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| | issue date = 08/15/1983 | | | issue date = 08/15/1983 |
| | title = Requests Extension of One Operating Cycle Beyond Present Commitment of 1985 Refueling Outage to Make Mods Per SEP Topic XV-2, Spectrum of Steam Piping Failures Inside & Outside Containment (Pwr). | | | title = Requests Extension of One Operating Cycle Beyond Present Commitment of 1985 Refueling Outage to Make Mods Per SEP Topic XV-2, Spectrum of Steam Piping Failures Inside & Outside Containment (Pwr). |
| | author name = TONER K A | | | author name = Toner K |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = CRUTCHFIELD D | | | addressee name = Crutchfield D |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000255 | | | docket = 05000255 |
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| {{#Wiki_filter:( **' consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 August 15, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -SEP TOPIC XV-2 "SPECTRUM OF STEAM PIPING FAILURES INSIDE AND OUTSIDE CONTAINMENT (PWR)" -REQUEST FOR TIME EXTENSION TO RESOLVE CONCERN OF TWO STEAM GENERATOR BLOWDOWNS INSIDE CONTAINMENT During a review of SEP Topic "Spectrum of Steam Piping Failures Inside and Outside Containment (PWR)," the NRC Staff became concerned that removal of core decay heat would become unreliable in the event of a main steam line break (MSLB) inside containment and a concurrent failure to close of the main steam isolation valve (MSIV) in the intact main steam (MS) line. As mented in NUREG-0820 "Integrated Plant Safety Assessment, Palisades Plant" dated October 1982, the NRC indicated that such an event would result in unreliable decay heat removal due to the blowdown of both steam generators. | | {{#Wiki_filter:( |
| In response to the Staff's concern, Consumers Power Company committed to performing appropriate modifications to make the MSIV/MS configuration failure proof with respect to the blowdown event. The commitment, which is also documented in NUREG-0820, presently requires that the modifications be completed. | | consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 August 15, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC XV-2 "SPECTRUM OF STEAM PIPING FAILURES INSIDE AND OUTSIDE CONTAINMENT (PWR)" - REQUEST FOR TIME EXTENSION TO RESOLVE CONCERN OF TWO STEAM GENERATOR BLOWDOWNS INSIDE CONTAINMENT During a review of SEP Topic xv~2 "Spectrum of Steam Piping Failures Inside and Outside Containment (PWR)," the NRC Staff became concerned that removal of core decay heat would become unreliable in the event of a main steam line break (MSLB) inside containment and a concurrent failure to close of the main steam isolation valve (MSIV) in the intact main steam (MS) line. As docu-mented in NUREG-0820 "Integrated Plant Safety Assessment, Palisades Plant" dated October 1982, the NRC indicated that such an event would result in unreliable decay heat removal due to the blowdown of both steam generators. |
| by the end of the 1985 refueling outage. The purposes of this submittal are to: 1) request a time extension of one operating cycle beyond the present commitment in which to make the modifications and 2) provide the NRC with a basis for such a request. Consumers Power Company is presently on schedule in its efforts to resolve the NRC concern via MSIV replacement by the end of the 1985 outage. We have completed a study which shows the feasibility of replacing the two existing MSIVs with new valves capable of closing under conditions of flow in either direction thereby eliminating the single-failure potential. | | In response to the Staff's concern, Consumers Power Company committed to performing appropriate modifications to make the MSIV/MS configuration single-failure proof with respect to the blowdown event. The commitment, which is also documented in NUREG-0820, presently requires that the modifications be completed. by the end of the 1985 refueling outage. The purposes of this submittal are to: 1) request a time extension of one operating cycle beyond the present commitment in which to make the modifications and 2) provide the NRC with a basis for such a request. |
| In addition, we have begun preparing valve procurement specifications which will be completed and forwarded to prospective manufacturers on or about September 1, 1983. 8308230375 830815 PDR ADOCIA. 05000255 P PDR OC0883-0010A-NL02 DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983 2 Recently, however, we have completed a preliminary probabilistic risk ment (PRA) and cost/benefit (C/B) analysis which reveals the need to: a) further evaluate the safety significance of this event given the reliability of existing systems to prevent inadequate core cooling during and after the event and b) should plant modification prove necessary, determine the most cost-effective modification which resolves the concern. The preliminary PRA and C/B analysis (Enclosure | | Consumers Power Company is presently on schedule in its efforts to resolve the NRC concern via MSIV replacement by the end of the 1985 outage. We have completed a study which shows the feasibility of replacing the two existing MSIVs with new valves capable of closing under conditions of flow in either direction thereby eliminating the single-failure potential. In addition, we have begun preparing valve procurement specifications which will be completed and forwarded to prospective manufacturers on or about September 1, 1983. |
| : 1) shows that the_§requency of a significant release resulting from this event is 9.8 x 10 occurrences/year and that the present cgurse of action (ie, MSIV replacement) results in a C/B ratio of $6.1 x 10 /manrem; an expenditure considerably in excess of the NRC safety goal guideline of $1000/manrem.
| | 8308230375 830815 PDR ADOCIA. 05000255 P PDR OC0883-0010A-NL02 |
| Consumers Power Company met with the Staff in Bethesda on July 26, 1983 to present the results of the preliminary PRA and C/B analysis and to request that the NRC review the results and grant Consumers Power Company a time extension of one operating cycle beyond our current commitment for any sary plant modification. | | |
| This time extension, if approved, would result in: 1) Consumers Power Company finalizing its PRA and C/B analysis to determine more accurately the safety significance of this event as well as the most co'st-effective modification (if modification is proven necessary) and ting such analysis by September 1, 1984 and 2) completing any required modifications by the end of the 1986 refueling outage. During the July 26, 1983 meeting, the Staff indicated that it would consider our request and would attempt to pass judgment on the request by Septem-ber 1, 1983. However, the Staff requested that Consumers Power Company provide in this submittal certain evaluation regarding plant response during and after the event. The NRC indicated that such evaluation would assist the Staff in its consideration of the request. Specifically, the Staff requested that we provide the following: | | DMCrutchfield, Chief 2 Palisades Plant SEP TOPIC XV-2 August 15, 1983 Recently, however, we have completed a preliminary probabilistic risk assess-ment (PRA) and cost/benefit (C/B) analysis which reveals the need to: |
| : 1) an evaluation of the adequacy of existing operating procedures to guide operator response for this event and 2) an evaluation as to whether adequate heat removal through a dried-out steam generator is possible given the presence of a heat transfer barrier lished by the steam that is created by the incoming auxiliary feedwater as it comes into contact with the high temperature steam generator internals. | | a) further evaluate the safety significance of this event given the reliability of existing systems to prevent inadequate core cooling during and after the event and b) should plant modification prove necessary, determine the most cost-effective modification which resolves the concern. The preliminary PRA and C/B analysis (Enclosure 1) shows that the_§requency of a significant release resulting from this event is 9.8 x 10 occurrences/year and that the present cgurse of action (ie, MSIV replacement) results in a C/B ratio of |
| Enclosures 2 and 3 provide our response to the requests. | | $6.1 x 10 /manrem; an expenditure considerably in excess of the NRC safety goal guideline of $1000/manrem. |
| Enclosure 2 cates that the immediate actions prescribed in our MSLB procedures are proper for the two steam generator blowdown event. Enclosure 3 (item 3) indicates that "steam blanketing" is not likely to be a problem given the design of the steam generator, the effectiveness of the internal separators and dryers and the low velocities of the steam which is developed by boiling of the incoming auxiliary feedwater. | | Consumers Power Company met with the Staff in Bethesda on July 26, 1983 to present the results of the preliminary PRA and C/B analysis and to request that the NRC review the results and grant Consumers Power Company a time extension of one operating cycle beyond our current commitment for any neces-sary plant modification. This time extension, if approved, would result in: |
| OC0883-0010A-NL02 | | : 1) Consumers Power Company finalizing its PRA and C/B analysis to determine more accurately the safety significance of this event as well as the most co'st-effective modification (if modification is proven necessary) and submit-ting such analysis by September 1, 1984 and 2) completing any required modifications by the end of the 1986 refueling outage. |
| -* DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983
| | During the July 26, 1983 meeting, the Staff indicated that it would consider our request and would attempt to pass judgment on the request by Septem-ber 1, 1983. However, the Staff requested that Consumers Power Company provide in this submittal certain evaluation regarding plant response during and after the event. The NRC indicated that such evaluation would assist the Staff in its consideration of the request. Specifically, the Staff requested that we provide the following: 1) an evaluation of the adequacy of existing operating procedures to guide operator response for this event and 2) an evaluation as to whether adequate heat removal through a dried-out steam generator is possible given the presence of a heat transfer barrier estab-lished by the steam that is created by the incoming auxiliary feedwater as it comes into contact with the high temperature steam generator internals. |
| * 3 Additional evaluations were requested by the Staff during an August 2, 1983 telephone conference call. These requests are itemized below. It should be noted that Enclosure 3 also responds in part to requests number 1 and 2a. Consumers Power Company will provide a detailed response to each NRC request as part of our final PRA and C/B analysis to be submitted by September 1, 1984. Additional NRC Requests 1. Evaluate the thermal-hydraulic response of the steam generator secondary side during and after the two steam generator blowdown event. 2a. Determine the number of cooldown cycles that would cause the steam generator vessel, tubes or tube sheet to fail. 2b. Determine the number of cooldown cycles that would occur during-and after the event. 3. Should it be determined that tube failure will occur, evaluate the impact on containment failure and include in the evaluation a description of the model utilized to analyze the consequences. | | Enclosures 2 and 3 provide our response to the requests. Enclosure 2 indi-cates that the immediate actions prescribed in our MSLB procedures are proper for the two steam generator blowdown event. Enclosure 3 (item 3) indicates that "steam blanketing" is not likely to be a problem given the design of the steam generator, the effectiveness of the internal separators and dryers and the low velocities of the steam which is developed by boiling of the incoming auxiliary feedwater. |
| | OC0883-0010A-NL02 |
| | |
| | DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983 |
| | * 3 Additional evaluations were requested by the Staff during an August 2, 1983 telephone conference call. These requests are itemized below. It should be noted that Enclosure 3 also responds in part to requests number 1 and 2a. |
| | Consumers Power Company will provide a detailed response to each NRC request as part of our final PRA and C/B analysis to be submitted by September 1, 1984. |
| | Additional NRC Requests |
| | : 1. Evaluate the thermal-hydraulic response of the steam generator secondary side during and after the two steam generator blowdown event. |
| | 2a. Determine the number of cooldown cycles that would cause the steam generator vessel, tubes or tube sheet to fail. |
| | 2b. Determine the number of cooldown cycles that would occur during-and after the event. |
| | : 3. Should it be determined that tube failure will occur, evaluate the impact on containment failure and include in the evaluation a description of the model utilized to analyze the consequences. |
| : 4. Determine the likelihood of a MSLB outside of containment and depending on the probability of such an event: a) evaluate the means by which long term cooling (LTC) would be accomplished taking into account that the spilled coolant would not be filling the sump to provide a LTC supply of water and b) provide a description of the model utilized to analyze the consequences. | | : 4. Determine the likelihood of a MSLB outside of containment and depending on the probability of such an event: a) evaluate the means by which long term cooling (LTC) would be accomplished taking into account that the spilled coolant would not be filling the sump to provide a LTC supply of water and b) provide a description of the model utilized to analyze the consequences. |
| : 5. Evaluate the effect of various MSLB sizes on the plant response. | | : 5. Evaluate the effect of various MSLB sizes on the plant response. |
| : 6. Evaluate the means by which the operator would prevent excessive cooldown that could pull a void on the primary system; especially if there exists a LOCA through the steam generators. | | : 6. Evaluate the means by which the operator would prevent excessive cooldown that could pull a void on the primary system; especially if there exists a LOCA through the steam generators. |
| In conclusion, this submittal represents Consumers Power Company's formal request to change its scheduled date for completing plant modifications to make the MSIV/MS configuration single-failure proof to prior to startup from the 1986 refueling outage. It is the opinion of Consumers Power Company, based on the evaluations to date of the event, that the health and safety of the public will not be jeopardized by this delay. OC0883-0010A-NL02 l' DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983 4 Consumers Power Company also requests that the NRC pass judgment on the request for time extension and notify us of the decision by September 1, 1983 so that our efforts to procure replacement valves and meet our present ment dates for installation are not constrained. | | In conclusion, this submittal represents Consumers Power Company's formal request to change its scheduled date for completing plant modifications to make the MSIV/MS configuration single-failure proof to prior to startup from the 1986 refueling outage. It is the opinion of Consumers Power Company, based on the evaluations to date of the event, that the health and safety of the public will not be jeopardized by this delay. |
| Should our request for time extension be approved, we will submit the final PRA and C/B analysis by September 1, 1984 and will complete any required modification during the 1986 refueling outage. Should our request be denied, we will proceed with our efforts to replace the existing MSIVs on a schedule consistent with our current commitment. | | OC0883-0010A-NL02 |
| Kerry A Toner Senior Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector | | |
| -Palisades Enclosures OC0883-0010A-NL02}} | | l' *~ |
| | DMCrutchfield, Chief 4 Palisades Plant SEP TOPIC XV-2 August 15, 1983 Consumers Power Company also requests that the NRC pass judgment on the request for time extension and notify us of the decision by September 1, 1983 so that our efforts to procure replacement valves and meet our present commit-ment dates for installation are not constrained. Should our request for time extension be approved, we will submit the final PRA and C/B analysis by September 1, 1984 and will complete any required modification during the 1986 refueling outage. Should our request be denied, we will proceed with our efforts to replace the existing MSIVs on a schedule consistent with our current commitment. |
| | Kerry A Toner |
| | ~~rV~ |
| | Senior Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Enclosures OC0883-0010A-NL02}} |
|
|---|
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
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Text
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consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 August 15, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC XV-2 "SPECTRUM OF STEAM PIPING FAILURES INSIDE AND OUTSIDE CONTAINMENT (PWR)" - REQUEST FOR TIME EXTENSION TO RESOLVE CONCERN OF TWO STEAM GENERATOR BLOWDOWNS INSIDE CONTAINMENT During a review of SEP Topic xv~2 "Spectrum of Steam Piping Failures Inside and Outside Containment (PWR)," the NRC Staff became concerned that removal of core decay heat would become unreliable in the event of a main steam line break (MSLB) inside containment and a concurrent failure to close of the main steam isolation valve (MSIV) in the intact main steam (MS) line. As docu-mented in NUREG-0820 "Integrated Plant Safety Assessment, Palisades Plant" dated October 1982, the NRC indicated that such an event would result in unreliable decay heat removal due to the blowdown of both steam generators.
In response to the Staff's concern, Consumers Power Company committed to performing appropriate modifications to make the MSIV/MS configuration single-failure proof with respect to the blowdown event. The commitment, which is also documented in NUREG-0820, presently requires that the modifications be completed. by the end of the 1985 refueling outage. The purposes of this submittal are to: 1) request a time extension of one operating cycle beyond the present commitment in which to make the modifications and 2) provide the NRC with a basis for such a request.
Consumers Power Company is presently on schedule in its efforts to resolve the NRC concern via MSIV replacement by the end of the 1985 outage. We have completed a study which shows the feasibility of replacing the two existing MSIVs with new valves capable of closing under conditions of flow in either direction thereby eliminating the single-failure potential. In addition, we have begun preparing valve procurement specifications which will be completed and forwarded to prospective manufacturers on or about September 1, 1983.
8308230375 830815 PDR ADOCIA. 05000255 P PDR OC0883-0010A-NL02
DMCrutchfield, Chief 2 Palisades Plant SEP TOPIC XV-2 August 15, 1983 Recently, however, we have completed a preliminary probabilistic risk assess-ment (PRA) and cost/benefit (C/B) analysis which reveals the need to:
a) further evaluate the safety significance of this event given the reliability of existing systems to prevent inadequate core cooling during and after the event and b) should plant modification prove necessary, determine the most cost-effective modification which resolves the concern. The preliminary PRA and C/B analysis (Enclosure 1) shows that the_§requency of a significant release resulting from this event is 9.8 x 10 occurrences/year and that the present cgurse of action (ie, MSIV replacement) results in a C/B ratio of
$6.1 x 10 /manrem; an expenditure considerably in excess of the NRC safety goal guideline of $1000/manrem.
Consumers Power Company met with the Staff in Bethesda on July 26, 1983 to present the results of the preliminary PRA and C/B analysis and to request that the NRC review the results and grant Consumers Power Company a time extension of one operating cycle beyond our current commitment for any neces-sary plant modification. This time extension, if approved, would result in:
- 1) Consumers Power Company finalizing its PRA and C/B analysis to determine more accurately the safety significance of this event as well as the most co'st-effective modification (if modification is proven necessary) and submit-ting such analysis by September 1, 1984 and 2) completing any required modifications by the end of the 1986 refueling outage.
During the July 26, 1983 meeting, the Staff indicated that it would consider our request and would attempt to pass judgment on the request by Septem-ber 1, 1983. However, the Staff requested that Consumers Power Company provide in this submittal certain evaluation regarding plant response during and after the event. The NRC indicated that such evaluation would assist the Staff in its consideration of the request. Specifically, the Staff requested that we provide the following: 1) an evaluation of the adequacy of existing operating procedures to guide operator response for this event and 2) an evaluation as to whether adequate heat removal through a dried-out steam generator is possible given the presence of a heat transfer barrier estab-lished by the steam that is created by the incoming auxiliary feedwater as it comes into contact with the high temperature steam generator internals.
Enclosures 2 and 3 provide our response to the requests. Enclosure 2 indi-cates that the immediate actions prescribed in our MSLB procedures are proper for the two steam generator blowdown event. Enclosure 3 (item 3) indicates that "steam blanketing" is not likely to be a problem given the design of the steam generator, the effectiveness of the internal separators and dryers and the low velocities of the steam which is developed by boiling of the incoming auxiliary feedwater.
OC0883-0010A-NL02
DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983
- 3 Additional evaluations were requested by the Staff during an August 2, 1983 telephone conference call. These requests are itemized below. It should be noted that Enclosure 3 also responds in part to requests number 1 and 2a.
Consumers Power Company will provide a detailed response to each NRC request as part of our final PRA and C/B analysis to be submitted by September 1, 1984.
Additional NRC Requests
- 1. Evaluate the thermal-hydraulic response of the steam generator secondary side during and after the two steam generator blowdown event.
2a. Determine the number of cooldown cycles that would cause the steam generator vessel, tubes or tube sheet to fail.
2b. Determine the number of cooldown cycles that would occur during-and after the event.
- 3. Should it be determined that tube failure will occur, evaluate the impact on containment failure and include in the evaluation a description of the model utilized to analyze the consequences.
- 4. Determine the likelihood of a MSLB outside of containment and depending on the probability of such an event: a) evaluate the means by which long term cooling (LTC) would be accomplished taking into account that the spilled coolant would not be filling the sump to provide a LTC supply of water and b) provide a description of the model utilized to analyze the consequences.
- 5. Evaluate the effect of various MSLB sizes on the plant response.
- 6. Evaluate the means by which the operator would prevent excessive cooldown that could pull a void on the primary system; especially if there exists a LOCA through the steam generators.
In conclusion, this submittal represents Consumers Power Company's formal request to change its scheduled date for completing plant modifications to make the MSIV/MS configuration single-failure proof to prior to startup from the 1986 refueling outage. It is the opinion of Consumers Power Company, based on the evaluations to date of the event, that the health and safety of the public will not be jeopardized by this delay.
OC0883-0010A-NL02
l' *~
DMCrutchfield, Chief 4 Palisades Plant SEP TOPIC XV-2 August 15, 1983 Consumers Power Company also requests that the NRC pass judgment on the request for time extension and notify us of the decision by September 1, 1983 so that our efforts to procure replacement valves and meet our present commit-ment dates for installation are not constrained. Should our request for time extension be approved, we will submit the final PRA and C/B analysis by September 1, 1984 and will complete any required modification during the 1986 refueling outage. Should our request be denied, we will proceed with our efforts to replace the existing MSIVs on a schedule consistent with our current commitment.
Kerry A Toner
~~rV~
Senior Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Enclosures OC0883-0010A-NL02
