Similar Documents at Byron |
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Category:CORRESPONDENCE-LETTERS
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) ML20217M2871999-10-21021 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 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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 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 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 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 ML20211P1841999-09-0808 September 1999 Forwards Insp Repts 50-454/99-15 & 50-455/99-15 on 990824- 26.No Violations Noted.Objective of Insp to Determine Whether Byron Nuclear Generating Station Emergency Plan Adequate & If Emergency Plan Properly Implemented ML20211Q6821999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Byron Operator Licesne Applicants During Wks of 000619 & 26.Validation of Exam Will Occur at Station During Wk of 000529 ML20211N5151999-09-0303 September 1999 Ack Receipt of Re Safety Culture & Overtime Practices at Byron Nuclear Power Station.Copy of Recent Ltr from NRC to Commonwealth Edison Re Overtime Practices & Safety Culture Being Provided ML20211K1081999-09-0202 September 1999 Responds to Request for Addl Info to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Braidwood,Units 1 & 2 & Byron,Unit 2 ML20211M1371999-09-0202 September 1999 Discusses 990527 Meeting with Ceco & Byron Station Mgt Re Overtime Practices & Conduciveness of Work Environ to Raising Safety Concerns at Byron Station.Insp Rept Assigned for NRC Tracking Purposes.No Insp Rept Encl 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) ML20211G4021999-08-25025 August 1999 Forwards Insp Repts 50-454/99-10 & 50-455/99-10 on 990622-0802.No Violations Noted ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed 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 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 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.. 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 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 ML20210A3151999-07-16016 July 1999 Forwards Insp Repts 50-454/99-08 & 50-455/99-08 on 990511-0621.Three Violations Being Treated as Noncited Violations ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196K0161999-06-30030 June 1999 Discusses 990622 Meeting at Byron Nuclear Power Station in Byron,Il.Purpose of Visit Was to Meet with PRA Staff to Discuss Ceco Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20212H8241999-06-24024 June 1999 Informs That Effective 990531 NRC Project Mgt Responsibility for Byron & Braidwood Stations Was Transferred to Gf Dick ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed ML20207G0601999-06-0707 June 1999 Provides Updated Info Re Number of Failures Associated with Initial Operator License Exam Administered from 980914-0918. NRC Will Review Progress Wrt Corrective Actions During Future Insps ML20207G0421999-06-0404 June 1999 Forwards Insp Repts 50-454/99-04 & 50-455/99-04 on 990330-0510.Violations Identified & Being Treated as non-cited Violations ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207E5451999-05-28028 May 1999 Forwards Insp Repts 50-454/99-07 & 50-455/99-07 on 990517-20.No Violations Noted.Fire Protection Program Was Effective ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions ML20207B6361999-05-25025 May 1999 Forwards SE Accepting Revised SG Tube Rupture (SGTR) Analysis for Bryon & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed ML20206U3471999-05-20020 May 1999 Forwards Insp Rept 50-454/99-05 on 990401-22.No Violations Noted.Insp Reviewed Activities Associated with ISI Efforts Including Selective Exam of SG Maint & Exam Records, Calculations,Observation of Exam Performance & Interviews ML20207A2151999-05-19019 May 1999 Forwards Insp Repts 50-454/99-06 & 50-455/99-06 on 990419-23.No Violations Noted.Insp Consisted of Review of Liquid & Gaseous Effluent Program,Radiological Environmental Monitoring Program,Auditing Program & Outage Activities 1999-09-08
[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) ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes 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 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) 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 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 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.. 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 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 ML20207H7501999-07-12012 July 1999 Forwards Revised Pressure Temp Limits Rept, for Byron Station,Units 1 & 2.Revised Pressurized Thermal Shock Evaluations,Surveillance Capsule Rept & Credibility Repts, Also Encl ML20209G1391999-07-0909 July 1999 Forwards Results of SG Tube Insps Performed During Byron Station,Unit 1,Cycle 9 Refueling Outage within 12 Months Following Completion of Insps ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196G2161999-06-25025 June 1999 Forwards for NRC Region III Emergency Preparedness Inspector,Two Copies of Comed Emergency Preparedness Exercise Manual for 1999 Byron Station Annual Exercise. Exercise Is Scheduled for 990825.Without Encls ML20209D4861999-06-17017 June 1999 Informs That R Heinen,License OP-30953-1 & a Snow,License SOP-30212-3,no Longer Require License at Byron Station 05000454/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed1999-06-0808 June 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i)(b).There Are Two Actions Remaining to Address Cause of Event.Both Actions Are Listed ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20211M1611999-05-28028 May 1999 Discusses 990527 Meeting with Comed Re Safety Culture & Overtime Control at Byron Nuclear Plant from Videoconference Location at NRC Headquarters.Requests That Aggressive Actions Be Taken to Ensure That Comed Meets Expectations ML20207D5261999-05-26026 May 1999 Forwards Response to NRC 990318 RAI Concerning Alleged Chilling Effect at Byron Station.Attachment Contains Responses to NRC 12 Questions ML20211M1781999-05-25025 May 1999 Summarizes Concerns with Chilling Effect & Overtime Abuses at Commonwealth Edison,Byron Station.Request That Ltr Be Made Part of Permanent Record of 990527 Meeting ML20195C7911999-05-25025 May 1999 Forwards Revised COLR for Byron Unit 2,IAW 10CFR50.59.Rev Accounts for Planned Increase of Reactor Coolant Full Power Average Operating Temp from 581 F to 583 F 05000454/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed1999-05-21021 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i)(B).Required Actions to Address Causes of Event Listed ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20207E9831999-05-18018 May 1999 Forwards Copy of Commonwealth Edison Co EP Exercise Evaluation Objectives for 1999 Byron Station Annual EP Exercise,Which Will Be Conducted on 990825.Without Encl ML20206N8551999-05-11011 May 1999 Forwards 1998 Annual Radioactive Environ Operating Rept for Byron Station. Rept Includes Summary of Radiological Liquid & Gaseous Effluents & Solid Waste Released from Site ML20206U3351999-04-30030 April 1999 Forwards Evaluation of Matter Described in Re Byron Station.Concludes That Use of Overtime at Byron Station Was Controlled IAW Administrative Requirements & Mgt Expectations Established to Meet Overtime Requirement of TS ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206C7901999-04-23023 April 1999 Provides Suppl Info Re Use of W Dynamic Rod Worth Measurement Technique,As Requested During 990413 Telcon.Rev Bars in right-hand Margin Identify Changes from Info Submitted by ML20206E7521999-04-22022 April 1999 Submits Rept on Number of Tubes Plugged or Repaired During Inservice Insp Activities Conducted at Plant During Cycle 9 Refueling Outage,Per TS 5.6.9 ML20206A7431999-04-22022 April 1999 Forwards Comments Generated Based on Review of NRC Ltr Re Preliminary Accident Sequence Precursor Analysis for Byron Station,Unit 1 ML20206B3941999-04-21021 April 1999 Forwards Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors, for Byron & Braidwood Stations.Updated Info Re PCT for Limiting Small Break & Large Break LOCA Analysis Evaluations & Detailed Description of Errors ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205S9621999-04-20020 April 1999 Responds to 981203 RAI Telcon Re SG Tube Rupture Analysis for Byron Station,Unit 2 & Braidwood Station,Unit 2.Addl Info & Subsequent Resolution of Issues Discussed During 990211 Telcon Are Documented in Encl ML20206A8141999-04-20020 April 1999 Advises NRC of Review of Cycle 10 Reload Under Provisions of 10CFR50.59 & to Transmit COLR for Upcoming Cycle ML20205T3901999-04-13013 April 1999 Forwards Byron Station 1998 Occupational Radiation Exposure Rept, Which Is Tabulation of Station,Utility & Other Personnel Receiving Annual Deep Dose Equivalent of Less than 100 Mrem ML20196K6661999-03-31031 March 1999 Forwards Byron Nuclear Power Station 10CFR50.59 Summary Rept, Consisting of Descriptions & SE Summaries of Changes, Tests & Experiments.Rept Includes Changes Made to Features Fire Protection Program,Not Previously Presented to NRC ML20205K5841999-03-31031 March 1999 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] |
Text
p - 4 g, je T Commonwealth Edison
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Downers Grove, liknois 60515
-March 11,1994
/
' William T. Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Revision 10 of the Byron Station Inservice Testing Program for Pumps; and Revision 12 of the Byron Station Inservice Testing -
Program for Valves e
Byron Station Units 1 and 2 "g . (NPF-37/66; NRC Docket Nos. 50-454/455)
References:
- 1. R. J. Barrett letter to T. J. Kovach dated January 31,1992
.3 transmitting the SER for Byron's Pump and Valve Program
- 2. J. E. Dyer letter to T. J. Kovch dated January 25,1993 y transmitting the SER for Relief3. qtest VR-4 for Byron Station n
- 3. J. E. Dyer letter to D. L. Farrar dated 09/14/93 transmitting the SER for Braidwood's Pump and Valve Program
- 4. D. J. Chrzanowski letter to T. E. Murley dated February 8,1993
- ' transmitting Byron's response to the January 31,1992 SER
Dear Mr. Russell:
Attached for your review and approva.' are Revision 10 of the IST Pump Program' ,
and Revision 12 of the IST Valve Program for Byron Station.
'l IST Pump Program There are no current commitments prompting the submittal of Revision 10 of the .
IST Pump Program.. All IST Pump Program open items identified in Byron's SER i (Reference 1) were addressed in' Byron's response to NRR (Reference 4), which 3 included the addition of vendor information to PR-7. In order to keep the program L
up to date,'however, results from the January 31,1992 SER and other i ."
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W. T. Russell 2 March 11,1994 administrative changes have been incorporated into this revision. The pump tables and relief requests have been changed to reflect the PR-1, PR-2, and PR-7 relief requests addressed in References 1 and 4. In addition, ISXO4P, which has been IST tested in the past, was officially entered into the pump tables.
IST Valve Program The IST Valve Program revisions are being submitted primarily in response to two open items regarding VR-2 and VR-19 discussed in References 1 and 4. Other items, summarized below, have also been addressed in this revision.
On January 31,1992, an NRC SER was issued for the Byron Station IST programs which included four open items. All but two of these items (VR-2 and VR-19) were addressed in a previous response to NRR in Reference 4.
Per Reference 1, VR-2, concerning the testing of the CS020 check valves, was approved "provided the licensee complies with the GL 89-04, Position 2 guidelines..." The NRC also stated that "the licensee should actively investigate the use of non-intrusive diagnostic techniques to demonstrate that these valves ;
exercise open during flow testing". At the time of Byron's response (Reference 4),
Braidwood had already submitted a variation of this relief request. In an effort to conserve time by eliminating the need for two independent reviews, Byron requested to defer responding to the VR-2 issue until after the issuance of Braidwood's SER, which was subsequently issued on September 14,1993.
Similarly, per Reference 1, VR-19, concerning the backflow test for the AF001 check valves was approved, however, the NRC stated that "the licensee should actively investigate the use of non-intrusive diagnostic techniques to demonstrate that these valves will close upon cessation or reversal of flow." Braidwood had already submitted a relief request including non-intrusive diagnostic techniques.
Byron, again, requested to defer response to this issue until after issuance of the Braidwood SER.
Revision 12 to Byron's IST Valve program includes Byron's approved VR-2 (per Reference 1), which is contingent upon following the guidelines outlined in GL 89-04, Position 2. Upon further review with Braidwood, it was determined that non-intrusive techniques are not possible. Rather than revising the current VR-2, draft VR-2A has also been submitted, which extends the frequency for disassembly and inspection to once every five years in conjunction with the eductor Technical Specification flow test. The NRC denied Braidwood's VR-2 in their latest SER (Reference 3) as additional information was requested.
Braidwood subsequently supplied the NRC with the requested information in their response to the September 1993 SER Note that the Byron Relief Request VR-2A contained in this submittal is the same as Braidwood's VR-2 Byron requests that relief request VR-2A be reviewed and approved by 8/20/94, prior to Byron's next
5 W. T. Russell 3 March 11,1994 refueling outage. VR-19 has been revised in conjunction with Braidwood to include acoustic diagnostic techniques to verify closure of the AF001 check valves.
Success with the acoustic techniques has only been shown during the 18 month dual pump injection test which is performed at the beginning of each refueling outage. If the results of the acoustic evaluation are questionable, the valve will then be scheduled for disassembly and internal visual inspection during that outage as was approved in Reference 1 for VR-19. Again, Braidwood and Byron will be submitting the same relief request, anticipating a potential combined ,
program submittal in 1995.
In addition to the changes listed above, this revision to the IST Valve Program also includes items arising from the Braidwood NRC inspection in May,1993 and the Byron NRC inspection in January,1994. The Braidwood and Byron inspections prompted the addition of a few valves to the Program that were determined to satisfy the IST scope requirements and which should be IST tested.
Also, the concern of stroke timing valves in both directions for valves that have an active IST safety function in both directions is addressed. A review of the valves currently in the IST program has been completed in an expedited manner, as requested by the NRC inspectors. Valves which will be stroked in both directions have been identified in this program revision.
Byron and Braidwood have recognized the fact that a scope review was needed to
. incorporate new interpretations of the code and regulatory requirements to ensure that all the necessary pumps and valves are being IST tested. A few valves are being added to the Program that have been identified by Byron /Braidwood as satisfying the OM-10 scope requirements for IST. The ongoing scope review by Byron and Braidwood should be completed by June 30,1994.
Additional items included in the IST Valve Program Revision 12 are as follows.
Technical Approach and Positions VA-05 and VA-06 have been added. VA-05 justifies exercising the U-0 CC Heat Exchanger and Pump isolation / separation manual valves on a U-2 Cold Shutdown frequency. VA-06 addresses stroke time corrective actions. Byron will be converting from the IWV corrective actions to the OM-10 corrective actions in preparation for Byron's ten year update in 1995.
Additional relief requests added in this revision include draft relief requests VR-15A-D, which were included in an effort to bring Byron's Program closer to Braidwood's IST Program, in anticipation of the potential 1995 Byron /Braidwood combined submittal. VR-20 is also being submitted consistent with GL 89-04.
Other miscellaneous editorial and administrative changes have also been incorporated.
y
W. T. Russell 4 March 11,1994 Please direct any comments or questions to this office. .;
Respectfully, ooydIf MO Joseph A. Bauer Nuclear Licensing Administrator n
f JAB /gp r
Attachments ec: . G. F. Dick, Byron Project Manager - NRR H. Peterson, SRI - Byron B. Clayton, Branch Chief- Region III Oflice of Nuclear Facility Safety - IDNS-d 9
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Ilyron Station Inservice Testing Pmgmm for Pumps Revision 10 and Inservice Testing Pmgnmi for Valves Revision 12 Index Attachment A Summary of Changes for Revision 10 of the Inservice Testing Program Plan for Pumps Attachment B Summary of Changes for Revision 12 of the Inservice Testing Program Plan for Valves Section 3.0 Inservice Testing Program Plan for Pumps Section 4.0 Inservice Testing Program Plan for Valves t
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ATTACIIMENT A Summary of Changes for Revision 10 of the Inservice Testing Pn> gram Plan for Pumps Sectior 3.0 - Tab!e of Contents
- 1. Revised to reflect program changes.
Section 3.1 - Program D_qscription
- 1. No change.
Section 3.2 - Program References
- 1. Added SER (Safety Evaluation Report) dated January 31,1992.
- 2. Added Byron Letter 93-0047, SER 01/31/92 response.
Section 3.3 - Pump _ Tables A. Pump Table Descrintion l .. No change.
B. Pumn Tabin
- 1. 1/2 A F0 l PA, 1/2 A F0 l PB , 1/2CV0 l PA, 1/2C V0 l PB, 1/2SI0 l PA, 1/2S I0 l PB, 1/2SX01 PA, 1/2SX0 l PB, 2SX04P: changed "Yes" under bearing temperature column to PR-2, due to the approval of PR-2, which includes all pumps.
- 2. Deleted Note 6 from 2SX04P pump.
- 3. Added ISXO4P pump to table.
- 4. Under Vibration column, changed PR-1 to PR-7 for the OSX02PA and OSX02PB pumps due to the approval of PR-7.
. Section 3.4 - Pump _ Notes
- 1. Deleted Note 6 due to ISXO4P implementation.
Section 3.5 - Pump Technical Anoroaches and Positions
- 1. No change.
l Attachment A Page _2
~
Section 3.6 - Pump Relief Requests
- 1. PR-1: Deleted PR-1 from Rev 9 and replaced with the Draft PR-1 from Rev 9a as it was granted per SER 01/31/92 provided all of OM-6 vibration requirements are complied with. Byron is in full compliance with the exception of the SX pumps covered under PR-7.
- 2. PR-2: Deleted PR-02 from Rev 9 and replaced with the Draft PR-2 from Rev 9 as it was granted per SER 01/31/92.
ATTACilMENT H Summary of Changes for Revision 12 of the Inservice Testing Pmgmm Plan for Valves ,
Section 4.0 - Table of Contents
- 1. Deleted Note 32.
- 2. Added Notes 43 through 46.
- 3. Added Technical Approach and Position VA-05 and VA-06.
- 4. Added Draft VR-2A, Draft VR-15A-D and VR-25.
- 5. Deleted the " Draft" associated with VR-20. j Section 4.1 - Program Description
- 1. No change. ,
Section 4.2 - Program Referenen
- 1. Added references to SERs dated August 16, 1991, January 31,1992,and January 25,1993.
Section 4.3 - Valve Tables A. Valve Table Description
- 1. Stroke direction clarified to include the possibility of more than one safety function.
B. Valve Tables
- 1. 1/2AF014A-II - changed test mode for Bt test from OP/RR to CS per NRC inspection at Braidwood.
- 2. 1/2CC9415 - added valves to program to stroke test at cold shutdown in both -
directions per Note 44 and Byron Inspection.
3 1/2CC9437A/B - added open direction to St; added Ft to test method along with Technical Position 2 due to typo; deleted " Passive" under Remarks.
- 4. 1/2CC9463A/B - changed test mode for Ct from CS to OP. !
- 5. OCC9464 - changed test mode for Ct from CS to OP.
- 6. 1/2CC9459B; l/2CC94678 - added manual valves to program per NRC inspection at Byron to cycle in both directions on a U-2 cold shutdown frequency. .
- 7. 1/2CC9473A/B - added closed direction to St 8 1/2CC9486 - added RR test mode for Lt (typo).
a+- w AL A 2- a,4en hr e+ -e4m.,i + e4 3- 944'- ~ L- a<L,- mL $ 4meL- em Attachment B Page 2 '
B. Valve Tables (continued)
- 9. 1/2CC9518 - added CS test mode for Bt (typo); removed " Passive" from remarks.
- 10. 1/2CC9534 - added CS test mode for Bt (typo); removed " Passive" from ,
remarks. 1
- 11. 1/2CS007A/B - added closed direction to St.
- 12. 1/2CS011 A/B - added Ct at RR per VR-25 and Xt at OP.
- 13. 1/2CS019A/B - added closed direction to St.
- 14. 1/2CS020A/B - added Bt at OP.
- 15. 1/2CVll2D/E - added closed direction to St. '
- 16. 1/2CV8106 - removed open direction to St.
- 17. 1/2CV8110 - added open direction to St.
- 18. 1/2CV8111 - added open direction to St.
- 19. 1/2CV8113 - added RR test mode for Lt (typo); added open direction to St; removed " Passive" from remarks.
- 20. 1/2CV8114 - added open direction to St. !
- 21. 1/2CV8116 - added open direction to St.
- 22. 1/2CV8152 - added open direction to St.
- 23. 1/2CV8160 - added open direction to St.
- 24. 1/2CV8440 - added these valves to program based on Westinghouse letter and UFSAR change to active. .
- 25. 1/2CV8480A - added Technical Position 3 for Bt test (Typo).
- 26. 1/2FWO36A-D - added these valves to program per UFSAR change to active.
- 27. 1/2FWO79A-D - added these valves to program per UFSAR change to active. ;
- 28. 1/21A066 - added open direction to St.
- 29. 1/2IA091 - added open direction and Ct; removed " Passive" from remarks.
- 30. 1/2MS013A-D - added closed direction to Rt.
- 31. 1/2MS014A -D - added closed direction to Rt.-
- 32. 1/2MS015A-D - added closed direction to Rt.
- 33. 1/2MS015D - changed open normal position to closed (typo).
34, 1/2MS016A-D - added closed direction to Rt. t 35, 1/2MS017A-D - added closed direction to Rt. ,
- 36. 1/2MS018A-D - added open direction to St.
- 37. 1/2MS019A-D - added these manual valves to program based on scope review. ,
- 38. 1/20G057A - added the open direction to St.
- 39. 1/2OG079 - added the open direction to St.
i
- 40. 1/20G080 - added the open direction to St.
- 41. 1/20G081 - added the open direction to St.
- 42. 1/20G082 - added the open direction to St.
- 43. 1/200083 - added the open direction to St.
- 44. 1/20G084 - added the open direction to St.
t' Attachment B Page 3 B. Valve Tables (continued)
- 45. 1/2OG085 - added the open direction to St. '
+
. 46. 1/2PS228A/B - added the open direction to St.
- 47. ' 1/2PS229A/B - added the open direction to St.
48, 1/2PS230A/B - added the open direction to St.
- 49. 1/2RC014A-D - removed open nonnal position and one of the two open stroke directions (typo). ;
- 50. 1/2RH8701 A/B - added closed direction to St.
- 51. 1/2RIl8702A/B - added closed direction to St.
52.. 1/2RIIS708A/B - added closed direction to Rt.
- 53. 1/2RH8705A/B - deleted normally open position; removed " Passive" from remarks.
- 54. 1/2RIl8716A/B - added these valves to the program per NRC inspection at Braidwood.
- 55. 1/2RII610 - added valves to program per NRC inspection at Byron.
- 56. 1/2RH611 - added valves to program per NRC inspection at Byron.
- 57. 1/2RYO75 - added valves to table per scope review.
- 58. 1/2RY455A,1/2RY456 - added closed direction to St; changed Ft test mode to CS.
- 59. 1/2RY8010A,B,C - added closed direction to Rt.
- 60. 1/2RY8046 - add RR test mode for Lt (typo) per VR-1,
- 61. 1/2S18801 A/B -'added close direction to St.
- 62. 1/2S18802A/B - added close direction to St.
- 63. 1/2S18806 - added close direction to St. .
- 64. 1/2 SIS 809A - added open direction to St.
- 65. 1/2SI8809B - added open direction to St.
- 66. 1/2S18811 A/B - added close direction to St.
- 67. 1/2S18821 A/B - added open direction to St.
~
- 68. 1/2S18835 - added open direction to St.
- 69. 1/2S18840 - added close direction to St.
- 70. 1/2SI8841 A/B - changed Ct test mode from RR f CS per VR-15; dc!eted Xt.
- 71. 1/2S18905C/D - changed Ct test mode from CS to RR per VR-15'(typo).
- 72. 1/2S18922A/B - changed test mode for Ct from CS to RR per VR-3.
- 73. 1/2S18924 - added open direction to St.
- 74. 1/2S18948A-D - change Ct test mode from RR to CS per note 42,
- 75. 1/2SI8949A,B,C.D - add CS for Bt per notes 6 and 40; change Ct test mode from CS to RR per VR-15.
- 76. 1/2S18958A/B - added Bt at OP per Note 27.
- 77. 1/2SX016A/B - added close direction to St; delete " Passive" from remarks.
- 78. 1/2SX027A/B - added close direction to St; delete " Passive" from remarks.
- 79. OSX028A/B - added Bt at OP pe scope review.
- 80. 1/2SX116A - added these check valves based on NRC inspection at Byron.
k
W Attachment B Page 4 B. Valve Tables (continued)
- 81. 1/2SX116B - added these check valves based on NRC inspection at Byron.
- 82. OSX007 - added contol valve per review of NRC inspection at Byron.
- 83. OSX146 - added isolation valve per review of NRC inspection at Byron.
- 84. OSX147 - added isolation valve per review of NRC inspection at Byron.
- 85. 1/2SX174 - added valves to the table per scope review. ,
- 86. 1/2WM191 - removed Bt at CS.
Section 4.4 - Valve Notes
- 1. Footnote added to Note 6 regarding RIi8705 valves not being PlV.
- 2. Changed Note 27 to reflect SI8958 closure function.
- 3. Changed Note 28 to reflect CV8440 closure testing in cold shutdowns when all four RCPs are off.
- 4. Deleted last sentence of Note 30 and added "during unit operation"
- 5. Deleted Note 32.
- 6. Added Note 43 regarding cold shutdown testing of the RH8716s.
- 7. Added Note 44 regarding CC9415 CS testing.-
- 8. Added Note 45 regarding FWO36A-D testing at CS.
- 9. Added Note 46 regarding FWO79A-D testing at CS.
Section 4.5 - Valve Technical Anoroaches and Positions
- 1. Added VA-05 regarding the testing of CC9459B and CC9467B manual valves '
on a U-2 cold shutdown frequency.
- 2. Added VA-06 regarding stroke time corrective actions.
Section 4.6 - Valve Relief Rmuests ,
- l. The approval states of each relief request was updated to show the current approval status as necessary..
- 2. VR Added RYO75 valves per scope review.
- 3. VR This relief has been approved per SER 1/31/92 provided the licensee complies with GL 89-04, position 2. IIence, a partial stroke will be performed following the disassembly.
I
Attachment B Page 5 a
Section 4.6. y;dve Relief Requests (continued).
- 4. Draft VR-2a - Added in anticipation of a joint program with Braidwood in the future as they are also submitting this relief request. Review and approval is requested by 8/20/94, prior to Byron's next refueling outage. Approved VR-2 will be utilized in the interim.
- 5. L) raft VR-15A through VP-15D - Braidwood has approval. Byron is submitting the same relief requests in anticipation of a Byron /Braidwood combined submittal in 1995. However, these are new submittals for Byron and have not specifically been approved for Byron. Approved VR-15 will be utilized in the interim.
15A - CV cold leg injection check valves.
158 - Pressure relief check valves.
15C - Si cold leg and SI/RH hot leg injection check valves.
15D - SI/RH hot leg injection check valves.
- 6. VR-19 revised to reflect Byron's SER dated January 31,1992 and agreement to respond following Braidwood's SER dated Sept. 14,1993. Byron's revised VR- '
19 includes acoustically testing the AF001 valves for closure during the 18 month dual pump injection test rather than diassembling them. However, if the results of acoustic tests are abnormal or questionable, the valve will bc ;
scheduled for disassembly and internal visual ' inspection.
- 7. VR Added this relief request for the CS0lls based on the the reasons given in the request.
t l
L 1
-