|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:consumers Power POWERINli MICHlliAN'S PROliRESS General Offices: 212 West Michigan Avenue, Jackson, Ml 49201 * (517) 788-0550 July 13, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -RESPONSE TO PALISADES SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ADDITIONAL INFORMATION (TAC NO 72622) Consumers Power Company was informed during a telephone conference call on April 18, 1990 that additional information and changes to our March 29, 1990 response were required. |
| | These changes were necessary to enable the NRG staff to complete their review and evaluation of the Palisades Inservice Inspection Program which was originally submitted to the NRG on December 19, 1988. Consumers Power Company's response to the concerns identified during the telephone conference call are detailed in Attachment |
| | : 1. Consumers Power Company agrees that certain components in Class 2 systems should not be exempted per IWC-1220 1974S75 Section XI of the ASME Code. Therefore, it was necessary to revise our March 29, 1990 submittal to porate the comments received during our April 18, 1990 telephone conference. |
| | Changes were required in the Class 2 exam tables, the previous line size exemption was removed from regenerative heat exchanger Class 2 shell welds. Items 2D and 2E from our March 29, 1990 letter have been revised to remove the previous exclusions which had been taken on Emergency Core Cooling subsystems, Containment Spray System and the Class 2 pumps. Items 2H and 2I from our March 29, 1990 have also been revised. OC0790-0790-NL02 A CMS" ENERGY COMPANY As requested by the NRC staff, a copy of this information is being forwarded to Boyd W Brown, Idaho National Engineering Laboratory, P 0 Box 1625, Idaho Falls, Idaho 83415-2209, in order to expedite the review. |
| | l<C(l<) Richard W. Smedley Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector |
| | -Palisades Attachments OC0790-0790-NL02 OC0790-0790-NL02 ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC QUESTIONS ON SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM July 13, 1990 7 Pages NRC CONCERN Regenerative heat exchanger E-56A and E-56B have been excluded from examination requirements based on Section XI, IWC-1220(c). |
| | CPCo RESPONSE 1 The Class 2 portion of the regenerative heat exchanger was previously exempted from examination based on the inlet nozzle line size being less than four inches. During the telecon it was pointed out that this line size exemption was taken in error. Therefore, the Class 2 examination tables are being revised to include circumferential shell welds numbers 01 and 02 on heat exchanger E-56A for examination during the second, third and fourth intervals. |
| | Also, vessel supports S-02 and S-03 on E-56A have been added to the examination schedule during the second, third and fourth intervals. |
| | The nozzle welds are exempted from examination, per Section XI, Category C-B, footnote (2). On vessel E-56B the Section XI, Category C-A welds will not be examined as allowed by footnote (3) of this category. |
| | The vessel supports on E-56B will not be examined as allowed by Section XI, IWF-2510 (b). OC0790-0790-NL02 2 NRC CONCERN Item 2. D., from Consumers Power Company letter to the NRC dated March 29, 1990 applied the pressure temperature exclusion from the 1974 edition, Sununer 1975 addenda of Section XI, paragraph IWC-1220(a) to three subsystems attached to the SIRW Tank. This system is part of an emergency core cooling system and this exclusion should not be applied to these subsystems. |
| | CPCo RESPONSE This exclusion has been removed from these three subsystems and examinations are now scheduled for the welds and hangers for all three lines. Table Al has also been revised to reflect this change (Attachment 2). The three affected lines are: ESS-6-SIS-CRH Line is found on page 451 in the exam tables. ESS-6-SDC-REl Line is found on page 435 in the exam tables. ESS-6-SRT-REl Line is found on page 461 in the exam tables. On line ESS-6-SIS-CRH weld numbers 214, 215, 225, 226, 237, 238, 242 and 243 have been scheduled for examination during the second, third and fourth intervals. |
| | Additionally, all pipe hangers on this line are now scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-6-SDC-REl weld numbers 210, and 204 have been scheduled for ination during the second, third and fourth interval Additionally, pipe hanger 207 PR is also scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-6-SRT-REl weld number 201 has been scheduled for examination during the second, third and fourth intervals. |
| | OC0790-0790-NL02 3 NRC CONCERN Item 2. E., from Consumers Power Company letter to the NRC dated March 29, 1990 determined that the Containment Spray System did not perform an emergency core cooling function and was not required to be tested as allowed by Section XI, 1974 edition Summer 1975 addenda, paragraph IWC-1220(b). |
| | 10CFRS0.55a(b) |
| | (2) (iv) requires that pipe welds in CHR systems be examined. |
| | This federal regulation takes precedence over the Section XI paragraph. |
| | Verify that the ISI Program will be revised to include a representative sample of welds in the Containment Spray System. CPCo RESPONSE This exclusion has now been removed from this system and an appropriate sampling of welds and pipe restraints have been added to the examination tables. The affected lines are: ESS-14-CSS-lPA ESS-14-CSS-lPB ESS-14-CSS-lPC ESS-10-CSS-lPA ESS-10-CSS-lPB ESS-10-CSS-lPC ESS-8-CSS-lPA ESS-8-CSS-lPB |
| | |
| | ESS-8-CSS-lPC ESS-6-CSS-lPA ESS-6-CSS-lPB ESS-10-CSS-1P3 ESS-8-CSS-TCA ESS-10-CSS-SLA ESS-10-CSS-SLB ESS-8-CSS-SLA ESS-8-CSS-SLB ESS-8-CSS-SLA ESS-8-CSS-SLB ESS-6-CSS-SLA ESS-6-CSS-SLB Line is found on page 325 in the exam tables. Line is found on page 330 in the exam tables. Line is found on page 336 in the exam tables. Line is found on page 326 in the exam tables. Line is found on page 333 in the exam tables. Line is found on page 339 in the exam tables. Line is found on page 327 in the exam tables. Line is found on page 334 in the exam tables. Line is found on page 340 in the exam tables. Line is found on page 327 in the exam tables. Line is found on page 334 in the exam tables. Line is found on page 426 in the exam tables. Line is found on page 432 in the exam tables. Line is found on page 409 in the exam tables. Line is found on page 417 in the exam tables. Line is found on page 410 in the exam tables. Line is found on page 418 in the exam tables. Line is found on page 412 in the exam tables. Line is found on page 421 in the exam tables. Line is found on page 412 in the exam tables. Line is found on page 420 in the exam tables. There are 237 category C-F welds contained within these lines and 31 (13%) of these welds have been scheduled for examination during the second, third and fourth intervals. |
| | The following is a line by line summary for each line with scheduled weld and pipe hanger examinations. |
| | OC0790-0790-NL02 4 On line ESS-14-CSS-SLA weld numbers 201, 201LI, 201LO, 202, 202LW, 203, 203LI, 203LO and 208 have been scheduled for examination during the second, third and fourth intervals. |
| | Additionally, all pipe hangers on this line are now scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-10-CSS-lPA weld numbers 209 and 227 have been scheduled for ination during the second, third and fourth intervals. |
| | On line ESS-10-CSS-lPB both pipe*hangers have been scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-8-CSS-lPA weld numbers 211, 212, 212PL-1, 212PL-2, 212PL-3, 212PL-4, 213, 214 and 215 have been scheduled for examination during the second , third and fourth intervals. |
| | Additionally, all pipe hangers on this line are now scheduled for examination. |
| | On line ESS-6-CSS-lPA weld number 211 has been scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-10-CSS-1P3 weld number 201 has been scheduled for examination during the second, third and fourth intervals. |
| | Additionally, both pipe hangers on this line are now scheduled for examination. |
| | On line ESS-8-CSS-TCA weld number 201 has been scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-10-CSS-SLA weld numbers 201 and 210 have been scheduled for examination during the second, third and fourth intervals. |
| | Additionally, pipe support 207PS and pipe hanger 207PR are now scheduled for examination. |
| | On line ESS-8-CSS-SLA (Page 410) weld numbers 211, 213 and 219 have been scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-8-CSS-SLA (Page 412) weld numbers 223, 226, 228, 229, 234 and 235 have been scheduled for examination during the second, third and fourth intervals. |
| | Additionally, all pipe hangers on this line are now scheduled for examination during the second, third and fourth intervals. |
| | On line ESS-6-CSS-SLA weld number 221 and pipe hanger 221PR have been scheduled for examination during the second, third and fourth interval. |
| | OC0790-0790-NL02 NRC CONCERN Page 40, from Consumers Power Company letter to the NRC dated March 29, 1990 applied the pressure and temperature exclusion and the controlled chemistry exemptions from the 1974 edition, Summer 1975 addenda of Section XI, paragraphs IWC-1220(a) and (c) to the Containment Spray Pumps, Charging 5 Pumps, Concentrated Boric Acid Pumps, High Pressure Safety Injection Pumps and Low Pressure Safety Injection Pumps. These systems are part of the emergency core cooling and containment heat removal systems and should not have these exemptions applied to these pumps. CPCo RESPONSE Page 40 from our March 29, 1990 letter, (Attachment |
| | : 2) has been revised to eliminate these exclusions. |
| | Examinations are now scheduled f*or these pumps. OC0790-0790-NL02 . j 6 NRC CONCERN Consumers Power Company response to Item 2.H. in CPCo letter dated March 29, 1990 needs to be revised to indicate that the intent of USNRC Regulatory Guide 1.150 will be met when examining reactor pressure vessel welds. CPCo RESPONSE Consumers Power Company has adopted the position on USNRC Regulatory Guide 1.150 that has been developed by Westinghouse Electric Corporation. |
| | This position is incorporated in the Westinghouse procedure, CPAL-ISI-154, Revision 2, used for the performance of this testing. This procedure meets the intent of all the requirements specified in USNRC Regulatory Guide 1.150 for testing reactor vessel welds. Westinghouse will be performing our reactor vessel examinations during this ten year interval. |
| | OC0790-0790-NL02 7 NRC CONCERN Regarding item 2.I. from March 29, 1990 letter from Consumers Power Company to the NRC, NRC requires that previous response be revised to include a performance demonstration of ultrasonic testing instrumentation and procedures to prove that this equipment and procedures are capable of detecting outside diameter surface connected defects in the circumferential orientation in a laboratory test block. CPCo RESPONSE These examinations are scheduled to be performed during the last refueling outage of the second interval. |
| | Prior to the performance of these examinations CPCo will demonstrate on a laboratory test block which contains crack type defects that the test equipment and procedures utilized are capable of detecting outside diameter surface connected defects in the circumferential direction. |
| | OC0790-0790-NL02 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC QUESTIONS ON SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM July 13, 1990 2 Pages OC0790-0790-:-NL02 Component CCS-10-CSH-lPl ccs-10-CSH-1P4 SFP-8-CPL-DLl SFP-6-CPL-SLl SFP-6-SRT-RLl SFP-6-SRT-SLl SFP-6-FPP-HXB RWS-6-CWR-SL4 TABLE Al PRESSURE TEMPERATURE EXEMPTIONS IWC-1220(a), 74S75 Function Pressure Component Cooling Line Component Cooling Line Reactor Cavity Drain Line Reactor Cavity Drain Line Spent Fuel Pool Recirc Line Spent Fuel Pool Reci re Line Spent Fuel Pool Recirc Line Clean Waste Relief Line 150 150 125 125 125 125 125 so psi psi psi psi psi psi psi psi 21 Design Temperature 140°F 140°F 150°F 150°F 150°F 150°F 150°F 180°F BASIS: IWC-1220(a) |
| | *allows exemptions from the NDT examination requirements of IWC-2520 where both the design pressure and temperature are equal to or less than 275 psig and 200°F, respectively. |
| | Design data was taken from manufacturers' drawings or Bechtel Specifications M-250 and M-259. 10 CFR 50.SSa requires that piping systems which perform ECCS, Residual Heat Removal (RHR), and Containment Heat Removal (CHR) function shall be inspected per IWC-1220, 74S75, Section XI. 10 CFR 50.55a permits the utilization of IWC-1220, 74S75, Section XI for other Class 2 piping systems. IWC-1220(a), 74S75 has been applied to all Class 2 piping. Revision 2 OC0790-0790-NL02 7/9/90 Functional Identification Containment Spray Pump Charging Pumps Concentrated Boric Acid Pump High-Pressure Injection Pump Low-Pressure Injection Pump Concentrated Boric Acid Tank Long-Term Cooling Safety Injection Revision 2 OC0790-0790-NL02 7 /9/90 Line Identifi-cation -ESS-LTC ESS-LTC ESS-SlS Loop Pipe Identifi-Sizes(s) cation a. P-54A b. P-54B c. P-54C a. P-55A b. P-55B c. P-55C a. P-56A b. P-56B a. P-66A b. P-66B a. P-67A b. P-67B a. T-53A b. T-53B 6 II a. IA b. 1B 12" a. lAl b. lBl c. 2Al d. 2Bl 40 Isometric Weld Multiple Number(s) |
| | Number(s) |
| | Loop Number Comment B-29, 130 ML-19 B-31, 130 ML-19 B-31, 130 ML-19 B-87, 131 ML-20 B-56, 131 ML-29 B-86, 131 ML-20 B-55, 132 ML-21 B-55, 132 ML-21 B-36, 133 ML-22 B-50, 133 ML-22 B-29, 134 ML-23 B-35, 134 ML-23 B-29, 3 ML-23 Exempt per IWC-1220(c), B-55, 3 ML-24 74S75 B-52A 201-228 ML-24A 1981 Mod e B-60A 201-212 ML-24A A-7 1-8 ML-25 Class designation A-8 1-12 ML-25 changed from Class 1 A-9 1-11 ML-25 to Class 2 in 1983 A-10 1-11 ML-25}} |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 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 ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 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 ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants. ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 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 ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants. ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided IR 05000255/19970181999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 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 ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML18066A4051999-02-10010 February 1999 Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46) ML18066A3921999-01-29029 January 1999 Forwards Licensee Interpretation of TS Requirements for Performance of SRs as Applied to Instrumentation Channel Calibr.Ltr Established No New Commitments ML18066A3891999-01-28028 January 1999 Submits Response to Concern Expressed in Insp Rept 50-255/98-06 Re Whether Palisades ISI Program Was Being Conducted IAW Applicable Requirements 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML18057A4811990-09-17017 September 1990 Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant ML18057A4551990-09-0606 September 1990 Forwards Proprietary Info Re Dept of Labor Decision on Discharge of Former Employee of Util,Per NRC 900809 Request. No 10CFR50.7 Violation Occurred Since Job Performance Was Reason for Discharge.Encl Withheld (Ref 10CFR2.790(a)(6)) ML18057A4521990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated IR 05000255/19900101990-09-0404 September 1990 Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated ML18057A4371990-08-31031 August 1990 Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment ML18057A4381990-08-31031 August 1990 Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place ML20059E0001990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 ML18057A4201990-08-24024 August 1990 Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting ML18057A4021990-08-22022 August 1990 Forwards Missing Pages from Decommissioning Funding Rept, Consisting of Pages 25 & 26 of Attachment a to Exhibit E ML18057A4241990-08-21021 August 1990 Forwards Application for Amend to License DPR-20,changing Tech Spec 4.5.1 Re Statement on Integrated Leak Rate Test ML18057A4071990-08-21021 August 1990 Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable ML18057A4121990-08-21021 August 1990 Forwards Application for Amend to License DPR-20,changing Tech Specs to Revise Wording for Reactor Protective Sys Trip Setting Limits for Steam Generator Low Water Level ML18057A4181990-08-21021 August 1990 Forwards Description of Changes Being Made to Plant Site Emergency Plan & Emergency Plan Changes.Change Allows Reduction in Shift Staffing During Cold Shutdown for Stated Staff ML18057A3911990-08-17017 August 1990 Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program. ML18057A3851990-08-17017 August 1990 Forwards Addl Info in Support of NRC Development of SER for full-term OL for Plant,Including Date of SER Providing Provisional OL to Plant & Summary of Valid Exemptions from 10CFR Regulations,Per Telcon ML18057A3841990-08-17017 August 1990 Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr ML18057A3821990-08-14014 August 1990 Requests That Bechtel-KWU Rept 128901/MJS, Full Flow Testing of Motor-Operated Valve MO-1042A, Be Withheld (Ref 10CFR2.790(b)(1)) ML18057A3721990-08-0808 August 1990 Forwards Addl Info Re Util Request for Exemption from Separation Criteria of 10CFR50,App R,Section III.G.2 Re Containment Air Room ML20055J1421990-07-26026 July 1990 Responds to Commitment Oversight Issue Resulting from Insp Rept 50-255/90-08.Commitment Mgt Seminar Training Will Be Complete Prior to 901001 ML18057A3561990-07-26026 July 1990 Forwards Certification of Financial Assurance for Decommissioning ML18057A3411990-07-18018 July 1990 Forwards Revised Proposed Tech Spec Page 6-3,now Designated as Page 6-1b,adding Section 6.3.4,now Designated as Section 6.3.5 to Remove Organization Charts,Per Generic Ltr 88-06 ML18057A3381990-07-16016 July 1990 Advises That Util Does Not Foresee Need to Rely on Section V.C of App G to Remain in Compliance W/Upper Shelf Energy (Use) Requirements Re Use of Matl in Reactor Beltline ML18057A3281990-07-13013 July 1990 Responds to Request for Addl Info Re Second 10-yr Interval Insp Program,Per 900418 Telcon.Util 900329 Response Revised to Reflect That Certain Components in Class 2 Sys Should Not Be Exempted,Per IWC-1220 of 1974 ASME Code Section XI ML18057A3191990-07-0909 July 1990 Forwards Performance Indicator Trend Graphs for Jan 1989 - May 1990 ML18057A3201990-07-0606 July 1990 Discusses Reassessment of Control Room Temp Following Station Blackout Event.Results of Analysis Indicate That Control Room Temp Will Remain Below 112 F for 4 H After Onset of Blackout ML18057A3171990-07-0303 July 1990 Provides Summary of Upgrades Made to Plant Electrical Distribution Sys,Per 870714 Loss of Offsite Power Event When Inadvertent Actuation of Water Deluge Spray Sys for 1-2 Startup Transformer Resulted in Bus to Ground Fault ML20058K3771990-07-0202 July 1990 Forwards Rev 26 to Security Plan.Rev Withheld (Ref 10CFR73.21(c)) ML18057A3111990-06-25025 June 1990 Forwards Endorsements 116 & 117 to Nelia Policy NF-179 & Endorsements 102 & 103 to Maelu Policy MF-50 ML18057A3101990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements on Corrective Actions. ML18057A3031990-06-22022 June 1990 Provides Addl Info Re Environ Qualification of Instrument Circuit Associated W/Steam Generator Pressure Channel PT-0752D,per Insp Rept 50-255/90-05.Circuits Spliced Directly to Pigtail from Electrical Penetration Connector ML18057A3001990-06-21021 June 1990 Concurs W/Nrc Change in Terminology & Submits Revised Proposed Section 4.14 of Tech Specs ML18057A2771990-06-15015 June 1990 Forwards Corrected NRC Form 474 Re Simulation Facility Certification,Indicating Exceptions to Ansi/Ans 3.5 ML18057A2901990-06-13013 June 1990 Forwards Application for Amend to License DPR-20,revising Tech Spec 3.3.1.b Re Safety Injection Tank Min Level ML18057A2941990-06-12012 June 1990 Advises That Submittal of Second Interval Inservice Insp Program Delayed from 900615 to 900715,per 900418 Telcon ML18057A2711990-06-11011 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i in Order to Maintain Plant in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Request Based on 900608 Failure of Heater Transformer 15 ML18057A2641990-06-11011 June 1990 Provides Response to NRC Requalification Exam Rept Dtd 900410 on NRC Concerns Re Facility & Training Ctr Staffing. Adequate Staffing Will Be Maintained to Ensure Operator Requalification Program Successful ML18057A2591990-06-11011 June 1990 Forwards Palisades Simulator Certification Submittal. ML18057A2631990-06-10010 June 1990 Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i to Enable Plant to Be Maintained in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Waiver Requested for 900611-18 ML18057A2571990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-255/90-12.Corrective Actions:Continuing Training Program Will Be Developed for Supervisors That Will Discuss Fire Protection Program Implementation Topics ML20043D0601990-06-0404 June 1990 Forwards Rev 25 to Security Plan,Including Changes to Security Plan Drawings to Clarify Protected Area Boundary within Plant Security Bldg & Vital Area Boundaries in Other Specific Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML18057A2581990-06-0101 June 1990 Forwards Revised Response to Violations Noted in Insp Rept 50-255/89-26.Concurs That Tests Performed Using Instrumented Insp Technique During 1988 Refueling Outage Considered Invalid ML18057A2561990-05-31031 May 1990 Advises That No NPDES Notifications Required Nor Any Repts of Oil or Salt Occurred During Nov 1989 - Apr 1990 ML18057A2541990-05-30030 May 1990 Forwards Response to Technical Evaluation Rept EGG-NTA-8333 Which Evaluated Plant Compliance w/NUREG-0737,Item II.D.1 & Requested Addl Info Re New PORVs & Block Valves No Later than Jan 1990 ML18057A2511990-05-30030 May 1990 Forwards Final Response to Concerns Re Porv/Block Valve Mod, Per 900308 Meeting.Bechtel Technical Rept Withheld ML18057A2501990-05-29029 May 1990 Forwards Investigation Rept Re Unsatisfactory Performance Testing of Fitness for Duty Program Blind Performance Test Samples ML18057A2411990-05-24024 May 1990 Forwards Revised Application to Amend License DPR-20, Consisting of Revised Attachments 1 & 5 to 890227 Amend Request,Reflecting Transfer of Plant Ownership ML18057A2311990-05-17017 May 1990 Forwards Analysis of Reactor Pressure Vessel Fast Neutron Fluence & PTS Ref Temps for Palisades Nuclear Plant. Rept Concludes That PTS Screening Criteria Will Be Exceeded at Axial Welds in Sept 2001 as Opposed to Mar 2002 ML18054B5861990-05-0707 May 1990 Forwards Monthly Trend Graph Rept for Jan 1989 - Mar 1990 Covering Safety Status Performance Indicators for HPSI, Auxiliary Feedwater,Emergency Ac Power,Lpsi,Containment Spray & Svc Water Sys ML18054B5801990-04-30030 April 1990 Responds to Request for Addl Info on Proposed Administrative Changes to Tech Spec Section 3.0.4,per Generic Ltr 87-09. Licensee Will Implement Program to Assure Appropriate Level of Mgt Approval Required When Operating Conditions Changed ML18054B5741990-04-25025 April 1990 Requests That Correspondence Re 890227 Application for Amend to License DPR-20 to Permit Transfer of Ownership of Plant Be Sent to Listed Address 1990-09-06
[Table view] |
Text
consumers Power POWERINli MICHlliAN'S PROliRESS General Offices: 212 West Michigan Avenue, Jackson, Ml 49201 * (517) 788-0550 July 13, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -RESPONSE TO PALISADES SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ADDITIONAL INFORMATION (TAC NO 72622) Consumers Power Company was informed during a telephone conference call on April 18, 1990 that additional information and changes to our March 29, 1990 response were required.
These changes were necessary to enable the NRG staff to complete their review and evaluation of the Palisades Inservice Inspection Program which was originally submitted to the NRG on December 19, 1988. Consumers Power Company's response to the concerns identified during the telephone conference call are detailed in Attachment
- 1. Consumers Power Company agrees that certain components in Class 2 systems should not be exempted per IWC-1220 1974S75 Section XI of the ASME Code. Therefore, it was necessary to revise our March 29, 1990 submittal to porate the comments received during our April 18, 1990 telephone conference.
Changes were required in the Class 2 exam tables, the previous line size exemption was removed from regenerative heat exchanger Class 2 shell welds. Items 2D and 2E from our March 29, 1990 letter have been revised to remove the previous exclusions which had been taken on Emergency Core Cooling subsystems, Containment Spray System and the Class 2 pumps. Items 2H and 2I from our March 29, 1990 have also been revised. OC0790-0790-NL02 A CMS" ENERGY COMPANY As requested by the NRC staff, a copy of this information is being forwarded to Boyd W Brown, Idaho National Engineering Laboratory, P 0 Box 1625, Idaho Falls, Idaho 83415-2209, in order to expedite the review.
l<C(l<) Richard W. Smedley Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector
-Palisades Attachments OC0790-0790-NL02 OC0790-0790-NL02 ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC QUESTIONS ON SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM July 13, 1990 7 Pages NRC CONCERN Regenerative heat exchanger E-56A and E-56B have been excluded from examination requirements based on Section XI, IWC-1220(c).
CPCo RESPONSE 1 The Class 2 portion of the regenerative heat exchanger was previously exempted from examination based on the inlet nozzle line size being less than four inches. During the telecon it was pointed out that this line size exemption was taken in error. Therefore, the Class 2 examination tables are being revised to include circumferential shell welds numbers 01 and 02 on heat exchanger E-56A for examination during the second, third and fourth intervals.
Also, vessel supports S-02 and S-03 on E-56A have been added to the examination schedule during the second, third and fourth intervals.
The nozzle welds are exempted from examination, per Section XI, Category C-B, footnote (2). On vessel E-56B the Section XI, Category C-A welds will not be examined as allowed by footnote (3) of this category.
The vessel supports on E-56B will not be examined as allowed by Section XI, IWF-2510 (b). OC0790-0790-NL02 2 NRC CONCERN Item 2. D., from Consumers Power Company letter to the NRC dated March 29, 1990 applied the pressure temperature exclusion from the 1974 edition, Sununer 1975 addenda of Section XI, paragraph IWC-1220(a) to three subsystems attached to the SIRW Tank. This system is part of an emergency core cooling system and this exclusion should not be applied to these subsystems.
CPCo RESPONSE This exclusion has been removed from these three subsystems and examinations are now scheduled for the welds and hangers for all three lines. Table Al has also been revised to reflect this change (Attachment 2). The three affected lines are: ESS-6-SIS-CRH Line is found on page 451 in the exam tables. ESS-6-SDC-REl Line is found on page 435 in the exam tables. ESS-6-SRT-REl Line is found on page 461 in the exam tables. On line ESS-6-SIS-CRH weld numbers 214, 215, 225, 226, 237, 238, 242 and 243 have been scheduled for examination during the second, third and fourth intervals.
Additionally, all pipe hangers on this line are now scheduled for examination during the second, third and fourth intervals.
On line ESS-6-SDC-REl weld numbers 210, and 204 have been scheduled for ination during the second, third and fourth interval Additionally, pipe hanger 207 PR is also scheduled for examination during the second, third and fourth intervals.
On line ESS-6-SRT-REl weld number 201 has been scheduled for examination during the second, third and fourth intervals.
OC0790-0790-NL02 3 NRC CONCERN Item 2. E., from Consumers Power Company letter to the NRC dated March 29, 1990 determined that the Containment Spray System did not perform an emergency core cooling function and was not required to be tested as allowed by Section XI, 1974 edition Summer 1975 addenda, paragraph IWC-1220(b).
10CFRS0.55a(b)
(2) (iv) requires that pipe welds in CHR systems be examined.
This federal regulation takes precedence over the Section XI paragraph.
Verify that the ISI Program will be revised to include a representative sample of welds in the Containment Spray System. CPCo RESPONSE This exclusion has now been removed from this system and an appropriate sampling of welds and pipe restraints have been added to the examination tables. The affected lines are: ESS-14-CSS-lPA ESS-14-CSS-lPB ESS-14-CSS-lPC ESS-10-CSS-lPA ESS-10-CSS-lPB ESS-10-CSS-lPC ESS-8-CSS-lPA ESS-8-CSS-lPB
ESS-8-CSS-lPC ESS-6-CSS-lPA ESS-6-CSS-lPB ESS-10-CSS-1P3 ESS-8-CSS-TCA ESS-10-CSS-SLA ESS-10-CSS-SLB ESS-8-CSS-SLA ESS-8-CSS-SLB ESS-8-CSS-SLA ESS-8-CSS-SLB ESS-6-CSS-SLA ESS-6-CSS-SLB Line is found on page 325 in the exam tables. Line is found on page 330 in the exam tables. Line is found on page 336 in the exam tables. Line is found on page 326 in the exam tables. Line is found on page 333 in the exam tables. Line is found on page 339 in the exam tables. Line is found on page 327 in the exam tables. Line is found on page 334 in the exam tables. Line is found on page 340 in the exam tables. Line is found on page 327 in the exam tables. Line is found on page 334 in the exam tables. Line is found on page 426 in the exam tables. Line is found on page 432 in the exam tables. Line is found on page 409 in the exam tables. Line is found on page 417 in the exam tables. Line is found on page 410 in the exam tables. Line is found on page 418 in the exam tables. Line is found on page 412 in the exam tables. Line is found on page 421 in the exam tables. Line is found on page 412 in the exam tables. Line is found on page 420 in the exam tables. There are 237 category C-F welds contained within these lines and 31 (13%) of these welds have been scheduled for examination during the second, third and fourth intervals.
The following is a line by line summary for each line with scheduled weld and pipe hanger examinations.
OC0790-0790-NL02 4 On line ESS-14-CSS-SLA weld numbers 201, 201LI, 201LO, 202, 202LW, 203, 203LI, 203LO and 208 have been scheduled for examination during the second, third and fourth intervals.
Additionally, all pipe hangers on this line are now scheduled for examination during the second, third and fourth intervals.
On line ESS-10-CSS-lPA weld numbers 209 and 227 have been scheduled for ination during the second, third and fourth intervals.
On line ESS-10-CSS-lPB both pipe*hangers have been scheduled for examination during the second, third and fourth intervals.
On line ESS-8-CSS-lPA weld numbers 211, 212, 212PL-1, 212PL-2, 212PL-3, 212PL-4, 213, 214 and 215 have been scheduled for examination during the second , third and fourth intervals.
Additionally, all pipe hangers on this line are now scheduled for examination.
On line ESS-6-CSS-lPA weld number 211 has been scheduled for examination during the second, third and fourth intervals.
On line ESS-10-CSS-1P3 weld number 201 has been scheduled for examination during the second, third and fourth intervals.
Additionally, both pipe hangers on this line are now scheduled for examination.
On line ESS-8-CSS-TCA weld number 201 has been scheduled for examination during the second, third and fourth intervals.
On line ESS-10-CSS-SLA weld numbers 201 and 210 have been scheduled for examination during the second, third and fourth intervals.
Additionally, pipe support 207PS and pipe hanger 207PR are now scheduled for examination.
On line ESS-8-CSS-SLA (Page 410) weld numbers 211, 213 and 219 have been scheduled for examination during the second, third and fourth intervals.
On line ESS-8-CSS-SLA (Page 412) weld numbers 223, 226, 228, 229, 234 and 235 have been scheduled for examination during the second, third and fourth intervals.
Additionally, all pipe hangers on this line are now scheduled for examination during the second, third and fourth intervals.
On line ESS-6-CSS-SLA weld number 221 and pipe hanger 221PR have been scheduled for examination during the second, third and fourth interval.
OC0790-0790-NL02 NRC CONCERN Page 40, from Consumers Power Company letter to the NRC dated March 29, 1990 applied the pressure and temperature exclusion and the controlled chemistry exemptions from the 1974 edition, Summer 1975 addenda of Section XI, paragraphs IWC-1220(a) and (c) to the Containment Spray Pumps, Charging 5 Pumps, Concentrated Boric Acid Pumps, High Pressure Safety Injection Pumps and Low Pressure Safety Injection Pumps. These systems are part of the emergency core cooling and containment heat removal systems and should not have these exemptions applied to these pumps. CPCo RESPONSE Page 40 from our March 29, 1990 letter, (Attachment
- 2) has been revised to eliminate these exclusions.
Examinations are now scheduled f*or these pumps. OC0790-0790-NL02 . j 6 NRC CONCERN Consumers Power Company response to Item 2.H. in CPCo letter dated March 29, 1990 needs to be revised to indicate that the intent of USNRC Regulatory Guide 1.150 will be met when examining reactor pressure vessel welds. CPCo RESPONSE Consumers Power Company has adopted the position on USNRC Regulatory Guide 1.150 that has been developed by Westinghouse Electric Corporation.
This position is incorporated in the Westinghouse procedure, CPAL-ISI-154, Revision 2, used for the performance of this testing. This procedure meets the intent of all the requirements specified in USNRC Regulatory Guide 1.150 for testing reactor vessel welds. Westinghouse will be performing our reactor vessel examinations during this ten year interval.
OC0790-0790-NL02 7 NRC CONCERN Regarding item 2.I. from March 29, 1990 letter from Consumers Power Company to the NRC, NRC requires that previous response be revised to include a performance demonstration of ultrasonic testing instrumentation and procedures to prove that this equipment and procedures are capable of detecting outside diameter surface connected defects in the circumferential orientation in a laboratory test block. CPCo RESPONSE These examinations are scheduled to be performed during the last refueling outage of the second interval.
Prior to the performance of these examinations CPCo will demonstrate on a laboratory test block which contains crack type defects that the test equipment and procedures utilized are capable of detecting outside diameter surface connected defects in the circumferential direction.
OC0790-0790-NL02 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC QUESTIONS ON SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM July 13, 1990 2 Pages OC0790-0790-:-NL02 Component CCS-10-CSH-lPl ccs-10-CSH-1P4 SFP-8-CPL-DLl SFP-6-CPL-SLl SFP-6-SRT-RLl SFP-6-SRT-SLl SFP-6-FPP-HXB RWS-6-CWR-SL4 TABLE Al PRESSURE TEMPERATURE EXEMPTIONS IWC-1220(a), 74S75 Function Pressure Component Cooling Line Component Cooling Line Reactor Cavity Drain Line Reactor Cavity Drain Line Spent Fuel Pool Recirc Line Spent Fuel Pool Reci re Line Spent Fuel Pool Recirc Line Clean Waste Relief Line 150 150 125 125 125 125 125 so psi psi psi psi psi psi psi psi 21 Design Temperature 140°F 140°F 150°F 150°F 150°F 150°F 150°F 180°F BASIS: IWC-1220(a)
- allows exemptions from the NDT examination requirements of IWC-2520 where both the design pressure and temperature are equal to or less than 275 psig and 200°F, respectively.
Design data was taken from manufacturers' drawings or Bechtel Specifications M-250 and M-259. 10 CFR 50.SSa requires that piping systems which perform ECCS, Residual Heat Removal (RHR), and Containment Heat Removal (CHR) function shall be inspected per IWC-1220, 74S75,Section XI. 10 CFR 50.55a permits the utilization of IWC-1220, 74S75,Section XI for other Class 2 piping systems. IWC-1220(a), 74S75 has been applied to all Class 2 piping. Revision 2 OC0790-0790-NL02 7/9/90 Functional Identification Containment Spray Pump Charging Pumps Concentrated Boric Acid Pump High-Pressure Injection Pump Low-Pressure Injection Pump Concentrated Boric Acid Tank Long-Term Cooling Safety Injection Revision 2 OC0790-0790-NL02 7 /9/90 Line Identifi-cation -ESS-LTC ESS-LTC ESS-SlS Loop Pipe Identifi-Sizes(s) cation a. P-54A b. P-54B c. P-54C a. P-55A b. P-55B c. P-55C a. P-56A b. P-56B a. P-66A b. P-66B a. P-67A b. P-67B a. T-53A b. T-53B 6 II a. IA b. 1B 12" a. lAl b. lBl c. 2Al d. 2Bl 40 Isometric Weld Multiple Number(s)
Number(s)
Loop Number Comment B-29, 130 ML-19 B-31, 130 ML-19 B-31, 130 ML-19 B-87, 131 ML-20 B-56, 131 ML-29 B-86, 131 ML-20 B-55, 132 ML-21 B-55, 132 ML-21 B-36, 133 ML-22 B-50, 133 ML-22 B-29, 134 ML-23 B-35, 134 ML-23 B-29, 3 ML-23 Exempt per IWC-1220(c), B-55, 3 ML-24 74S75 B-52A 201-228 ML-24A 1981 Mod e B-60A 201-212 ML-24A A-7 1-8 ML-25 Class designation A-8 1-12 ML-25 changed from Class 1 A-9 1-11 ML-25 to Class 2 in 1983 A-10 1-11 ML-25