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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program ML20206E3721999-04-29029 April 1999 Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML20206B7381999-04-26026 April 1999 Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept ML20205E3471999-03-29029 March 1999 Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to ML20204F4611999-03-19019 March 1999 Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML20203F8041999-02-11011 February 1999 Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c) ML20203C8971999-02-0808 February 1999 Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP ML20202H4891999-01-26026 January 1999 Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr ML20199H2431999-01-15015 January 1999 Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper ML20199E1841999-01-13013 January 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication ML20199E0781999-01-13013 January 1999 Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5 ML20199D9711999-01-13013 January 1999 Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl ML20199E9051999-01-12012 January 1999 Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls ML20199E7671999-01-12012 January 1999 Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24 ML20199A4151999-01-0404 January 1999 Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility ML20198K6551998-12-24024 December 1998 Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant ML20198J4001998-12-21021 December 1998 Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request ML20196H3171998-12-0303 December 1998 Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety ML20196G7541998-11-25025 November 1998 Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request ML20195G9851998-11-17017 November 1998 Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips ML20195H5321998-11-13013 November 1998 Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed ML20195F2271998-11-12012 November 1998 Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21 ML20154M5381998-10-14014 October 1998 Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items ML20154M2211998-10-14014 October 1998 Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld ML20206E3721999-04-29029 April 1999 Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML20206B7381999-04-26026 April 1999 Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined ML20205E3471999-03-29029 March 1999 Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to ML20204F4611999-03-19019 March 1999 Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20203C8971999-02-0808 February 1999 Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP ML20199H2431999-01-15015 January 1999 Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper ML20199D9711999-01-13013 January 1999 Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl ML20199E0781999-01-13013 January 1999 Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5 ML20199E1841999-01-13013 January 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication ML20198K6551998-12-24024 December 1998 Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant ML20196H3171998-12-0303 December 1998 Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety ML20154M2211998-10-14014 October 1998 Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety ML20154E0121998-09-30030 September 1998 Forwards Exemption from 10CFR50.54(q) Re Plant & Suppls ,1120& 980302,0429 & 0828 Which Requested Exemption from Certain Protions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities ML20239A2491998-09-0303 September 1998 Forwards Insp Rept 50-155/98-06 on 980716-0826.No Violations Noted.Overall,Reactor Decommissioning Activities Were Generally Performed Satisfactorily & as Planned.Potential Weaknesses Were Identified in Review of SE Procedure ML20237E2731998-08-25025 August 1998 Discusses NRC Insp Rept 50-155/98-03 on 980527.Violations Noted.Insp Findings Documented in NRC Insp Rept Sent to Util by Ltr ML20237C5461998-08-19019 August 1998 Refers to Revs 133,134 & 135 to Portions of Big Rock Point Plant Emergency Plan.Based on Determinations That Changes in Revs 133-135 Do Not Decrease Effectiveness of Emergency Plan,Nrc Approval Not Required ML20236Y0441998-08-0505 August 1998 Forwards Summary of Decommissioning Insp Plan Through March 1999.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability ML20236V0651998-07-28028 July 1998 Ack Receipt of 980605 Request for Withdrawal of 980325 Request for License Amend for DPR-6,paragraph 2.C.(5), Physical Protection & Closes TAC MA0756 ML20236U4311998-07-24024 July 1998 Forwards Insp Rept 50-155/98-05 on 980528-0715.No Violations Noted.Nrc Concern That Programmatic Assessments of RPP Were Not Initiated Following Identification of Multiple Deficiencies in RP Program During First Half of 1998 IR 05000155/19980041998-07-0808 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-155/98-04 ML20236M4131998-07-0707 July 1998 Ack Receipt of Ltr Dtd 980512,transmitting Changes Identified as Rev 14 to Big Rock Point Security Suitability, Training & Qualification Plan.No NRC Approval Required ML20249C4391998-06-25025 June 1998 Ack Receipt of ,Which Transmitted Changes to Rev 14 to Suitability,Training & Qualification Plan,Submitted Under Provisions 10CFR50.54(p) ML20249B3041998-06-16016 June 1998 Forwards Insp Rept 50-155/98-03 on 980407-0527.Violation Noted & Being Considered for Escalated Enforcement Action. Notice of Violation Not Presently Being Issued for Insp Finding ML20248F3541998-05-28028 May 1998 Responds to to P Harris Which Requested That NRC Retain Resident Inspector at Big Rock Site to Monitor Project for Period of Five Years.Informs That NRC Intends to Assign Inspector to Site for One Year ML20247M9481998-05-15015 May 1998 Ack Receipt of Ltr Dtd 980312,which Transmitted Changes Identified as Rev 7 to Safeguards Contingency Plan,Submitted Under Provisions of 10CFR50.54(p) ML20217D1221998-04-21021 April 1998 Forwards Insp Rept 50-155/98-02 on 980203-0406.No Violations Noted.Emergency Preparedness Exercise Was Completed Satisfactorily,However,Unusual Event Was Declared When Algae Containing Co-60 Alarmed Discharge Canal Radiation Monitor ML20217A5991998-04-16016 April 1998 Forwards Request for Addl Info Re Proposed Changes to Proposed Defueled TS as Detailed in .Questions Were Discussed W/Licensee Staff on 980121-22 & 980311.RAI Summarizes Questions That Remain ML20216J4411998-04-16016 April 1998 Informs That Consumer Request for Exemption from Certain Requirements of 10CFR50.54, Condition of Licenses, Based On,In Part,Determination That Plant Permanantly Shut Down & Defueled Not Required ML20216J9861998-04-16016 April 1998 Forwards SE Approving Licensee 970919 Submittal of Training Program for Certified Fuel Handlers.Comments Also Encl ML20247L4021998-04-14014 April 1998 Discusses Rev 131 to Chapter 5 & Rev 132 to Chapters 2,3 & Appendix H of Big Rock Point Plant Emergency Plan Submitted Under Provisions of 10CFR50.54(q).No NRC Approval Required ML20216G9071998-04-0808 April 1998 Responds to Asking Number of Questions Re Activities at Big Rock Point Nuclear Plant.Particularly on 980203 NRC Requested Addl Info from Utility Re Proposed Changes to Emergency Preparedness Plan ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided IR 05000155/19970151998-03-20020 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-155/97-15 ML20246H0091998-03-19019 March 1998 Discusses Rev 130 to App a of Big Rock Point Nuclear Plants Emergency Plan,Received in Sept 1997.NRC Approval Not Required Based on Determination That Changes Do Not Decrease Effectiveness of Emergency Plan ML20203K7501998-02-26026 February 1998 Forwards Summary of Decommissioning Insp Plan for Remainder of Fy 1998.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events, Resource Availability ML20203H8511998-02-23023 February 1998 Forwards Request for Addl Info Re Exemption from Offsite Emergency Planning Requirements.In Accordance with 10CFR50.30(b),response Must Be Executed in Signed Original Under Oath or Affirmation ML20202J8111998-02-14014 February 1998 Forwards Insp Rept 50-155/97-15 on 971205-980202 & Notice of Violation.Activities in Areas of Facility Mgt & Control, Decommissioning Support & Spent Fuel Safety ML20203E0811998-02-13013 February 1998 Informs That on 980331 & 0401,NRR Will Be Holding 1998 Decommissioning Power Reactor Counterparts Meeting in Arlington,Tx.Recipient Requested to Make Presentation at Subj Meeting.Meeting Agenda Encl ML20202D7751998-02-0808 February 1998 Ack Receipt of Ltr Dtd 980116,which Transmitted Changes Identified as Rev 32 to Big Rock Point Security Plan, Submitted Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan 1999-09-30
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JAN 8 1993 Docket No. 50-155 l
consumers Power company l ATTH: Mr. William L. Beckman Plant Manager Big Rock Point Nuclear Plant 10269 US 31 North Charlevoix, MI 49720-9436 Dear Mr. Beckman SUBJECT: RESPONSE TO UNRESOLVED AND OPEN ITEMS (URC INSPECTION REPORT NO. 50-155/92019(DRS)
This will acknowledge receipt of your letter dated December 23, 1992, in response to our letter dated October 30, 1992, transmitting the responses to unresolved and open items associated with Inspection Report No. 50-155/92019(DRS). This report summarized the results of the electrical distribution system functional inspection (EDSFI) at your Big Rock Point Nuclear Power Plant. We have reviewed your corrective actions and have no further questions at this time. These corrective actions will be examined during future inspections.
Sincerely, m;.s.fiSa w u . i C.U% Mb H. J. Miller, Director Division of Reactor Safety _
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JAf/ 8 1933 Consumers Power Company 2 Divir_ibsttisn cc: David P. Iloffman, Vice President - 11uclear Operations cc w/1tr dtd 12/23/92:
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OC/LFDCB Resident Inspector, RIII James R. Padgett, Michigan Public Service Commission Michigan Department of Public Ilealth L. 01shan, LPM, 11RR E. Imbro, NRR Palisades SRI W. Ilodges, Region I J. Durr, Region I A. Gibson, Region II C. Julian, Region II S. Collins, Region IV T. Stetka, Region IV K. Perkins, Region V L. Miller, Region V
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Consumers William L Becktnan 1%nt Mauger POWEMING MIEHIGAN5 PROGRESS rig Rock Point Nuclear Plant,10269 Us.31 North, Charlevoix, MI 49720 December 23, 1992
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Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 000'.ET 50-155 - LICENSE DPR-6 - BIG ROCK POINT PLANT -
FULLOW-UP RESPONSE TO INSPECTION REPORT 92-019 As discussed in our letter dated November 24, 1992, Consumers Power Company was to provide a response to each of the Open and Unresolved items described in the subject Inspection Report. The attachment to this letter provides this information.
With respect to Open item (155/92019-02) concerning our ungrounded 2.4 KV electrical system, we understand that this issue is under review by the NRC and that no action is required by Consumers Power Company at this time.
Should any questions arise concerning these issues, please contact us at your convenience.
Gregory C Withrow for William L Beckman (Signed)
William L Beckman Plant Manager CC: Administrator, Region ill, USNRC NRC Resident inspector - Big Rock Point ATTACHMENT
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l l ATTACHMENT
. Consumers Power Company i Big Rock Point Plant Docket 50-155 i.
FOLLOW-UP RESPONSE 10 INSPECIl0N REPORT 92-019
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' FOLLOW UP RESPONSE TO INSPECTION REPORT 92 019
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Qpfnjtem 1551R019-01 Lack of a calculation to demonstrate that the 46 kV line could maintain i adequate voltage levels during a design basis accident (DBA) with the 2.4 kV voltage regulator out of service.
Response As discussed in the Inspection Report, a preliminary calculation was performed during the Inspection which concluded this mode of operation acceptable.
A formal load flow calculation will be performed and reviewed by offsite engineering personnel to docement the acceptability of this configuration.
This effort should be completed by May 1, 1993. Within 60 days following completion of the analysis, operating procedures will be updated to advise operators that this mode of operation is acceptable.
QPSD item 155/RQ19-QA Addition of acceptance criteria to the Daily Fuel 011 Report.
Response The Daily Fuel Gil Report has been revised to address this concern. The report now provides a level for each tank at which refuel is required. A copy of the revised report is attached to this letter and we consider all actions complete.
Unr33.91ved Item 155192019-063 Calculations performed during the intpection concluded that the required NPSH for the diesel generator cooling water pump could be met at high flow rates providing signifit. ant lake level decrease or temperature increase do not occur. The Inspectors were concerned that the limits for lake level and temperature were not available to plant operators.
Response As discussed in the report, Consumers Power agreed to issue an Operations Memo to advise plant operators on the potential loss of EDG cooling water pump NPSH due to lake level. This memo was issued on September 25, 1992 and a copy is attached for your information. As stated in the Operations Memo, this guidance will remain in effect until the issue is resolved or the information is incorporated into the operating procedures.
The reason that temperature monitoring was not included in the guidance is because enhancements are in progress to improve flow characteristics and monitoring of this piping. These enhancements will be completed prior to lake water temperature increasing due to summer temperature effects. Flow characteristic improvements will mitigate the effects of warmer water on the cooling capability of this system.
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Untelolved item 155/92019-068 The team was concerned that the suction pressure acceptance criteria identified in the weekly surveillance procedure was too high to assure proper operation of the cooling water system.
l Response As discussed in the report, Consumers Power Company agreed to re analyze the ,
suction pressure acceptance criteria for the surveillance procedure. This action is complete and a copy of the revised acceptanca criteria is attached to this letter.
Unresolved item 155/92019-06C The team was concerned that suction screen cleaning was being postponed after suction pressures indicated potential plugging. Trending data showed that
=intenance orders were written when suction pressure fell outside the i pected range, but on occasion the work completion was not timely.
aesponse The surveillance procedure has been revised (copy-attached) to require high priority to maintenance orders for suction screen replacement, in addition, values are being assigned to minimum discharge pressure and maximum suction '
pressure to identify screen clogging and maintenance order generation. These values are being put in the surveillance procedure.
Open Item 155/22-019 07 During the ins)ection, wiring discrepancies between the electrical design drawings and tie as-build configuration of the EOG control panels.
Response As stated in the inspection report, the observed discreaancies did not affect-the operability of the circuits. Drawing changes have )een initiated, .
Walkdowns are ) art of the modification process and should identify any other
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deficiencies witch will_be handled on a case-by-case basis. Current
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surveillance testing insures equipment operability.
9%tn.lt9m 155]E klR-98 I
- The team was concerned that control of conduit and cable tray fill l requirements was deficient and that licensee walkdowns identified some
! overfilled conduits that did not have a thermal analysis.
Response-The electrical design specification (E 8) will be revised to incorporate-
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conduit and cable tray sizing / fill instructions. The raceway schedule has i l been reviewed to identify which conduits / cable trays exceed these guidelines and evaluations are_in progress. All safety-related overfills have been resolved and the remainder will be reviewed on a case by case basis.- The target completion date for the effort is December 1993, which allows time for walkdowns in the 1993 Refueling Outage. ,
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Open item E 5L91Q)J-09 The team was concerned with the availability of design infornation to insure that installed fuses were properly selected and sized. Although an operability concern did not exist because the circuits have functioned when required, program improvements were warranted.
Response Although design information is not readily available for all fuses at BRP, it has been our philosophy to do only "like for like" replacements to insure configuration control. As discussed in the inspection Report, BRP personnel identified this concern just prior to the EDSF1 from our review of inspection results at other facilities and is in the process of establishing a arogram.
The program has a target completion date of December 1993, since wal(downs are required during the 1933 Refueling Outage.
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DAtg FUEL OIL REPORT DATE
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- , TIMd* _ TO BE RUN ON 85' SH!rt DAILY TIME _
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_ ,HEATly0!LER FUEL OIL LEVEL AND WATER _USACES _
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CAUCE ORDER O!L WHEN WE CAN RECE!VE 7,500 CALLONS. h SPECIFIC CRAVITY s '
PREVIOUS LEVEL Heating oil must be .82$ to .887. ;
Premium diesel oil must be .802 to .876.
PRESENT LEVEL Detain Water ** Fuel 011 ** Feed Water (FS-9502) (FI-9562p (FI.9563)
PREVIOUS CAL. Present Present Present PRESENT CAL. Previous Previous Previous DA!LY USE Daily Wkly Use Wkly Use Use _
t ErF = ritMten.calhnt E 6.44 ErP g .
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Fuel 011 Cs!1one
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_ _ _ EMERCENCY DIESEL FIRE PUMP OIL (T-$3) -
CAUCE DIPSTICK _
CQ12{Kl(18 USE PRIMIUM OIL ONLY. FULL TANK IS 44'. EMERCENCY DIESEL FIRE PUMP PREVIOUS LEVEL WILL BE DIPSTICKED THE FIRST FRIDAY OF EVERY MONTM. REFUEL AT OR ABOVE PRESENT LEVEL 26* CONTACT STOCKROOH WHEN
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_ _ 14CElYlM,91L SHIPMEt[Tj.
EMERCENCY DIESEL CENERATOR O!L (T-83)
CAUCE DIPSTICK _
00MMIJffs _
USB PREMIUM OIL ONLY. FULL TANK PREVIOUS LEVEL IS 72* (6.0 FT). RMERCENCY CINERATOR TANK WILL DE DIPSTICKED
- THE FIRST FRIDAY OF EVERY MONTH.
RErvEL AT on AsoVs $0* (4.2 FT).*
PRESENT LEVEL M4 CONTACT STOCKROOM WHEN RECEIVINC 0.!L 311IfMENIj.
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STANDBY DIESEL CENERATOR O!L CAUCE COMMENT ORDER OIL AT OR ABOVE 34' (approx. 450 Cal.) USE PREVIOUS LEVEL PREMIUM O!L ONLY. FULL TANK IS 40". CONTACT STOCKROOH WHEN RICE!VING OIL SHIPMENTS.-
PRESENT LEVEL
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WARIHOUSE SECURITY SECURITY BOILER ASD IN OUT PREVIOUS %
..P_ RESENT %
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- NOTE: An alarm at the high fuel oli annunciator indicates that the tank being filled -
(T-53 or T-83) is full and refueling should be terminated.
- HOTE: Record once por week on Monday.
REVIEWED BY SHIFT SUPERVISOR:
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<
e 0 0 OPERATIONS MEMO 807-92 (REV. 1)
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TO: Shift Supervisors Operators CONSUMERS POWER WJTrubilowicz
\ COMPANY PROM:
September 25, 1992 Internal DATE: Correspondence SUBJECT: DIO ROCK POINT PLANT- i EMERGENCY DIESEL GENERATOR OPERABILITY
' Shift Supervisor Log Quality Review Form CC:
control Room Log QA-05A (2)
Training Department Log DCC 740/22*07*02/L One of the concerns that hLs been raised as a result of the EDSPI deals with the ability of the Emergency Diesel Generator (EDG) to draw cooling water out of the Discharge Bay under low lake level conditions.22, 1992The length of the suction line was measured on September and it was calculated that it becomes uncovered at a lake level of ~577.1 feet above sea level.
Until the losue can be resolved, we need to monitor the actual lake level and set an operability requirement for the EDG based on lake level. This will be accomplished as follows:
On the 'C' Shift each day, take a reading on the lake Icvel instrument located in the Discharge Canal and record it on the Control Room Log Sheet.
If the lake level drops below the 578 foot elevation, the ED3 shall be declared inoperable and the three~ day LdO as specified in Technical Specification 11.3.5.3. A.2 chall apply. ,
This Operations Memo will remain in effect until the issue is resolved or this information is incorporated into the operating procedures.
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T7 28 Revision 17 Page 9 of 18 1 EMERGENCY DIESEL GENERATOR AUTO TEST START Init :Date- l
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s Olpstick Oil Level (between ADD and FULL) !
Water Pump ',uction Vac.(PI 834) t
"flg(12. to 13.5)
Water Pump llead psig (PI 835) *(7 to'12)_
Water Pump Discharge psig (PI 836) *(8 to 13)
(0P) !
1. Acceptance Criteria:
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Water Pump Discharge (PI 836) 2 6.25 psig and Water Pump Suction (PI 834) $ 14' Hg Vac -l Acceptance Criteria Met? Yes No l
If cooling water discharge: *
- pressure is less than 8 psig *
- or suction pressure is greater *
- than or equal to 13.5 inches Hg.. * I,
- it may be an indication that the *
- suction strainer is.beginning- *
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- to plug. Maintenance action ,
- to clean the strainer must be- * -
- given a lllGjf priority to assure **
- the EDG will-operate properly.
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(0P)-
l j. If PI 836 < 8 psig or if PI 834 213.5"'Hg Vac, notiff the Shift Supervisor to' initiate a-Maintenance Order to clean the suction screen.
N/A (0P)
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