Forwards Revs to Byron,Dresden,Lasalle & Zion Station OCDM, Current as of 971231,ODCM Manual & Summary of Changes Included| ML20216H404 |
| Person / Time |
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| Site: |
Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
|---|
| Issue date: |
03/13/1998 |
|---|
| From: |
Sager D
COMMONWEALTH EDISON CO. |
|---|
| To: |
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
|---|
| Shared Package |
|---|
| ML20216H409 |
List: |
|---|
| References |
|---|
| NUDOCS 9803230006 |
| Download: ML20216H404 (25) |
|
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2871999-10-21021 October 1999
Refers to Rev 5 Submitted in May 1999 for Portions of Byron Nuclear Power Station Generating Stations Emergency Plan Site Annex.Informs That NRC Approval Not Required Based on Determination That Plan Effectiveness Not Decreased
ML20217P6171999-10-21021 October 1999
Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)
SVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999
Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217J4411999-10-18018 October 1999
Forwards Exemption from Certain Requirements of 10CFR73.55 for Zion Nuclear Power Station,Units 1 & 2 in Response to Application Dtd 990730,to Allow Util to Discontinue Specific Aspects of Security Plan & SER
ML20217H6251999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld
ML20217H6341999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld
ML20217F4301999-10-14014 October 1999
Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1
ML20217G9791999-10-14014 October 1999
Forwards SE Accepting Relief Requests to Rev 5 of First 10-year Interval Inservice Insp Program for Plant,Units 1 & 2
ML20217K7011999-10-13013 October 1999
Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl
05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999
Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action
ML20217D3191999-10-12012 October 1999
Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon
ML20217C1671999-10-0808 October 1999
Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2
ML20217F7891999-10-0808 October 1999
Forwards Insp Repts 50-454/99-12 & 50-455/99-12 on 990803- 0916.One Violation Occurred Being Treated as NCV
05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999
Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee
ML20217F6321999-10-0707 October 1999
Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations
ML20217A7601999-10-0606 October 1999
Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20212K9421999-10-0505 October 1999
Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2
ML20217B6351999-10-0505 October 1999
Forwards for Info,Final Accident Sequence Precursor Analysis of Operational Event at Byron Station,Unit 1,reported in LER 454/98-018 & NRC Responses to Util Specific Comments Provided in
ML20212L1791999-10-0505 October 1999
Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Rvid & Is Releasing Rvid Version 2
ML20212M0931999-10-0404 October 1999
Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff
05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999
Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl
ML20217B2991999-10-0101 October 1999
Forwards Insp Repts 50-454/99-16 & 50-455/99-16 on 990907-10.No Violations Noted.Water Chemisty Program Was Well Implemented,Resulted in Effective Control of Plant Water Chemistry
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
ML20212J6751999-09-30030 September 1999
Forwards Replacement Pages Eight Through Eleven of Insp Repts 50-454/99-15 & 50-455/99-15.Several Inaccuracies with Docket Numbers & Tracking Numbers Occurred in Repts
ML20217A6201999-09-30030 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl
ML20217A5821999-09-29029 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20217A9311999-09-29029 September 1999
Informs That NRC 6-month Review of Braidwood Identified That Performance in Maint Area Warranted Increased NRC Attention. Addl Insps Beyond Core Insp Program Will Be Conducted Over Next 6 Months to Better Understand Causes of Problem
ML20216G9541999-09-27027 September 1999
Forwards Environ Assessment & Finding of No Significant Impact Re 990730 Application for Exemption.Exemption Would Allow Zion Nuclear Power Station to Discontinue Specific Aspects of Security Plan
ML20216H4301999-09-23023 September 1999
Informs That Arrangements Made for Administration of Licensing re-take Exams at Braidwood Generating Station for Week of 991108
SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999
Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage
ML20212E7171999-09-22022 September 1999
Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads
ML20212J0451999-09-21021 September 1999
Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr
ML20212D8231999-09-20020 September 1999
Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21
05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl
ML20212C0591999-09-17017 September 1999
Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97
ML20216F8051999-09-17017 September 1999
Forwards Insp Rept 50-454/99-14 & 50-455/99-14 on 990823-27. Security Program Was Effectively Implemented in Areas Inspected.No Violations Were Identified
ML20216F7441999-09-17017 September 1999
Forwards Insp Repts 50-456/99-13 & 50-457/99-13 on 990706-0824.Three Violations Noted & Being Treated as Ncvs. Insp Focused on C/As & Activities Addressing Technical Concerns Identified During Design Insp Completed on 980424
A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999
Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station
ML20212C6961999-09-15015 September 1999
Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted
SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999
Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys
ML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
ML20212A1141999-09-10010 September 1999
Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage
ML20211Q9911999-09-10010 September 1999
Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring
ML20212A6991999-09-10010 September 1999
Forwards SE Accepting Licensee Second 10-year Interval ISI Program Request for Relief 12R-07 for Plant,Units 1 & 2
ML20211Q7961999-09-0909 September 1999
Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr,
ML20217H5661999-09-0909 September 1999
Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl
ML20211Q6511999-09-0808 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P6171999-10-21021 October 1999
Forwards non-proprietary & Proprietary Versions of HI-982083, Licensing Rept for Byron & Braidwood Nuclear Stations. Proprietary Rept Withheld,Per 10CFR2.790(b)(4)
SVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999
Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630
ML20217M4361999-10-19019 October 1999
Forwards Rev 46 to Braidwood Station Security Plan, IAW 10CFR50.4(b)(4).Description of Changes,Listed.Encl Withheld Per 10CFR73.21
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217H6251999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld
ML20217H6341999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld
ML20217F4301999-10-14014 October 1999
Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1
ML20217K7011999-10-13013 October 1999
Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl
05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999
Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action
ML20217C1671999-10-0808 October 1999
Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2
05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999
Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee
05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999
Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999
Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage
05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl
A99025, Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station1999-09-15015 September 1999
Forwards Response to NRC 990820 RAI Re Proposed Defueled TS for Zion Station
SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999
Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys
ML20211Q9911999-09-10010 September 1999
Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring
ML20211Q9011999-09-0808 September 1999
Advises That Us Postal Service Mailing Address Has Changed for Braidwood Station.New Address Listed
05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl
ML20211M1151999-08-31031 August 1999
Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006
ML20211J0311999-08-30030 August 1999
Agrees with Content in NRC 990810 Memo Re Plant Spent Fuel Pool.Memo Contains Accurate Summation of Info That Util Communicated to NRC During 990713 Telcon
ML20211G1831999-08-27027 August 1999
Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS
ML20211G1221999-08-27027 August 1999
Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d)
ML20211G8191999-08-26026 August 1999
Forwards Amend 6 to Fire Protection Rept for Zion Nuclear Power Station,Units 1 & 2, IAW 10CFR50.71(e).Attachment 1 Contains Summary of Changes
SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999
Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated
SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999
Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl
SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999
Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety
BW990053, Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 21999-08-13013 August 1999
Forwards post-outage Summary Rept for ISI Examinations Conducted During Seventh Refueling Outage of Braidwood Station,Unit 2
BW990052, Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station1999-08-12012 August 1999
Informs That RW Clay,License OP-31044,no Longer Requires Operator License at Braidwood Station
05000454/LER-1998-008, Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER1999-08-12012 August 1999
Informs That Licensee Determined That Suppl Rept to LER 98-008 Is Not Warranted.No Addl Info Was Generated Following Completion of Root Cause Investigation of Following Completion of Corrective Actions Stated in Original LER
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
BW990049, Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle1999-08-0404 August 1999
Informs NRC of Plans to Demonstrate Compliance with 10CFR50.46 Requirements for Fuel Predicted to Experience Fuel Pellet to Rod Cladding Gap Reopening,During Current Cycle
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
ML20210K0771999-07-30030 July 1999
Submits 30-day Rept Re Discovery of ECCS Evaluation Model Error for Byron & Braidwood Stations,As Required by 10CFR50.46
ML20210J0861999-07-30030 July 1999
Requests NRC Approval of Exemption from Certain Requirements of 10CFR73, Physical Protection of Plants & Matls, by 990921.Exemption Is Needed to Support Scheduled 991001 Implementation of Plant Sf Ni.Encl Withheld,Per 10CFR73.21
05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999
Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed
ML20210J8951999-07-29029 July 1999
Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal..
BW990045, Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr1999-07-28028 July 1999
Forwards Errata to 1998 Radioactive Effluent Release Rept. Info Has Been Corrected & Revised Spreadsheets Included in Attachment to Ltr
SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999
Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2
SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999
Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept
05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed
ML20210E2151999-07-23023 July 1999
Forwards Byron Unit 1 B1R09 ISI Summary Rept Spring 1999 Outage,980309-990424, in Compliance with Requirements of Article IWA-6000, Records & Repts of Section XI of ASME & P&PV,1989 Edition
SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999
Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625
ML20216D3781999-07-21021 July 1999
Forwards Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR on ITS Format & W(Z) Function, to Account for Error That W Discovered in Computer Code Used to Calculate PCT During LBLOCA
ML20210D2961999-07-20020 July 1999
Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761
ML20216D7061999-07-19019 July 1999
Forwards Rev 45 to Braidwood Station Security Plan,Iaw 10CFR50.4(b)(4).Plan Includes Listed Changes.Rev Withheld, Per 10CFR73.21
ML20210C2561999-07-19019 July 1999
Forwards Rev 1 to Calculation 22S-B-110X-0068, Determination of Heat Load for Assemblies F50D & Z33A, as Replacement Pages to Rev 0.Calculation Submitted Re Request for Approval of Proposed Plant Defueled Station EP
ML20209H2991999-07-16016 July 1999
Withdraws 980529 LAR to Credit Automatic PORV Operation for Mitigation of Inadvertent Safety Injection at Power Accident.Response to NRC 990513 RAI Re LAR Encl
BW990042, Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.71999-07-16016 July 1999
Forwards Braidwood Station,Unit 1 Post Accident Monitoring Rept for Reactor Vessel Level Indication Sys (Rvlis),Due to Facility Train B RVLIS Being Restored to Operable Status After 7-day Completion Time,Per TS 3.3.3 & 5.6.7
1999-09-08
[Table view] |
Text
'. : .
~
g Osmmonwealth liliwn Company l 400 Opus I' lace ikiwners Gnn e, ll. (d)515 5701 March 13,1998 Document Control Desk Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington, D.C. 20555
Subject:
Summary of Offsite Dose Calculation Manual Revisions, January - December 1997 Attachment I contains a summary of the changes made to the Commonwealth Edison Company (Comed) Offsite Dose Calculation Manual (ODCM) during the period of January through December 1997.
Manual changes were submitted to your ofS s part of the normal controlled document distributions. However, in accordance with Tecunical Specifications, an entire copy of the ODCM, current as of December 31,1997, is also provided as Attachment II.
Please contact Eileen Murphy at (630) 663-3817 if you have any questions regarding the ODCM.
Sincerely, d [_ '
David -ger Vice President Generation Support ,
cc: NRC Region Ill w/out Attachment 11 G. F. Dick, Braidwood/ Byron Project Manager - NRR, w/out Attachment 11 J. F. Stang, Dresden Project Manager - NRR, w/out Attachment II l D. Skay, LaSalle Project Manager - NRR, w/out Attachment 11 R. M. Pulsifer, Quad Cities Project Manager - NRR, w/out Attachment II C. Y. Shiraki, Zion Project Manager - NRR, w/out Attachment il rg' s
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980323OOO6 9Idd3i3 PDR ADOCK 05000010 W PDR [llllllll(lllllllf' A I!nicom company
4 bec: A. Haeger / T. Johnson, w/out Attachment II J. Bauer / D. Thompton, w/out Attachment 11 L. Aldrich / P. Moore, w/out Attachment 11 N. Hightower / T. Greene, w/out Attachment 11 P. Behrens / R. Wiebenga, w/out Attachment 11 R. Svaleson, w/out Attachment II E. Katzman / E. Zirnhelt, w/out Attachment II W. Cari / E. Murphy, w/out Attachment 11 l
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ATTACitMENT I Changes to Site Annexes of the ODCM 1
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Attachment I Summarv of ODCM Revisions by Station:
Sation Chaoter. Revision Number Revision Date Byron Chapter 10, Revisioni.3 February 1997 Chapter 11, Revision 1.4 February 1997 Chapter 1 I, Revision 1.5 October 1997 Chapter 12, Revision 1.4 February 1997 Chapter 12, Revision 1.5 October 1997 Dresden Chapter 10, Revision 1.9 January 1997 Chapter 11, Revision 1.2 January 1997 Chapter i1, Revision 1.3 December 1997 Chapter 12, Revision 1.3 January 1997 Chapter 12, Revision 1.4 May 1997 Chapter 12, Revision 1.5 August 1997 Chapter 12, Revision 1.6 December 1997 LaSalle Chapter i1, Revision 1.9 March 1997 Zion Chapter 10, Revision 1.9 January 1997 Chapter 12, Revision 1.8 January 1997 Chapter 12, Revision 1.9 October 1997 Appendix F, Revision 1.1 October 1997 4
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ATTACilM ENT 11 Comed ODCM Current as of December 31, ~1997
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Byron Station Chapter 10 Change Summary ODCM Revision 1.3, February 1997 Page 10-1 Removed page revision index. No longer are individual pages revised. The revision number for the index is assigned to the chapter.
Page 10-11 Updated page numbers.
Page 10-iii Updated page numbers. Corrected system designator for Essential Service Water.
Page 10-v Updated page numbers.
Page 10-1 Removed specific UFSAR Chapter numbers due to a UFSAR revision in progress that affects Chapter
- 11. Deleted information concerning low, mid, and high noble gas channels from section 10.1.2.1 since that information applied to the WRGM monitors, not the 1(2)RE-PR028 monitors. Added that the 28's provide noble gas monitoring.
Changed reference _to UFSAR from "Section" to
" Chapter" to be consistent with the wording used in the UFSAR.
Page 10-2 Removed specific UFSAR Chapter numbers due to a UFSAR revision in progress that affects Chapter
- 11. Updated the high alarm tunction for monitors 1 (2 ) RE-PR027.
Page 10-3 Removed specific UFSAR Chapter numbers due to a UFSAR revision in progress that affects Chapter
- 11. Updated the high alarm function for monitor ORE-PR026. Removed statement concerning a procedural limit on the release rate trom section 10.1.3.1.2; this is covered in Section 10.1.3.2.
Changed the 1/4% in section 10.1.3.1.1 to 0.25%
to make reading the value easier.
Page 10-4 Removed statement concerning a procedural limit on the release rate trom section 10.1.3.1.3; this is covered in Section 10.1.3.2.
Page 10-5 Removed from 10.1.3.2 the specific release rate limit indicated in station procedures. This limit is not specifically used in all procedures; however, the limit used stijl ensures the station maximum release rate is not exceeded when releasing from multiple sources. Removed default fan flows listed in section 10.1.3.5. Fan flows J
are estimated trcm operating fan combinations; standard defaults are not normally used.
Page 10-6 Removed specific UFSAR Chapter numbers due to a UFSAR revision in progress that affects Chapter
- 11. Changed reference to UFSAR trom "Section" to
" Chapter" to be consistent with the wording used in the UFSAR. Corrected system designator for Essential Service Water.
Page 10-7 Removed specific UFSAR Chapter numbers due to a UFSAR revision in progress that affects Chapter
- 11. Changed reference to UFSAR from "Section" to
" Chapter" to be consistent with the wording used in the UFSAR. Clarified wording in section 10.2.3.1 to give a generic overview of the purpose of setpoint calculations.
Pages 10-7,8,9 Regrouped information as it applies to specific liquid monitors. Added clarifying information.
Page 10-9 Revised wording for determining liquid dilution flow rates to agree with Admin Tech Requirements.
Page 10-10 Clarified information under "other monitors" to include release monitors during non-release times and updated section to include the current process to determine isotopic mixtures for setpoint calculations. Removed specific reference to Cs-137 for the use in determining conversion factors. The source used is dependent on the monitor. Deleted reference to Figure 10-4.
Page 10-11 Corrected the percent for Kr-87. Originally typed as 00.4 instead of 0.04.
Page 10-14 Inserted dotted lines indicating an occasional flowpath from the gland steam condensers due to a modification being conducted to the system.
Page 10-15 Inserted dotted lines indicating an occasional flowpath through the evaporators. Corrected spelling error of " evaporators".
Page 10-17 Deleted Figure 10-4, Simplified Solid Radwaste Processing Diagram.
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l-Byron Station Chapter 11 Change Summary ODCM Revision 1.4, February 1997 l
Page 11-1 Removed page revision index. No longer are individual pages revised. The revision number for the index is assigned to the chapter.
l Page 11-2 Revised radiciodine canister collection and analysis frequency to biweekly.
I Page 11-6 Added well water location BY-32, due to an ANI
( auditor request to have a well water location between the site and the Rock River.
l Page 11-7 Corrected spelling error of " quadrant".
Page 11-9 Corrected title of Health Physics Support Director to Radiation Protection Director.
Page 11-13 Added well water location BY-32 to the map.
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Byron Station Chapter 11 Change Summary l
ODCM Revision 1.5, October 1997 l l
Page Change Descriotion 11-i Updated revision number 11-2 through 11-7 Updated the distances for the sampling and monitoring locations listed in Table 11-1 based on the results of a verification survey performed in August,1997. The survey was performed using a Global Positioning System (GPS) identifying the latitude, longitude and distance from the Station Vent Stack for each location.
11-3 Corrected the sector designator and direction for airborne control sample BY-8. The saraple location is very close to the edge of sectors P and Q, however, the August,1997 GPS survey identified the proper sector as P.
Il-5 Corrected the sector directions for TLD monitoring locations BY-211-1, 211-4, and 212-1. The sector designators listed in Table 11-1 were correct, however, the directions given for those sectors were wrong.
I Byron Station Chapter 12 Change Summary ODCM Revision 1.4, February 1997 Page 12-11 Removed page revision index. No longer are individual pages revised. The revision number for the index is assigned to the chapter.
Page 12-5 Corrected a typographical error in the title for the REMP program.
Page 12-15 Corrected the column header alignment.
Page 12-16 Corrected the column header alignment.
Page 12-20 Corrected spelling error of " Emitters".
Page 12-29 Corrected spelling error of " Emitters".
Page 12-30 Corrected spelling error of " elapsed".
Page 12-40 Added a paragraph to explain the requirements behind program deviations. This information was located in Chapter 9 (UREMP) and has been relocated into this chapter. Chapter 9 is to be deleted.
Page 12-41 Revised wording of 12.5.1.A.3. The wording was taken from Chapter 9 and relocated into this chapter.
Page 12-43 Revised radioiodine collection and analysis frequency to biweekly.
Page 12-44 Added and revised ranges for inner ring and outer ring TLDs. Original ranges did not encompass all existing locations. Corrected spelling error
" access".
Page 12-45 Changed the number of required samplcs to agree with the addition of a well water sampling location in Chapter 11.
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Page 12-46 Revised control _ range for milk sampling. Original )
ranges did not incorporate cows between 6.2 and i I
9.8 miles.
Page 12-48 Changed title in footnote 2. Revised footnote 8 to indicate that milk sampling may be discor.tinued I
but not required to be discontinued.
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Page 12-60 Added footnote 6 to I-131 Page 12-52 Added footnote 6 to indicate I-131 LLD applies to specific I-131 analyses. This was at the request of the contractor laboratory to remove any confusion when I-131 may be identified on a gamma spec when it is not specifically being analyzed for.
Page 12-S6 Corrected spelling error of " calendar".
Page 12-S8' Corrected a typographical error. There was a footnote notation in the last paragraph but no footnote existed or was required.
Byron Station ODCM Change Summary Chapter 12, Revision 1.5, October 1997 Paue Channe Description 12-ii Updated revision number.
12-iii Updated page numbers in Table of Contents.
12-iv Updated page numbers in List of Tables.
12-18,25,27 Corrected typographical crrors in section numbers.
12-34 Corrected typographical error in titic.
12-36,38 Corrected typographical errors in rection numbers.
12-38,39,40 Added surveillance requirements and bases statements for use and monitoring of the Old Steam Generator Storage Facility (OSGSF).
12-49 Corrected Table number in Notation (1) from 1.1-1 to I l-l.
12-51 Changed the LLD for tritium from 200 pCi/l to 2,000 pCi/l to maintain consistency with the NRC re-.c.dations in Generic Letter 89-01.
12-53 Added a footnote to the table to identify that the revised LLD for tritium is the minimum acceptable LLD authorized. Vendors performing environmental sample analyses off-site would still be required to use 200 pCi/l as the LLD.
12-56 Deleted the reference to use of preoperational studies in the Annual Environmental Operating Report. This data is not required to be included and has not been in previous reports.
12-59 Corrected a typographical error that referred to a section number in the old 10 CFR Part 20.
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..g Dresden Station Chapter 10 Change Summary ODCM Revision 1,9, January 1997 Pane Chance Description 10-1 Updated revision number 10-3 Added descriptive information in parentheses to Section 10.1.2.4, 10-4 Changed statement regarding the location of the definitions of parameters in equations 10-1 and 10-2. The definitions are found throughout Section A.I of Appendix A and not in only one location as previously stated.
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9 Dresden Station Chapter 11 Change Summary 00CM Revision 1.2, January 1997 P39ti item Il-i Removed page index. Individual pages no longer updated.
11-2 Removed 0-05 and footnote. D-05 deleted in 1995 as indicated by the footnote. Removed asterisk by D-45 indicating it replaced D-05 in 1995.
11-3 Updated location of TLD's 110-3 and 110-4 to reflect current placement.
11-6 Added D-50 as a unit 2/3 Cooling Water Sample location, 11-7 Changed Director title due to new department responsibilities.
11-12 Deleted D-05 from map. Lncation no longer exists.
11-13 Added D-50 location due to new cooling water sample. Updated locations for TLD's 110-3 and 110-4 based on current location, 11-14 Removed an incorrect milk location from the map; two different locations were given on the map for D-26.
I l Dresden Station Chapter 11 Change Summary ODCM Revision 1.3, December 1997 Page Change Descrintion Il i Updated the revision number and date.
11-ii Updated the List of Tables and List of Figures for the new revision.
'11-1 Updated the description of the Figures.
l l 11-2 through Changed the sample / monitoring locations, sampling frequency, and analyses
- Il-8 type / frequency to reflect the Comed Uniform Radiological l
Environmental Monitoring Program (UREMP).
11-9,10 Updated the Figures to illustrate the sampling / monitoring locations for UREMP.
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Dresden Station Chapter 12 Change Summary ODCM Revision 1.3, January 1997
[ age Item 12-11 Revi sed revision index to 1.3 l 12-111 Modified section titles to be consistent with text.
Added the tour existing sections under 12.3.C.
12-iv Added the 4 existing sections under 12.4.C and the three existing sections under 12.S.C.
12-5 Modified headings to be consistent with table of contents.
12-6 Capitalized " Unit" in 12.2. B.1. 4. Modified headings to be consistent with the table at contents.
12-7 Added footnote indicating discharge is not allowed it actions cannot be performed.
12-9 Added footnote indicating discharge is not allowed if actions cannot be performed.
12-13 Changed requirements for the Reactor Building Vent Exhaust Duct Radiation Monitor minimum channels to say "See Technical Specifications Section 3/4.2". This will ensure !
the user is cognizant that this item appears in the Technical Specifications.
12-14 Deleted 7 day clock and reporting requirement for Action 20. Upgraded Tech Specs do not address Low Range 2(3) Chimney noble gas monitoring and change is consistent with current Tech Specs and Quad Cities and LaSalle ODCM requi rements f or comparable monitors. Deleted Action 24 since it is associated with the Reactor Building Vent Exhaust Duct Radiation Monitor (see change for page 12-13),
i 12-16 Ottgas monitor Functional Test frequency changed from daily to quarterly and Instrument check changed from quarterly to daily to comply with current Tech Specs.
Changed requirements for the Reactor Building Vent Exhaust i Duct Radiation Monitor minimum channels to say "See l Technical Specifications Section 3/4.2". This will ensure the user is cognizant that this item appears in the Techni cal Specifications.
12-40 Added a "d" on the end of " describe" in last sentence of 12.5.A.2 to correct grammar.
12-41 Added word " Program" to title of 12.5.B for consistency among other section titles. )
12-50 Inserted the symbol "E" in place of an "s" to represent the requirement for summing tactors.
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Dresden Station Chapter 12 Change Summary ODCM Revision 1.4, May 1997 Pane Channe Description 12-i Updated special note to identify T/S amendments authorizing transfer of Units 2 and 3 RETS to the ODCM. Added Statement that Unit 1 Technical Specifications shall take precedence over Unit i ODCM items until the Upgraded Unit 1 Technical Specifications are approved by the NRC. Updated file name.
12-ii Updated revision number.
12-iii, iv Updated page numbers in Table of Contents.
12-v Updated page numbers in List of Tables.
12-4 Revised Note (e) on Table 12.1-2. Technical Specification Amendments 154/149 revised the wording of this note in Table 1.2 of the Unit 2/3 Technical Specifications. Note was changed to conform with Units 2/3 Technical Specifications.
12-8 Added description ofgrab sample location to Action 10 statement 12-14,15 Added description of backup sample locations and clarifying information to Action Statements for Table 12.2-3.
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4 Dresden Station
. Chapter 12 Change Summary ODCM Revision 1.5, August 1997 Eagg. Channe Descriotion 12-i Updated Special Note to reflect transfer of RETS to the ODCM in Amc.ndment 39 Unit 1. Added statement that Technical Specifications shall always take prye'-= over the ODCM.
12-ii Updated revision number.
12-7 Deleted senice water effluent monitor from Table 12.2-1. Deleted Action 10 statement Senice water system has been drained and is no longer in senice per the Ut P+x ;; d:sioning Plan. Corrected the table header to align correct header above each column.
12-9 Deleted senice water etTluent inonitor from Table 12.2-2. Senice water system has been dramed and is no longer in senice per the UI Decommissiomng Plan.
12-15 Corrected TS reference to reflect new section number in the Upgraded Technical Specife 12-25 Deleted sampling requirements for U1 senice wer releases. System has been dramed and is no longer in senice per the U1 Decommissiomng Plan.~
12-25,26 Deleted Table Notation 7 addressing sampling requirements. Deleted the frequency notations and referred to the specific TS section addressing the sampling and analysis frequencies.
12-27 Deleted Table Notations 7 and 8. Table now refers to the appropriate Technical Specificat:on section which lists sampling requirements.
Dresden Station Chapter 12 Change Summary ODCM Revision 1.6, December 1997 Page Chance Descrintion 12-i Updated revision number in file designator.
12-il Updated revision number, 12-iii Updated page numbers in Table of Contents.
12-iv - Updated page numbers and Section titles in Table of Contents.
12-v Updated page numbers in List of Tables.
12-27,28 Added definition of LLD, including equation. Included alternate LLD methodology. Made table title consistent with first page of table.
12-40,41 Added definition of LLD, including equation. Included alternate LLD methodology.
12-35,37 Corrected typographical errors in the Technical Specifications references.
12-45 through Revised Section 12.5, Radiological Environmental Monitoring Program, to 12-60 reflect implementation of the Comed Uniform REMP. New sampling / monitoring locations and frequencies and the new analyses types and frequencies correspond with the standardized program.
12-45 Changed the reference to ODCM section numbers to address the new section numbers.
12-55 The LLD for tritium was changed to reflect the LLD value specified in NUREG-1301, 12-62 Changed the reference to ODCM section numbers to address the new sectica numbers.
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4 LaSalle Station Chapter 11 Change Summary ODCM Revision 1.9, March 1997 Page Chance Descrintion I l-i Updated revision number 11-7 Deleted L-41 cow. Farmer requested withdrawal from program.
Il-11 Removed L-4I sample location from map
Zion Station Chapter 10 Change Summary ODCM Revision 1.9, January 1997 Pane Change Description 10-i Updated revision number.
10-5 Revised ilVAC flow rate for radiation monitors 1(2)RE-0015 from 7.32 E+05 cc/see to 5.60 E+04 cc/sec. The ilVAC flow rate has changed due to exempt changes 1(2)-96-252 which relocated the sample tap location to the steam jet air ejector (SJAE) discharge header.
10-7 Corrected typographical error.
4 Zion Station Chapter 12 Change Summary ODCM Revision 1.8, January 1997 I
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12-il Updated revision number, 12-1,2,13, Corrected typographical errors. I 24,29,33, 36,40,46, f l
48,51 '
12-13 ACTION 15 - Remove requirement to daily verify alignment of Auxiliary Building ventilation. This is consistent with other radiation monitors which require realignment of ventilation due to monitor inoperability. The daily verification of the alignment (controlled by an out-of-service) is a task of no value.
12-22 Corrected Table 12.3-2 to reference applicable footnotes. Current sections of the table reference incorrect footnotes.
12-25 Revised wording to be consistent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. Subsequently reduced the limits to one half of current values.
12-26 Revised last paragraph to indicate this section applies to effluents released from each unit at the site, 12-27 Revised wording to be consistent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unli, versus each site. Subsequently reduced the limits to one half of current values.
12-31 Revised * , erding to be consistent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. Th6 requirement had incorrecly been written to apply to the site.
12-33 Revised wording to be consistent with NUREG-1301 and current ODCM methodology; indicated limits apply to effluents released from each unit, versus each site. The requirement had incorrectly been wntten to apply to the site.
Zion Station Chapter 12 Change Summary ODCM Revision 1.9, October 1997 Pye Chance Description 12-ii Updated revision number and file designator.
12-8 Deleted footnote (3) from channel check for composite sampler.
12-11 Changed mode applicability from ALL to "l,2,3, and 4" for iodine and paniculate monitors OR-PR12B and OR-PR12A.
12-27 Revised wording for determining dose due to liquid releases from the site.
12-29 Added footnote (g) designator to sampling frequency for Vent Stack.
12-30 Added footnote (g) to provide appropriate action when noble gas monitor is not in service.
12-35 Revised wording for determining dose due to gaseous releases from each unit.
12-45 Revised tritium water LLD to 2,000 pCi/l and added footnote (7) designator.
12-47 Added footnote (7) clarifying appropriate use of tritium LLDs for environmental samples.
12-50 Revised wording defming due date for Annual Radiological Environmental Operating Report.
12-51 Deleted wording referring to submittal of Annual Radioactive Efiluent Release Report "no longer than 12 months since the previous report" Added a list of exceptions to the Regulatory Guide 1.21 reponing requirements.
Zion Station Appendix F Change Summary ODCM Revision 1.1, October 1997 Pane Chance Description F-1 Corrected a typographical error in Reference 1.
F-3 Added bars to blank spaces in Elevated Release Point Characteristics.
F-4 Revised critical ranges for unrestricted area boundaries for sectors NE through SSE, for restricted area boundaries for all sectors, and for nearest resident for sectoca N and SSW through NNW, based on the 1993 census data.
F-6, 7, and Revised all parameters to reflect new critical ranges in Table F-3.
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ATTACIIMENT II l
Comed ODCM i
Current as of December 31,1997 j
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BRAIDWOOD RIvision 1.8 October 1995 CHAPTER 10 Braldwood Annex Index EAGE REVISION 10-1 1.8 1 0 -11 1.8 10-lii 1.8 10-IV 1.8 10-v 1.8 10 1 1.8 10-2 1.8 10-3 1.8 10-4 1.8 10-5 1.8 10-6 1.8 10 7 1.8 10-8 1.8 10-9 1.8 10-10 1.8 .
10-11 1.8 10-12 1.8 ,
10-13 1.8 10-14 1.8 10-15 1.8 10 16 1.8
EPSPROJeden4mid/10r14 10-1
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