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| | number = ML20106E376 | | | number = ML20106E376 |
| | issue date = 10/20/1984 | | | issue date = 10/20/1984 |
| | title = Forwards Comments on Draft License NPF-23 Transmitted by Tm Novak 841018 Ltr.License Should Be Issued for Full Power. Environ Protection Plan Acceptable | | | title = Forwards Comments on Draft License NPF-23 Transmitted by Tm Novak .License Should Be Issued for Full Power. Environ Protection Plan Acceptable |
| | author name = Tramm T | | | author name = Tramm T |
| | author affiliation = COMMONWEALTH EDISON CO. | | | author affiliation = COMMONWEALTH EDISON CO. |
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| | contact person = | | | contact person = |
| | document report number = 9363N, NUDOCS 8410290194 | | | document report number = 9363N, NUDOCS 8410290194 |
| | | title reference date = 10-18-1984 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC |
| | page count = 5 | | | page count = 5 |
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| f'~ N Commonwealth Edison | | f'~ N Commonwealth Edison |
| [ ,) One First N!tional Pitt2, Chicago Ilknors f 'g \ C ' Addrzss R ply to. Post Office Box 767 | | [ ,) One First N!tional Pitt2, Chicago Ilknors f 'g \ C ' Addrzss R ply to. Post Office Box 767 |
| 'N Chicago, Illinois 60690 October 20, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject: Byron Generating Station Units 1 and 2 Draft License NPF-23 NRC Docket No. 50-454 Reference (a): October 18, 1984 letter T. M. Novak to D. L. Farrar | | 'N Chicago, Illinois 60690 October 20, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject: Byron Generating Station Units 1 and 2 Draft License NPF-23 NRC Docket No. 50-454 Reference (a): {{letter dated|date=October 18, 1984|text=October 18, 1984 letter}} T. M. Novak to D. L. Farrar |
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| ==Dear Mr. Denton:== | | ==Dear Mr. Denton:== |
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| License Condition'3: Post-Fuel-Loading Initial Test Program _ | | License Condition'3: Post-Fuel-Loading Initial Test Program _ |
| The requirement to obtain NRC approval if the test program is delayed should be modified to permit continued operation of the plant at a given power level if the results of the startup tests to that plateau are properly reviewed by Commonwealth Edison and found acceptable within the specified time periods. Continued power operation during an unexpected delay will not endanger the public health and safety as long as the test results are satisfactory. For example, a breakdown of secondary side pumps or heat exchangers which imposes a temporary power limitation would raise no new safety issue. | | The requirement to obtain NRC approval if the test program is delayed should be modified to permit continued operation of the plant at a given power level if the results of the startup tests to that plateau are properly reviewed by Commonwealth Edison and found acceptable within the specified time periods. Continued power operation during an unexpected delay will not endanger the public health and safety as long as the test results are satisfactory. For example, a breakdown of secondary side pumps or heat exchangers which imposes a temporary power limitation would raise no new safety issue. |
| License Condition 5: Equipment Qualification The requirement to reevaluate the environmental conditions resulting from a HELB outside containment should be deleted. A preliminary evaluation was provided by letter dated October 18, 1984 from T. R. Tramm to H. R. Denton which contained our commitment to further review of this issue. The results of preliminary evaluations were also provided which indicated that there is reasonable. assurance that the reactor can be operated safely while more detailed analyses are completed and reviewed. | | License Condition 5: Equipment Qualification The requirement to reevaluate the environmental conditions resulting from a HELB outside containment should be deleted. A preliminary evaluation was provided by {{letter dated|date=October 18, 1984|text=letter dated October 18, 1984}} from T. R. Tramm to H. R. Denton which contained our commitment to further review of this issue. The results of preliminary evaluations were also provided which indicated that there is reasonable. assurance that the reactor can be operated safely while more detailed analyses are completed and reviewed. |
| License Condition 6: Fire Protection Program Conditions 6(a) and 6(d) should be revised to indicate that our-spproved fire protection program also includes provisions i | | License Condition 6: Fire Protection Program Conditions 6(a) and 6(d) should be revised to indicate that our-spproved fire protection program also includes provisions i |
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| the Fire-Protection Report (FPR) which make the report self-consistent and do not alter the conclusions of the analysis of fire hazards. For example,.the current report contains figures which identify certain-exterior walls as fire barriers. Where the analyses discussed in the FPR show that fire protection is adequate without these fire barriers, we do not intend to maintain these walls as fire barriers. The figures in the FPR will be revised but no additional NRC review needs to be performed. | | the Fire-Protection Report (FPR) which make the report self-consistent and do not alter the conclusions of the analysis of fire hazards. For example,.the current report contains figures which identify certain-exterior walls as fire barriers. Where the analyses discussed in the FPR show that fire protection is adequate without these fire barriers, we do not intend to maintain these walls as fire barriers. The figures in the FPR will be revised but no additional NRC review needs to be performed. |
| License Condition 7: Control Room Human Factors This Condition should be revised to specify panels 1PM07J and 1PM05J rather than IPM07J and IPM05J. | | License Condition 7: Control Room Human Factors This Condition should be revised to specify panels 1PM07J and 1PM05J rather than IPM07J and IPM05J. |
| License Condition 9: TMI Item II.F.1 This Condition should be revised to require operability of the. iodine / particulate sampling system through the first refueling cycle. By letter dated August 17, 1984 from T. R. Tramm to H. R. | | License Condition 9: TMI Item II.F.1 This Condition should be revised to require operability of the. iodine / particulate sampling system through the first refueling cycle. By {{letter dated|date=August 17, 1984|text=letter dated August 17, 1984}} from T. R. Tramm to H. R. |
| Denton we are committed to resolution of questions arising from recent research regarding the adequacy of these systems. | | Denton we are committed to resolution of questions arising from recent research regarding the adequacy of these systems. |
| License Condition 11: Emergency Planning | | License Condition 11: Emergency Planning |
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| License Condition 18: Control Room Ventilation Systems This Cendition should be revised to delete reference to the filters in the recirculation portion of the control room ventilation system. Modifications to this system have been discussed with the | | License Condition 18: Control Room Ventilation Systems This Cendition should be revised to delete reference to the filters in the recirculation portion of the control room ventilation system. Modifications to this system have been discussed with the |
| .NRC Staff which would make consideration of these charcoal filters unnecessary in evaluations of accident doses. | | .NRC Staff which would make consideration of these charcoal filters unnecessary in evaluations of accident doses. |
| License Condition 19: Turbine Missiles This Condition should be deleted. By letter dated September 26, 1984, from T. R. Tramm to H. R. Denton, Commonwealth Edison committed to a program of turbine maintenance which includes inspection of all three low pressure turbine rotors within the first 3 and 1/2 operating years based on 'nanufacturer's calculations. | | License Condition 19: Turbine Missiles This Condition should be deleted. By {{letter dated|date=September 26, 1984|text=letter dated September 26, 1984}}, from T. R. Tramm to H. R. Denton, Commonwealth Edison committed to a program of turbine maintenance which includes inspection of all three low pressure turbine rotors within the first 3 and 1/2 operating years based on 'nanufacturer's calculations. |
| Subsequent interva.ls will also be based upon the manufacturer,s calculations. | | Subsequent interva.ls will also be based upon the manufacturer,s calculations. |
| License Condition 20: Steam Generator Tube Rupture This Condition should be deleted. By letter dated October 1 2 , ~'1 9 8 4 from T. R. Tramm to H. R. Denton, Commonwealth Edison committed'to resolution of outstanding NRC generic questions regarding steam generator tube rupture analyses in conjunction with the owner's group effort. The analytical work is scheduled to be completed by May, 1985. This commitment includes all necessary Technical Specification revisions. | | License Condition 20: Steam Generator Tube Rupture This Condition should be deleted. By letter dated October 1 2 , ~'1 9 8 4 from T. R. Tramm to H. R. Denton, Commonwealth Edison committed'to resolution of outstanding NRC generic questions regarding steam generator tube rupture analyses in conjunction with the owner's group effort. The analytical work is scheduled to be completed by May, 1985. This commitment includes all necessary Technical Specification revisions. |
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1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
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Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML20205B4241999-03-23023 March 1999
Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util
ML20207K0351999-03-0404 March 1999
Forwards Util Which Transmitted Corrected Pages to SG Replacement Outage Startup Rept.Subject Ltr Was Inadvertently Not Sent to NRC Dcd,As Required by 10CFR50.4
ML20205C6861999-03-0404 March 1999
Provides Notification That Byron Station Implemented ITS on 990205 & Braidwood Station Implemented ITS on 990219
ML20207D6831999-03-0101 March 1999
Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d)
ML20207D4301999-02-26026 February 1999
Informs NRC That Supplemental Info for Byron & Braidwood Stations Will Be Delayed.All Mod Work Described in Ltr Is on Schedule,Per GL 96-06
ML20207B8971999-02-25025 February 1999
Expresses Concern That Low Staffing Levels & Excessive Staff Overtime May Present Serious Safety Hazard at Some Commercial Nuclear Plants in Us
ML20203C7001999-02-0202 February 1999
Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List
ML20202F5911999-01-29029 January 1999
Forwards Byron Unit 1 Cycle 9 COLR in ITS Format & W(Z) Function & Byron Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function. New COLR Format Has Addl Info Requirements
ML20199E1611999-01-15015 January 1999
Forwards Response to 980902 RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. CE Endorses Industry Response to RAI as Submitted by NEI
ML20199B7511999-01-0808 January 1999
Forwards Proprietary Versions of Epips,Including Rev 52 to Bzp 600-A1 & Rev 48 to Bzp 600-A4 & non-proprietary Version of Rev 52 to Bzp 600-A1 & Index.Proprietary Info Withheld
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059K6741990-09-17017 September 1990
Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided
ML20059L6611990-09-10010 September 1990
Forwards Byron Station Units 1 & 2 Inservice Insp Program
ML20064A3681990-08-24024 August 1990
Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA
ML20064A0181990-08-16016 August 1990
Submits Supplemental Response to NRC Bulletin 88-008,Suppls 1 & 2.Surveillance Testing Revealed No Leakage,Therefore Charging Pump to Cold Leg Outage Injection Lines Would Not Be Subjected to Excessive Thermal Stresses
ML20063Q1051990-08-10010 August 1990
Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2
ML20055J1221990-07-25025 July 1990
Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary
ML20055H7631990-07-25025 July 1990
Forwards Financial Info Re Decommissioning of Plants
ML20055J1261990-07-25025 July 1990
Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses
ML20055G3251990-07-16016 July 1990
Responds to SALP Board Repts 50-454/90-01 & 50-455/90-01 for Reporting Period Nov 1988 - Mar 1990.Effort Will Be Made to Continue High Level of Performance in Areas of Radiological Controls,Plant Operations,Emergency Preparedness & Security
ML20044A9621990-07-13013 July 1990
Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc
ML20044B1411990-07-12012 July 1990
Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request
ML20044B2081990-07-11011 July 1990
Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl
ML20044B2141990-07-11011 July 1990
Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification
ML20044A9521990-07-10010 July 1990
Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage
ML20044A7991990-06-29029 June 1990
Forwards Description of Change Re Design of Containment Hydrogen Monitoring Sys,Per 900517 Request.Util Proposing Alternative Design Ensuring Containment & Hydrogen Monitoring Sys Operability in Event of Power Loss
ML20055D4811990-06-29029 June 1990
Discusses Revised Schedule for Implementation of Generic Ltr 89-04 Re Frequently Identified Weaknesses of Inservice Testing Programs.All Procedure Revs Have Either Been Approved or Drafted & in Onsite Review & Approval Process
ML20055D2951990-06-22022 June 1990
Discusses Results of 900529-0607 Requalification Exam.Based on Results of Exam,Station Removed/Prohibited Both Shift & Staff Teams & JPM Failure from License Duties.Shift Team Placed in Remediation Program from 900611-14
ML20058K3521990-06-22022 June 1990
Requests Withdrawal of 900315 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Specs 3.8.1.1 & 4.8.1.1.2 to Clarify How Gradual Loading of Diesel Generator Applied to Minimize Mechanical Stress on Diesel
ML20043D3151990-06-0101 June 1990
Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043E3141990-05-31031 May 1990
Withdraws 880302 Application for Amend to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,changing Tech Spec 4.6.1.6.1.d to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin,Due to Insufficient Available Data
ML20043F4731990-05-30030 May 1990
Forwards Suppl to 881130 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Changes Requested Per Generic Ltr 87-09,to Remove Unnecessary Restrictions on Operational Mode Changes & Prevent Plant Shutdowns
ML20043C8641990-05-29029 May 1990
Forwards Rept of Local Leakage Rate Test Results for Third Refueling Outage.Leakage Rates of Six Valves Identified as Contributing to Failure of Max Pathway Limit
ML20043B7691990-05-23023 May 1990
Forwards Endorsement 11 to Nelia & Maelu Certificates N-93 & M-93 & Endorsement 9 to Nelia & Maelu Certificates N-101 & M-101
ML20043A9161990-05-16016 May 1990
Provides Advanced Notification of Change That Will Be Made to Fire Protection Rept Pages 2.2-18 & 2.3-14
ML20043A6391990-05-11011 May 1990
Submits Revised Schedule for Implementation of Generic Ltr 89-04 Guidance.Rev to Procedures for Check Valve & Stroke Time Testing of power-operated Valves Will Be Completed by 900629
ML20043A2891990-05-10010 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for Byron Nuclear Power Station
ML20042G7111990-05-0707 May 1990
Responds to NRC Questions Re leak-before-break Licensing Submittal for Stainless Steel Piping.Kerotest Valves in Rh Sys Will Be Replaced in Byron Unit 2 During Next Refueling Outage Scheduled to Begin on 900901
ML20042F6851990-05-0404 May 1990
Requests Resolution of Util 870429,880202 & 0921 & 890130 Submittals Re Containment Integrated Leak Rate Testing in Response to Insp Repts 50-454/86-35 & 50-455/86-22 by 900608
ML20042G3591990-04-30030 April 1990
Forwards Errata to Radioactive Effluent Rept for Jul-Dec 1989,including Info Re Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor
ML20055C5761990-04-30030 April 1990
Forwards Results of Investigation in Response to Allegation RIII-90-A-0011 Re Fitness for Duty.W/O Encl
ML20042E9601990-04-30030 April 1990
Forwards Response to NRC 900327 Ltr Re Violations Noted in Insp Repts 50-454/90-09 & 50-455/90-08.Response Withheld (Ref 10CFR73.21)
ML20042E9111990-04-25025 April 1990
Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants.
ML20012E1081990-03-21021 March 1990
Forwards Calculations Verifying Operability of Facility Dc Battery 111 W/Only 57 of 58 Cells Functional & Onsite Review Notes,Per Request
ML20012D8671990-03-21021 March 1990
Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date
ML20012C5471990-03-12012 March 1990
Provides Results of Completed Util Reviews & Addresses Addl Info Requested by NRC Re 890317 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Change Tech Spec 4.5.2,supplemented on 890825 & 890925-27 Meetings
ML20006E1441990-02-16016 February 1990
Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals
ML20012A4491990-02-16016 February 1990
Advises That 16 Tubes in All Four Steam Generators Removed from Svc as Result of Eddy Current Insp During Cycle 3 Refueling Outage.Tube Plugging Distribution Between Steam Generators Listed
ML20006E4201990-02-14014 February 1990
Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690
ML20006E2611990-02-0909 February 1990
Responds to NRC Bulletin 88-009 Re Thimble Tube Thinning. Thimble Tube Insps Performed Using Eddy Current Testing Methodology & Performed at Every Refueling Outage Until Sufficient Data Accumulated to Generate Correlation
ML20011F3661990-02-0707 February 1990
Forwards Errata to Radioactive Effluent Rept for Jan-June 1989 & Advises That Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor
ML20006D6911990-02-0202 February 1990
Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle
ML20006E1521990-01-31031 January 1990
Discusses Applicability of Safety Evaluations Prior to Manipulation of ECCS Valves,In Response to Violations Noted in Insp Repts 50-454/89-16 & 50-455/89-18.Nuclear Operations Directive Re ECCS Valve Positions Will Be Sent by 900415
ML19354E4451990-01-22022 January 1990
Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters
ML20005G7161990-01-20020 January 1990
Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl
ML20005G3831990-01-10010 January 1990
Suppls 891117 Application for Amends to Licenses NPF-37 & NPF-66,incorporating Further Clarification of Curve Applicability in Tech Spec Figure 3.4-2a,per 891229 Telcon W/Nrc
ML20005G6431990-01-10010 January 1990
Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood
ML20006B8821990-01-10010 January 1990
Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs
ML20005E1911989-12-26026 December 1989
Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21
ML20005E1751989-12-22022 December 1989
Forwards Rev 29 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML19332F6621989-12-14014 December 1989
Forwards Amend 12 to, Byron/Braidwood Stations Fire Protection Rept. Amend Reflects Changes to Facility & Procedures Effective 890630
1990-09-17
[Table view] |
Text
f'~ N Commonwealth Edison
[ ,) One First N!tional Pitt2, Chicago Ilknors f 'g \ C ' Addrzss R ply to. Post Office Box 767
'N Chicago, Illinois 60690 October 20, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject: Byron Generating Station Units 1 and 2 Draft License NPF-23 NRC Docket No. 50-454 Reference (a): October 18, 1984 letter T. M. Novak to D. L. Farrar
Dear Mr. Denton:
This letter provides Commonwealth Edison comments on the draft of the Byron 1 license which was sent to us in Reference (a).
We urge that the comments in Attachment A to this letter be carefully considered before the license is finalized.
We are available to discuss these matters in more detail if necessary. Further discussions are needed if any of these comments are not incorporated into the license.
Very truly yours, f g f.A?1==_- -
T. R. Tramm Nuclear Licensing Administrator Attachments 9363N h0hf0 A
Ob Ij
ATTACHMENT A Comments on Draft License a
License Condition 1: Maximum Power Level This license should be issued for the full power level, 3411 megswatts thermal, with 5% limitation pending Commission approval. Such a License Condition would not need revision unless the Commissioners approve operation at less than full power. If only a 5% license is to be issued at this point, the following draft License Conditions are meaningless: 3(c), 3(d), 3(f), 6(d), 6(e),
6(f), 6(g), 7, 8, 9, 11, 13, 16, 18, 20, 21, and 22.
s License Condition 2: Technical Specifications and Environmental Protection Plan Our comments on the Technical Specifications have been provided to the Staff in review meetings. The Environmental Protection Plan is acceptable.
License Condition'3: Post-Fuel-Loading Initial Test Program _
The requirement to obtain NRC approval if the test program is delayed should be modified to permit continued operation of the plant at a given power level if the results of the startup tests to that plateau are properly reviewed by Commonwealth Edison and found acceptable within the specified time periods. Continued power operation during an unexpected delay will not endanger the public health and safety as long as the test results are satisfactory. For example, a breakdown of secondary side pumps or heat exchangers which imposes a temporary power limitation would raise no new safety issue.
License Condition 5: Equipment Qualification The requirement to reevaluate the environmental conditions resulting from a HELB outside containment should be deleted. A preliminary evaluation was provided by letter dated October 18, 1984 from T. R. Tramm to H. R. Denton which contained our commitment to further review of this issue. The results of preliminary evaluations were also provided which indicated that there is reasonable. assurance that the reactor can be operated safely while more detailed analyses are completed and reviewed.
License Condition 6: Fire Protection Program Conditions 6(a) and 6(d) should be revised to indicate that our-spproved fire protection program also includes provisions i
F +
- b n described in letters dated August 20, 1984, October 11, 1984 and
' October 15, 1984 from.T. R. Tramm to H. R. Denton.
~
Condition 6(c) should be revised to require that changes to the fire protection program be reported on a schedule consistent with changes which are reported pursuant to 50.59. This will greatly simplify our reporting task and make NRC reporting requirements more uniform.
Condition 6(c) should also be revised to allow for changes 4
the Fire-Protection Report (FPR) which make the report self-consistent and do not alter the conclusions of the analysis of fire hazards. For example,.the current report contains figures which identify certain-exterior walls as fire barriers. Where the analyses discussed in the FPR show that fire protection is adequate without these fire barriers, we do not intend to maintain these walls as fire barriers. The figures in the FPR will be revised but no additional NRC review needs to be performed.
License Condition 7: Control Room Human Factors This Condition should be revised to specify panels 1PM07J and 1PM05J rather than IPM07J and IPM05J.
License Condition 9: TMI Item II.F.1 This Condition should be revised to require operability of the. iodine / particulate sampling system through the first refueling cycle. By letter dated August 17, 1984 from T. R. Tramm to H. R.
Denton we are committed to resolution of questions arising from recent research regarding the adequacy of these systems.
License Condition 11: Emergency Planning
-This Condition should be deleted. All three of these requirements of the ASL8's Initial Decision have been completed.
Letters dated August 16, 1984 from T. R. Tramm to H. R. Denton and.
October 12, 1984 from T. R. Tramm to H. R. Denton provide documentation of the completion of these tasks.
License Condition 12: Reliability of Diesel Generators This Condition should be deleted. By letter dated October 16,.1984 from T. R. Tramm to H. R. Denton we provided the results of our further evaluation of the effects of diesel engine vibration on the panel-mounted controls and instrumentation. No changes were found-toibe necessary.
l
a License Condition 15: Formal FEMA Finding
-This Condition should be deleted. Existing regulations already provide for this eventuality.
License Condition 16: Protection Against Postulated Breaks or Cracks in High Energy and Moderate Energy Lines This Condition should be revised to acknowledge that FSAR Section 3.6.2 is being revised in accordance with commitments made in response to IDI/IDR findings. Advance copies of these FSAR revisions were provided by letter dated October 19, 1984 from T. R.
Tramm to H. R. Denton.
License Condition 18: Control Room Ventilation Systems This Cendition should be revised to delete reference to the filters in the recirculation portion of the control room ventilation system. Modifications to this system have been discussed with the
.NRC Staff which would make consideration of these charcoal filters unnecessary in evaluations of accident doses.
License Condition 19: Turbine Missiles This Condition should be deleted. By letter dated September 26, 1984, from T. R. Tramm to H. R. Denton, Commonwealth Edison committed to a program of turbine maintenance which includes inspection of all three low pressure turbine rotors within the first 3 and 1/2 operating years based on 'nanufacturer's calculations.
Subsequent interva.ls will also be based upon the manufacturer,s calculations.
License Condition 20: Steam Generator Tube Rupture This Condition should be deleted. By letter dated October 1 2 , ~'1 9 8 4 from T. R. Tramm to H. R. Denton, Commonwealth Edison committed'to resolution of outstanding NRC generic questions regarding steam generator tube rupture analyses in conjunction with the owner's group effort. The analytical work is scheduled to be completed by May, 1985. This commitment includes all necessary Technical Specification revisions.
License Condition 21: Reactor Systems Technical Specification This Condition should be deleted. By letter dated October
-11, 1984- from T. R. Tramm to H. R. Denton, Commonwealth Edison b
_4 committed to resolution of outstanding Reactor Systems Branch generic questions .regarding Technical Specifications in con junction with owner's group' efforts. The schedule for completion of this effort is uncertain.
License Condition 22: Energy Absorbing Material We understand that this license condition will be deleted from'this list and added to the list in Attachment 1 which is
' incorporated by License Condition 1.
9363N s
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