan (W-13C) to remove heat and smoke from the cable spreading room, }
control room, or computer room. Damper controls exhaust air from one zone at !
a time. l MR 86-015 changed fire dampers from 1.5-hour rated to 3-hour rated dampers.
MR 87-003 installed gauge to monitor the control room to turbine hall dP. )
MR 87-168 changed the automatic water suppression system for the charcoal filter from a fusible link design to a manual actuation system using approved components.
l MR 93-041 installed in 1994 changed the following:
Changed the CR-HVAC system pneumatic controls to permit operation of control room chiller HX-38B, fail heating temperature control valves to bypass heat exchanger (HX-100A/B) and fail system dampers to Mode 4, following a loss of instrument air. To allow uninterrupted control of system modes, the modification also provided non-interruptible power to control panel C-67. The modification changed the original system configuration aligned to Mode 3 on receipt of a control room high radiation signal to align to Mode 4 to reduce the quantity of negative pressure ductwork subject to unfiltered inleakage, added the computer room to the control room zone, and supplied the mechanical equipment room with filtered air. Installed redundant, diesel-backed power to the control room supply and emergency filtration fans to increase system reliability and keep the operators from having to don air masks in a 4 potentially high temperature environment. )
MR E-237 revised the circuitry such that the CR-HVAC system would remain in Mode 2 when a containment isolation signal was reset.
MR IC-261 added noble gas monitors.
MR 90-103 removed ceiling tiles in control room to increase effective room volumes to address heat up resulting from station blackout.