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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217M6061999-10-20020 October 1999 Notification of 991102 Meeting with Util in Port Gibson,Ms to Discuss Bases for Emergency Preparedness Plan Change Submitted in & Supplemented by 990120 & 0715 Ltrs ML20212C0761999-09-15015 September 1999 Notification of 990930 Meeting with Firstenergy Nuclear Operating Co in Rockville,Md to Discuss Licensee Recent Submittal Requesting Five Percent Power Uprate IR 05000416/19990021999-09-10010 September 1999 Notification of Significant Licensee Meeting with Entergy Operations,Inc on 991018 to Discuss Listed Topics Identified in NRC Insp Repts 50-416/99-02,99-03 & 99-06 ML20211K7171999-09-0202 September 1999 Forwards Ineel Technical Ltr Rept, Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors Dated 990730.Rept Used for Review of BWROG Rept on Revised Source Term Accident Analysis ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211E1491999-08-23023 August 1999 Notification of Licensee Meeting with Util on 990830 to Discuss Recent Refueling Maint Outage ML20209G2421999-07-14014 July 1999 Notification of 990722 Meeting with License in Rockville, MD to Discuss Changes in EOI Licensing Organization Including Division of Responsibilities within New EOI Corporate Licensing Group ML20209F6111999-07-12012 July 1999 Revised Notification of 990805 Meeting with Util to Discuss Radiation Protection Issues Identified in NRC Insps Repts 50-458/98-10 & 50-458/99-04 ML20196L0051999-07-0808 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Recently Signed Asset Purchase Agreement Between Illinois Power & Amergen Energy Co & Proposed Transfer of License to Be Submitted to NRC ML20209D8271999-07-0707 July 1999 Notification of 990719 Licensee Meeting in Arlington,Tx to Discuss Failed Fuel Recovery Project ML20196G0321999-06-24024 June 1999 Notification of 990726 Meeting with Util to Discuss Radiation Protection Issues ML20196F0391999-06-23023 June 1999 Notification of 990707 & 08 Meeting with EOI in Conference 1 at GGNS Energy Svc Ctr to Discuss Low Power Shutdown Risk Assessment Methods & Associated Probabilistic Risk Assessment Model ML20212J3201999-06-23023 June 1999 Forwards Proposed Change to STSs for Review & Comment.Change Would Remove TS Requirements for ESF Features to Be Operable After Sufficient Radioactive Decay Has Occurred to Ensure Off Site Doses Remain Below SRP Limits ML20195F8811999-06-10010 June 1999 Notification of 990622 Meeting with Util in Rockville,Md to Discuss Related Issues Associated with Fuel Integrity Problems Experienced During Recent Cycle 8 Operation ML20207G3761999-06-0202 June 1999 Revised Notification of 990611 Meeting with EOI in Rockville,Maryland to Discuss Issues Associated with Fuel Integrity Problems Experienced During Recent Cycle 8 Operation.Meeting Cancelled ML20207E9231999-06-0202 June 1999 Notification of 990611 Meeting with EOI in Rockville, Maryland to Be Briefed by EOI & to Discuss Related Issues Associated with Fuel Integrity Problems Experienced During Recent Cycle 8 Operation ML20207A2551999-05-18018 May 1999 Notification of 990603 Meeting with EOI in Rockville,Md to Discuss EOI Submittal on BWROG Source Term Analysis & Possible Related Future Amend Requests from EOI ML20206F2481999-04-22022 April 1999 Informs That Operational Readiness Insp Team Completed Insp at Clinton Power Station Including Two Weeks on Site & Two Separate Instances of Continuous 72 Hours Control Room Observation.Operational Performance Adequate ML20206F2361999-04-21021 April 1999 Documents Completion of Insp Activities Performed During Week of 990412,to Assess Licensee Implemented & Planned Corrective Actions Associated with NRC Manual Chapter 0350 Case Specific Checklist Restart Item II.1 DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20205R8871999-04-20020 April 1999 Notification of 990504 Meeting with Util in Rockville,Md to Discuss Proposal to Submit Consolidated Security Plan for Util Sites ML20206F2331999-04-19019 April 1999 Discusses Results of Clinton Power Station Corrective Action Insp & Recommendations to Close Demand for Info Ltr.Insp Team Focused on Operations,Maintenance & Plant Support Organizations 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 ML20196K9471999-04-0606 April 1999 Notification of Significant Licensee Meeting with Util on 990420 to Discuss Results of Most Recent NRC Plant Performance Review IR 05000458/19993011999-03-29029 March 1999 Forwards NRC Operator Licensing Exam Rept 50-458/99-301 (Including Completed & Graded Tests) for Tests Administered on 990222-0303 ML20205C4481999-03-29029 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990222-0303 ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20204B3041999-03-15015 March 1999 Notification of Licensee Meeting with Util in Energy Svc Ctr,Grand Gulf Site on 990415 to Discuss Plant Performance Review Results.Meeting Open to Public ML20207K9161999-03-11011 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss River Bend Station Engineering Program & Performance with Project,Maintenance & Engineering Branch Personnel ML20199L0511999-01-21021 January 1999 Notification of 990222 Meeting with Util in Rockville,Md for Ucs to Present Addl Info & Clarify Issues Raised in Two 10CFR2.206 Petitions Re River Bend Station & Perry Nuclear Power Plant ML20198R8831999-01-0707 January 1999 Forwards SER Accepting Licensee 971015 Request to Amend Perry Nuclear Power Plant TSs 5.2.2.e to Remove Reference to GL 82-12 & Require Administrative Controls Be Established Which Will Ensure Adequate Shift Coverage ML20198S0601999-01-0606 January 1999 Notification of 990121 Meeting with Util to Discuss Potential Change to Clinton Degraded Voltage Relay Setpoints ML20196D9451998-11-30030 November 1998 Notification of 981204 Meeting with Centerior Svc Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20195G1121998-11-17017 November 1998 Notification of 981201-02 Meeting with Entergy Operations in Taft,Louisianna to Conduct Joint Workshop for Licensing Personnel from Entergy & Nrc,Project Directorate IV-1 ML20195F1691998-11-12012 November 1998 Notification of 981123 Meeting with Entergy Operations,Inc in Arlington,Tx to Discuss Apparent Inoperability of Divs I & II Emergency DGs ML20195B8551998-11-0909 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Revisions to Licensing Basis for Feedwater Containment Isolation Valves ML20154L1161998-10-14014 October 1998 Notification of 981027 Meeting with Util in Rockville,Md to Discuss Licensee Proposed Mod of keep-fill Sys for Feed Water Sys Check Valves to Eliminate Containment Leakage Concern ML20154J9271998-10-13013 October 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam Administered on 980901 ML20154J7921998-10-13013 October 1998 Forwards NRC Operator Licensing Retake Exam & Insp Rept 50-461/98-301(OL) Administered on 980901 ML20151X1651998-09-14014 September 1998 Notification of Significant Licensee Meeting W/Util on 980929 to Discuss Emergency Preparedness Activities & Issues ML20151U7971998-09-0808 September 1998 Notifies of 980929 Meeting with Util in Rockville,Md to Discuss Level of Instructions & Details for Transferring Quality Assurance Plan Details from Current Program Plans at Four Sites to Std Quality Assurance Program Plan ML20153H6671998-09-0808 September 1998 Revised Notification of 981007 Meeting with Util to Discuss Level of Instructions & Details for Transferring QA Plan Details from Current Program Plans at Four Sites to Std Program Plan at All Sites.Originally Scheduled for 980929 ML20151T6141998-09-0303 September 1998 Notification of Licensee Meeting W/Util on 980910 in Arlington,Tx to Discuss Plant Performance W/Regional Administrator & Division Directors ML20238F8661998-09-0101 September 1998 Forwards Licensee Revs to Svc List for Placing in PDR ML20238F3341998-08-31031 August 1998 Notification of 980915 Meeting W/Centerior Service Co in Rockville,Md to Discuss Licensing Submittal Based Upon Revised Accident Source Term That Deletes MSIV Leakage Control Sys & Relaxes MSIV Leakage Limits ML20238F5861998-08-28028 August 1998 Notification of 980909 Meeting w/BWR/6S:EOI & Listed Utils in Rockville,Md to Discuss W/Nrc Planned Applications by Licensees to Reduce Operability Requirements During Refueling Outages ML20238F1861998-08-28028 August 1998 Notification of 980910 Meeting W/Centerior Service Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl ML20237D6711998-08-25025 August 1998 Notification of 980917 Meeting W/Util in Rockville,Md to Hold NRC Insp Manual Chapter 0350 Restart Panel Meeting W/Illinois Power to Discuss Progress of Clinton Power Station Toward Restart ML20237A2811998-08-12012 August 1998 Notification of 980827 Meeting W/Nrc & Util in Rockville,Md to Discuss Level of Instructions & Details for Transferring QA Plan Details from Current Program Plans at Four Sites 1999-09-02
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217M6061999-10-20020 October 1999 Notification of 991102 Meeting with Util in Port Gibson,Ms to Discuss Bases for Emergency Preparedness Plan Change Submitted in & Supplemented by 990120 & 0715 Ltrs ML20212C0761999-09-15015 September 1999 Notification of 990930 Meeting with Firstenergy Nuclear Operating Co in Rockville,Md to Discuss Licensee Recent Submittal Requesting Five Percent Power Uprate IR 05000416/19990021999-09-10010 September 1999 Notification of Significant Licensee Meeting with Entergy Operations,Inc on 991018 to Discuss Listed Topics Identified in NRC Insp Repts 50-416/99-02,99-03 & 99-06 ML20211K7171999-09-0202 September 1999 Forwards Ineel Technical Ltr Rept, Evaluation of Fuel Pin Failure Timing in Boiling Water Reactors Dated 990730.Rept Used for Review of BWROG Rept on Revised Source Term Accident Analysis ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211E1491999-08-23023 August 1999 Notification of Licensee Meeting with Util on 990830 to Discuss Recent Refueling Maint Outage ML20209G2421999-07-14014 July 1999 Notification of 990722 Meeting with License in Rockville, MD to Discuss Changes in EOI Licensing Organization Including Division of Responsibilities within New EOI Corporate Licensing Group ML20209F6111999-07-12012 July 1999 Revised Notification of 990805 Meeting with Util to Discuss Radiation Protection Issues Identified in NRC Insps Repts 50-458/98-10 & 50-458/99-04 ML20196L0051999-07-0808 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Recently Signed Asset Purchase Agreement Between Illinois Power & Amergen Energy Co & Proposed Transfer of License to Be Submitted to NRC ML20209D8271999-07-0707 July 1999 Notification of 990719 Licensee Meeting in Arlington,Tx to Discuss Failed Fuel Recovery Project ML20196G0321999-06-24024 June 1999 Notification of 990726 Meeting with Util to Discuss Radiation Protection Issues ML20196F0391999-06-23023 June 1999 Notification of 990707 & 08 Meeting with EOI in Conference 1 at GGNS Energy Svc Ctr to Discuss Low Power Shutdown Risk Assessment Methods & Associated Probabilistic Risk Assessment Model ML20212J3201999-06-23023 June 1999 Forwards Proposed Change to STSs for Review & Comment.Change Would Remove TS Requirements for ESF Features to Be Operable After Sufficient Radioactive Decay Has Occurred to Ensure Off Site Doses Remain Below SRP Limits ML20195F8811999-06-10010 June 1999 Notification of 990622 Meeting with Util in Rockville,Md to Discuss Related Issues Associated with Fuel Integrity Problems Experienced During Recent Cycle 8 Operation ML20207G3761999-06-0202 June 1999 Revised Notification of 990611 Meeting with EOI in Rockville,Maryland to Discuss Issues Associated with Fuel Integrity Problems Experienced During Recent Cycle 8 Operation.Meeting Cancelled ML20207E9231999-06-0202 June 1999 Notification of 990611 Meeting with EOI in Rockville, Maryland to Be Briefed by EOI & to Discuss Related Issues Associated with Fuel Integrity Problems Experienced During Recent Cycle 8 Operation ML20207A2551999-05-18018 May 1999 Notification of 990603 Meeting with EOI in Rockville,Md to Discuss EOI Submittal on BWROG Source Term Analysis & Possible Related Future Amend Requests from EOI ML20206F2481999-04-22022 April 1999 Informs That Operational Readiness Insp Team Completed Insp at Clinton Power Station Including Two Weeks on Site & Two Separate Instances of Continuous 72 Hours Control Room Observation.Operational Performance Adequate ML20206F2361999-04-21021 April 1999 Documents Completion of Insp Activities Performed During Week of 990412,to Assess Licensee Implemented & Planned Corrective Actions Associated with NRC Manual Chapter 0350 Case Specific Checklist Restart Item II.1 DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20205R8871999-04-20020 April 1999 Notification of 990504 Meeting with Util in Rockville,Md to Discuss Proposal to Submit Consolidated Security Plan for Util Sites ML20206F2331999-04-19019 April 1999 Discusses Results of Clinton Power Station Corrective Action Insp & Recommendations to Close Demand for Info Ltr.Insp Team Focused on Operations,Maintenance & Plant Support Organizations 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 ML20196K9471999-04-0606 April 1999 Notification of Significant Licensee Meeting with Util on 990420 to Discuss Results of Most Recent NRC Plant Performance Review IR 05000458/19993011999-03-29029 March 1999 Forwards NRC Operator Licensing Exam Rept 50-458/99-301 (Including Completed & Graded Tests) for Tests Administered on 990222-0303 ML20205C4481999-03-29029 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990222-0303 ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20204B3041999-03-15015 March 1999 Notification of Licensee Meeting with Util in Energy Svc Ctr,Grand Gulf Site on 990415 to Discuss Plant Performance Review Results.Meeting Open to Public ML20207K9161999-03-11011 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss River Bend Station Engineering Program & Performance with Project,Maintenance & Engineering Branch Personnel ML20199L0511999-01-21021 January 1999 Notification of 990222 Meeting with Util in Rockville,Md for Ucs to Present Addl Info & Clarify Issues Raised in Two 10CFR2.206 Petitions Re River Bend Station & Perry Nuclear Power Plant ML20198R8831999-01-0707 January 1999 Forwards SER Accepting Licensee 971015 Request to Amend Perry Nuclear Power Plant TSs 5.2.2.e to Remove Reference to GL 82-12 & Require Administrative Controls Be Established Which Will Ensure Adequate Shift Coverage ML20198S0601999-01-0606 January 1999 Notification of 990121 Meeting with Util to Discuss Potential Change to Clinton Degraded Voltage Relay Setpoints ML20196D9451998-11-30030 November 1998 Notification of 981204 Meeting with Centerior Svc Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20195G1121998-11-17017 November 1998 Notification of 981201-02 Meeting with Entergy Operations in Taft,Louisianna to Conduct Joint Workshop for Licensing Personnel from Entergy & Nrc,Project Directorate IV-1 ML20195F1691998-11-12012 November 1998 Notification of 981123 Meeting with Entergy Operations,Inc in Arlington,Tx to Discuss Apparent Inoperability of Divs I & II Emergency DGs ML20195B8551998-11-0909 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Revisions to Licensing Basis for Feedwater Containment Isolation Valves ML20154L1161998-10-14014 October 1998 Notification of 981027 Meeting with Util in Rockville,Md to Discuss Licensee Proposed Mod of keep-fill Sys for Feed Water Sys Check Valves to Eliminate Containment Leakage Concern ML20154J9271998-10-13013 October 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam Administered on 980901 ML20154J7921998-10-13013 October 1998 Forwards NRC Operator Licensing Retake Exam & Insp Rept 50-461/98-301(OL) Administered on 980901 ML20151X1651998-09-14014 September 1998 Notification of Significant Licensee Meeting W/Util on 980929 to Discuss Emergency Preparedness Activities & Issues ML20151U7971998-09-0808 September 1998 Notifies of 980929 Meeting with Util in Rockville,Md to Discuss Level of Instructions & Details for Transferring Quality Assurance Plan Details from Current Program Plans at Four Sites to Std Quality Assurance Program Plan ML20153H6671998-09-0808 September 1998 Revised Notification of 981007 Meeting with Util to Discuss Level of Instructions & Details for Transferring QA Plan Details from Current Program Plans at Four Sites to Std Program Plan at All Sites.Originally Scheduled for 980929 ML20151T6141998-09-0303 September 1998 Notification of Licensee Meeting W/Util on 980910 in Arlington,Tx to Discuss Plant Performance W/Regional Administrator & Division Directors ML20238F8661998-09-0101 September 1998 Forwards Licensee Revs to Svc List for Placing in PDR ML20238F3341998-08-31031 August 1998 Notification of 980915 Meeting W/Centerior Service Co in Rockville,Md to Discuss Licensing Submittal Based Upon Revised Accident Source Term That Deletes MSIV Leakage Control Sys & Relaxes MSIV Leakage Limits ML20238F5861998-08-28028 August 1998 Notification of 980909 Meeting w/BWR/6S:EOI & Listed Utils in Rockville,Md to Discuss W/Nrc Planned Applications by Licensees to Reduce Operability Requirements During Refueling Outages ML20238F1861998-08-28028 August 1998 Notification of 980910 Meeting W/Centerior Service Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl ML20237D6711998-08-25025 August 1998 Notification of 980917 Meeting W/Util in Rockville,Md to Hold NRC Insp Manual Chapter 0350 Restart Panel Meeting W/Illinois Power to Discuss Progress of Clinton Power Station Toward Restart ML20237A2811998-08-12012 August 1998 Notification of 980827 Meeting W/Nrc & Util in Rockville,Md to Discuss Level of Instructions & Details for Transferring QA Plan Details from Current Program Plans at Four Sites 1999-09-02
[Table view] |
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f*gsh *1C*g ' UNITED STATES y
g( :
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C.,20555 c . g, j August 24, 1984 MEMORANDUM FOR: B. J. Youngblood, Chief Licensing Branch No. 1. DL
' A. Schwencer, Chief Licensing Branch No. 2, DL FROM: W. R. Butler, Chief j Containment Systems Branch, DSI
SUBJECT:
REQUEST FOR INFORMATION REGARDING HYDROGEN CONTROL FOR MARK III CONTAINMENTS As part of our continuing review of hydrogen control for Mark III containment plants during postulated degraded core accidents, we have identified the need for additional infonnation on several matters. The .
items pertain to the CLASIX-3 code, which has been used by HCOG to l support the determining, the licensing activities environmental as.sociated conditions againstwith Mark which III plants; e.g.,
equipment survivability is to be evaluated. _ _
The CSB requests that the ciselosed questions be transmitted to
.the Grand Gulf, Perry, River Bend and Clinton applicants.
N W. R. Butler, Chief Containment Systems Branch, DSI
Enclosure:
As stated cc: R. W. Houston
E. J. Weink~am B. Siegel ,
D. Houston CONTACT: A. Notafrancesco, CSB: DSI x29487 e
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~
1
. REQUEST FOR ADDITIONAL INFORMATION RELATED TO DEGRADED CORE HYDROGEN CONTROL 4
- 1. It is the intent of the Mark III owners to use the HC06 quarter-scale
. . tests',(whichfocusesondiffusion-typeburningwithinthewetwell i
region)andplantspecific/HCOGCLASIX-3 analyses (whichfocuseson discrete-type burning within the containment), to determine the most severe thermal environment within the containment and drywell for purposes of demonstrating equipment survivability. Since the present passive heat sink modeling in CLASIX-3 tends to underestimate the compartment atmosphere temperatures and since CLASIX-3 appears to be in non-conformance with the provisions of NUREG-0588, the CLASIXs3 containment response sensitivity studies (correspondence
(
No. HGW-001) shsaid not be used as the baefs for determining the-I
- most severe compartment temperature conditions. In view of this j concern, the present version of CLASIX-3 is inappropriate. ;
C
(,z .
f Since the methodology described in NUREG-0588 is generally recognized as an acceptable approach for addressing equipment qualification, describe and justify if there are deviations from the provisions of NUREG-0588 with regard to the passive heat-sink and heat-transf.er
,"e.[ -
assumptions that will be used for plant specific analyses in the .
4 following areas:
1
- 1) the temperature difference used with the heat-transfer film coefficients for both saturated and super-heated atmospheres;- 1 S
1 f.
I
. - - - . _ _ - , , _ - . . . ~ . - . - , - . _ . . _ _ - , . - - _ . _ _ _ _ _ . -- _ _ - _ , --_. -
e 2~
- 2) "the inalytical.model and assumptions used to account for condensate removal'from the heat sink surface; and
- 3) the energy removal associated with condensed mass.
- 2. For each postulated degraded core sequence, (i.e., SORV and drywell break initiated events), provide an evaluation of the impact on the drywell atmosphere environment when considering heat losses from the reactor vessel and its associated piping (e.g., SRV lines). Provide and justify assumptions used in your evaluation, e.g., convective and radiatiye heat transfer parameters. ,__ _
1 l
- 3. According to the BWR/6 Standard Technical Specifications, periodic low pressure leak testing of the drywell is required. The .
acceptance criterion is that the leakage shall be less than or equal to 10% of~ the maximum allowable A/fii (i.e., approximately 1 ft* ).
_Thus, the maximum allowable leak rate is equivalent to roughly 4000 SCFM at 3 psi pressure differential. Provide an evaluation of the l
consequences within the drywell and the containment by the combustion of hyd[ ogen when considering the drywell bypass le'akage (include mechanistically the effects of upper pool dump and pool drawdown). l x
e-' y Y
( .
_