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Category:Letter
MONTHYEARML24281A0662024-10-0404 October 2024 EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components IR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 ML24269A0552024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24255A8032024-09-11011 September 2024 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24274A1482024-09-30030 September 2024 NRR E-mail Capture - Davis-Besse - RAI Re Relief Request L-23-214 ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station ML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information ML23033A0322023-02-0101 February 2023 NRR E-mail Capture - Request for Additional Information for Davis-Besse's 2022 Steam Generator Inspection Report (L-2022-LRO-0115) ML22357A0302022-12-23023 December 2022 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000346/2023010 ML22266A1102022-09-23023 September 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure ML22214A7042022-08-0202 August 2022 Reissue - Davis-Besse Nuclear Power Station, Unit 1 Notification of Nrc Fire Protection Team Inspection Request for Information: Inspection Report 05000346/2022011 ML22187A0992022-07-0606 July 2022 Notification of NRC Supplemental Inspection (95001) and Request for Information ML22164A8572022-06-13013 June 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan ML22118A6862022-04-28028 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML22112A1092022-04-22022 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building ML22055A0872022-02-23023 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3 IR 05000346/20210912021-12-17017 December 2021 NRC Inspection Report (05000346/2021091) Preliminary Greater than Green Finding ML21321A3792021-11-16016 November 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML21301A0992021-10-28028 October 2021 Draft Request for Additional Information: Proposed Alternate for Examination of Steam Generator Welds - Energy Harbor Nuclear Corp., Davis-Besse Nuclear Power Station, Unit No. 1 ML21203A3252021-07-28028 July 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000346/2021011 ML21155A1952021-06-0404 June 2021 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Davis Besse Nuclear Power Station ML21041A5452021-02-10010 February 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20300A5592020-10-27027 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20154K7642020-06-0202 June 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425 ML20133J9792020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20021A3162020-01-21021 January 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19179A1382019-06-28028 June 2019 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program ML19164A1532019-06-13013 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan ML19162A3922019-06-11011 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML19143A0732019-05-29029 May 2019 FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments ML18305B0192018-11-0101 November 2018 18 Davis-Besse Nuclear Power Station - Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information(Rdb) ML18201A4122018-07-19019 July 2018 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML18190A4902018-07-0909 July 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team), Inspection Report 05000346/2018011 (DRP-DXB) ML18102B0852018-04-12012 April 2018 NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver ML18043A0102018-02-0909 February 2018 NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans ML17355A3722017-12-21021 December 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information ML17257A1402017-09-14014 September 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML17135A3612017-05-12012 May 2017 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000346/2017010 (Jvb) ML17129A4112017-05-0909 May 2017 Request for Additional Information Regarding Evaluation Submitted in Response to License Renewal Commitment No. 54 ML17100A1732017-04-19019 April 2017 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16364A2792017-01-23023 January 2017 Request for Additional Information Regarding License Renewal Commitment No. 42 ML16355A0352016-12-19019 December 2016 Ltr 12/19/16 Davis-Besse Nuclear Power Station, Unit 1 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000346/2017009 (Bxj) ML16256A0662016-10-18018 October 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 21, 2015 Mr. Brian D. Boles Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 North State, Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO AMENDMENT REQUEST FOR EMERGENCY DIESEL GENERATOR MINIMUM VOLTAGE SURVEILLANCE REQUIREMENTS (TAC NO. MF6060)(L-15-117)
Dear Mr. Boles:
By application dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15091A143), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a license amendment request for the Davis-Besse Nuclear Power Station, Unit No. 1. The proposed amendment requests changes to certain technical specification minimum voltage and frequency acceptance criteria for emergency diesel generator testing.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. This request was discussed with FENOC personnel during a teleconference on August 17, 2015. A response to the enclosed request for additional information is requested to be provided by October 9, 2015.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
B. Boles If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1380.
Sincerely, Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION AMENDMENT REQUEST TO CHANGE EMERGENCY DIESEL GENERATOR MINIMUM VOLTAGE REQUIREMENTS FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 By application dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15091A143), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a license amendment request (LAR) for the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The proposed amendment requests changes to certain technical specification minimum voltage and frequency acceptance criteria for emergency diesel generator (EOG) testing.
Section 3 of the LAR provides the technical evaluation for minimum EOG starting and steady state voltage and frequency. For EOG starting, the existing minimum voltage acceptance criterion will be increased from 4031 V to 4070 V. The minimum acceptable voltage of 4070 V was determined based on the bus voltage required by the EOG output circuit breaker to close.
In addition, the existing EOG minimum steady state voltage acceptance criteria would be increased from 3744 V to 4088 V. The LAR states that a more restrictive minimum steady state voltage provides assurance that during EOG loading, the voltage response recommendations of Safety Guide 9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies" (ADAMS Accession No. ML12305A251), can be satisfied.
The NRC staff notes that:
(a) Safety Guide 9, Section C4, pertains to the starting and load-accepting capabilities of the diesel generator and states, in part, that the diesel generator should be designed such that the frequency will not decrease, at any time during the loading sequence, to less than 95 percent of nominal and the voltage will not decrease to less than 75 percent of nominal.
(b) The EOG minimum steady state voltage and frequency acceptance criterion, as specified in surveillance requirement 3.8.1.2, 3.8.1.8.b, 3.8.1.11.c.3, 3.8.1.14.b, and 3.8.1.15.c.3, is based on the performance capability of the EOG governor and voltage regulator after perturbations due to load sequencing have dampened and the EOG is in a steady state operating mode.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the additional information below is needed to complete its review of the application.
Enclosure
(1) According to the Updated Final Safety Analysis Report (UFSAR) (ADAMS Accession No. ML14339A821 ), Table 8.3-1 for EOG loading, Step 1 loading includes loads that do not trip on a loss of power and a 400 horse-power (hp) component cooling water pump that starts as soon as the EOG output breaker closes with the proposed allowable voltage of 4070 V. A large motor (e.g., make up pump} starts within 2.5 seconds of breaker closure.
Explain how the evaluation performed demonstrates that the voltage drop (Attachment H of the LAR) during this stage of EOG loading satisfies Safety Guide 9 criterion and the minimum voltage required for running equipment.
(2) Provide the acceleration time for the large motors started in load sequencer Step 1 and 1a. Provide a list of the motor-operated valves that are required to operate during this period. Provide a summary of the assumptions, methods, and results of the evaluation performed for this additional loading.
(3) The NRC staff notes that an 800 hp motor-driven feedwater pump can be manually loaded onto the EOG.
Provide a summary of the assumptions, methods, and results of the evaluation performed to demonstrate that the voltage drop in the auxiliary system will not adversely impact safety-related equipment if the EOG was operating at the steady state voltage of 4088 V prior to pump start.
(4) For surveillance requirements associated with steady state operation of the EOG, the LAR proposes the following limits: Steady state voltage~ 4088 V and::;; 4400 V, and frequency ~ 59.5 Hz and ::;; 60.5 Hz.
- a. Explain how the maximum postulated loading evaluated in Attachment H considered the worst-case combination of allowable voltage and frequency coupled with large pumps operating at run out conditions.
- b. Explain how fuel oil consumption for EOG operation was evaluated after establishing the maximum EOG loading. Compare the revised EOG fuel oil consumption results with the design-bases and TS requirements for the EOG day tank and bulk storage (week) tank.
(5) In the LAR, the licensee stated that a transient analysis computer model was used to analyze the voltage and frequency response of the DBNPS EDGs during load sequencing associated with the design-basis loss of coolant accident and loss of offsite power. The licensee states this analysis showed that DBNPS EDGs are capable of starting their dedicated engineered safety features loads in the required sequence while meeting the minimum voltage and frequency recommendations of Safety Guide 9 for the loading sequence and each load sequence time interval.
Provide a summary of the EOG frequency and voltage response in a tabulated form with assumptions made for starting voltage and frequency.
B. Boles If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1380.
Sincerely, IRA!
Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
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