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| e-SHAW. PITTMAN, PoTTs & TROWBRIDG E 1800 M S TR E ET. N. W. | | e-SHAW. PITTMAN, PoTTs & TROWBRIDG E 1800 M S TR E ET. N. W. |
| WA S HI NGTO N. O. C. 2O O3 6 l'"a*:,%.%2 ~ s'"n,*c." "i". \ UI ''*''''"''** | | WA S HI NGTO N. O. C. 2O O3 6 l'"a*:,%.%2 ~ s'"n,*c." "i". \ UI ''*''''"''** |
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| $$b!$ "$"%"o'!" September 25, 1980 Herbert Grossman, Esq. Dr. Richard F. Cole Chairman Atomic Safety and Licensing Board j Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission ' | | $$b!$ "$"%"o'!" September 25, 1980 Herbert Grossman, Esq. Dr. Richard F. Cole Chairman Atomic Safety and Licensing Board j Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission ' |
| U.S. Nuclear Regulatcry Commission Washington, D.C. 20555 l Washington, D.C. 20555 ! | | U.S. Nuclear Regulatcry Commission Washington, D.C. 20555 l Washington, D.C. 20555 ! |
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| Wisconsin Electric has responded to the allegations set forth in ! | | Wisconsin Electric has responded to the allegations set forth in ! |
| the letters to Senator Proxmire and Congressman Zablocki by letters l dated September 24, 1980. The letter to Senator Proxmire is i enclosed with this letter; an identical letter was sent to l Congressman Zablocki. | | the letters to Senator Proxmire and Congressman Zablocki by letters l dated September 24, 1980. The letter to Senator Proxmire is i enclosed with this letter; an identical letter was sent to l Congressman Zablocki. |
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| SHAW, PITTMAN, POTTS & TROWBRIDOE A copy of this letter and the enclosed letter to Senator Proxmire is being served on all parties to the above proceeding. | | SHAW, PITTMAN, POTTS & TROWBRIDOE A copy of this letter and the enclosed letter to Senator Proxmire is being served on all parties to the above proceeding. |
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| .P | | .P Joh H. O'Neill, Jr. |
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| | I cou sel for Wisconsi M lectric P wer Company Enclosures cc: Service List |
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| Joh H. O'Neill, Jr. | |
| I cou sel for Wisconsi M lectric P wer Company Enclosures | |
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| Wisconsin Electncmeacoursur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 September 24, 1980 . | | Wisconsin Electncmeacoursur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 September 24, 1980 . |
| The Honorable William Proxmire United States Senate Washington, D.C. 20510 l | | The Honorable William Proxmire United States Senate Washington, D.C. 20510 l |
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| ==Dear Senator Proxmire:== | | ==Dear Senator Proxmire:== |
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| The Nuclear Regulatory Commission (NRC) recently provided us with a copy of a letter to you from Wisconsin's Environmental Decade, Inc. (Decade), dated August 8, 1980, which asserts that a dangerous condition exists at Wisconsin Electric Power Company's Point Beach Nuclear Plant, Unit 1. Of course, such is not the case. Decade, in its opposition to i nuclear power, has over the years become somewhat accomplished ' | | The Nuclear Regulatory Commission (NRC) recently provided us with a copy of a letter to you from Wisconsin's Environmental Decade, Inc. (Decade), dated August 8, 1980, which asserts that a dangerous condition exists at Wisconsin Electric Power Company's Point Beach Nuclear Plant, Unit 1. Of course, such is not the case. Decade, in its opposition to i nuclear power, has over the years become somewhat accomplished ' |
| in linking series of statements out of context, selected facts, half-truths, and outright distortions, and we believe that you should be apprised of the actual facts. We invite you to compare the information in this letter with the hyperbole and alarmist allegations presented to you by Decade. | | in linking series of statements out of context, selected facts, half-truths, and outright distortions, and we believe that you should be apprised of the actual facts. We invite you to compare the information in this letter with the hyperbole and alarmist allegations presented to you by Decade. |
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| 1 The Honorable William Proxmire September 24, 1980 Page 2 i | | 1 The Honorable William Proxmire September 24, 1980 Page 2 i |
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| from the steam generator tube leaks or tube rupture at ' Point Beach. Any radiological releases from steam generator tube leakage was many time below the maximum allowable. Wisconsin Electric, its consultants, and the NRC have considered the safety significance of the steam generator tube degradation problem at Point Beach. Wisconsin Electric has taken certain ' | | from the steam generator tube leaks or tube rupture at ' Point Beach. Any radiological releases from steam generator tube leakage was many time below the maximum allowable. Wisconsin Electric, its consultants, and the NRC have considered the safety significance of the steam generator tube degradation problem at Point Beach. Wisconsin Electric has taken certain ' |
| actions with NRC concurrence to insure that Point Beach Unit 1 continues to operate safely while the most effective repair i | | actions with NRC concurrence to insure that Point Beach Unit 1 continues to operate safely while the most effective repair i |
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| program for the steam generators is selected and implemented. ' | | program for the steam generators is selected and implemented. ' |
| In its letter to you, Decade engages in a vitriolic attack on the NRC. Decade may be venting its frustration in having failed to convey to the NRC that its position on the steam generator tube degradation problem has any merit. But i again Decade's attack missed the mark by a wide margin. If { | | In its letter to you, Decade engages in a vitriolic attack on the NRC. Decade may be venting its frustration in having failed to convey to the NRC that its position on the steam generator tube degradation problem has any merit. But i again Decade's attack missed the mark by a wide margin. If { |
| anything, the NRC has become cautious in the extreme since Three Mile Island. Decade's quote from the Kemeny Commission s | | anything, the NRC has become cautious in the extreme since Three Mile Island. Decade's quote from the Kemeny Commission s Report is incomplete--perhaps deliberately so. |
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| Report is incomplete--perhaps deliberately so. | |
| In fact, the NRC has been responsive to the steam generator concerns. The NRC Commissioners were formally briefed on the steam generator tube degradation problems at | | In fact, the NRC has been responsive to the steam generator concerns. The NRC Commissioners were formally briefed on the steam generator tube degradation problems at |
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| ' Point Beach on two occasions, once by representatives from Decade. Decade raised the safety issues set forth in its letter to you by petitions to the Commission on two separate occasions. After preparing a safety evaluation report, which addressed Decade.'s concerns, the Director, Nuclear Reactor Regulation, rejected Decade's position as unfounded on each occasion. The Director's decision was not overturned by the Commissioners after their review. We should point out that the NRC would have conducte,d its review without Decade's involve- | | ' Point Beach on two occasions, once by representatives from Decade. Decade raised the safety issues set forth in its letter to you by petitions to the Commission on two separate occasions. After preparing a safety evaluation report, which addressed Decade.'s concerns, the Director, Nuclear Reactor Regulation, rejected Decade's position as unfounded on each occasion. The Director's decision was not overturned by the Commissioners after their review. We should point out that the NRC would have conducte,d its review without Decade's involve- |
| ; ment. | | ; ment. |
| Decade cites a 1975 American Physical Society report in support of its allegations. Again Decade quotes material out of context. The purpose of the American Physical Society | | Decade cites a 1975 American Physical Society report in support of its allegations. Again Decade quotes material out of context. The purpose of the American Physical Society |
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| j study was to critique the light water reactor safety program in general and the emergency core cooling system (ECCS) interim acceptance criteria established by the Atomic Energy Commission in particular. The American Physical Society report pointed | | j study was to critique the light water reactor safety program in general and the emergency core cooling system (ECCS) interim acceptance criteria established by the Atomic Energy Commission in particular. The American Physical Society report pointed i out areas where it believed additional research or conservation could be introduced in the ECCS analysis. The question postulated by the American Physical Society deals with a loss-of-coolant accident to the reactor followed by a number of steam generator tube ruptures which in theory could result in restricted flow of emergency cooling to the reactor core. I The principal reason that this concern is not applicable to the situation at Point Beach Unit 1 is fairly |
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| i out areas where it believed additional research or conservation could be introduced in the ECCS analysis. The question postulated by the American Physical Society deals with a loss-of-coolant accident to the reactor followed by a number of steam generator tube ruptures which in theory could result in restricted flow of emergency cooling to the reactor core. I The principal reason that this concern is not applicable to the situation at Point Beach Unit 1 is fairly | |
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| | 4 i The Honorable William Proxmire September 24, 1980 Page 3 simple. The postulated problem requires a number of |
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| 4 i The Honorable William Proxmire September 24, 1980 Page 3 | |
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| simple. The postulated problem requires a number of | |
| , " double-ended" breaks of steam generator tubes. The tube degradation at Point Beach occurs within the 23-inch tubesheet. | | , " double-ended" breaks of steam generator tubes. The tube degradation at Point Beach occurs within the 23-inch tubesheet. |
| Thus, a tube break would be physically restrained by the tubesheet, and the postulated double-ended breaks of steam | | Thus, a tube break would be physically restrained by the tubesheet, and the postulated double-ended breaks of steam |
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| generator tubes could simply not occur. To demonstrate the integrity of Lne steam generator tubes, on a periodic schedule, the tubes are subjected to a hydrostatic test--a high differential pressure across the tubes approximating the forces : | | generator tubes could simply not occur. To demonstrate the integrity of Lne steam generator tubes, on a periodic schedule, the tubes are subjected to a hydrostatic test--a high differential pressure across the tubes approximating the forces : |
| which might be caused by a loss-of-coolant accident. ' | | which might be caused by a loss-of-coolant accident. ' |
| Wisconsin Electric has taken a number of steps to | | Wisconsin Electric has taken a number of steps to insure the plant is being operated safely notwithstanding the : |
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| insure the plant is being operated safely notwithstanding the : | |
| steam generator tube problem. The plant is being operated at a | | steam generator tube problem. The plant is being operated at a |
| , lower temperature at approximately 804 power level in order to | | , lower temperature at approximately 804 power level in order to |
| ; inhibit the rate of tube degradation, which appears to be | | ; inhibit the rate of tube degradation, which appears to be |
| ; related to temperature. The Company is conducting more frequent periodic inspections of all steam generator tubes and is regularly conducting the hydrostatic differential pressure test described above to insure the integrity of the system | | ; related to temperature. The Company is conducting more frequent periodic inspections of all steam generator tubes and is regularly conducting the hydrostatic differential pressure test described above to insure the integrity of the system boundaries. These measures have been approved by the NRC and, i . in some cases, have been confirmed by an NRC Order. Most recent inspections appear to indicate a reduction in the rate of tube degradation. |
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| boundaries. These measures have been approved by the NRC and, i . in some cases, have been confirmed by an NRC Order. Most recent inspections appear to indicate a reduction in the rate of tube degradation. | |
| Decade's complaints that it has not been afforded an | | Decade's complaints that it has not been afforded an |
| : opportunity for.a hearing on these issues go to the NRC Confirmatory orders confirming the actions taken by Wisconsin | | : opportunity for.a hearing on these issues go to the NRC Confirmatory orders confirming the actions taken by Wisconsin Electric. Decade has petitioned for a public hearing regarding these Orders. An Atomic Safety and Licensing Board presently has before it the question of whether, as a matter of law, Decade has a right to such a hearing. The " stinging dissent" |
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| | { by two NRC Commissioners referred to by Decade goes only to the policy question relating to the circumatances as to when a public hearing should be provided. It has nothing to do with the merits of the situation at Point Beach. |
| Electric. Decade has petitioned for a public hearing regarding these Orders. An Atomic Safety and Licensing Board presently has before it the question of whether, as a matter of law, | |
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| Decade has a right to such a hearing. The " stinging dissent" | |
| { by two NRC Commissioners referred to by Decade goes only to the | |
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| policy question relating to the circumatances as to when a public hearing should be provided. It has nothing to do with the merits of the situation at Point Beach. | |
| Wisconsin Electric has one of the finest operating records of any utility in the country at its Point Beach Nuclear Plant. No one is more interested in the absolute safe operation of the Point Beach Plant than those of us responsible for its opera'lon c and maintenance. The actions that have been taken at Point Beach insure its safe operation until necessary repairs are accomplished. | | Wisconsin Electric has one of the finest operating records of any utility in the country at its Point Beach Nuclear Plant. No one is more interested in the absolute safe operation of the Point Beach Plant than those of us responsible for its opera'lon c and maintenance. The actions that have been taken at Point Beach insure its safe operation until necessary repairs are accomplished. |
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| | The Honorable William Proxmire September 24, 1980 Page 4 We appreciate this opportunity to set the fact's straight. We, of course, would be happy to answer any questions that you might have. |
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| The Honorable William Proxmire September 24, 1980 Page 4 | |
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| We appreciate this opportunity to set the fact's straight. We, of course, would be happy to answer any questions that you might have. | |
| Very truly yours, | | Very truly yours, |
| _ ^D hw tb Exe utive Vice President Sol Burstein cc: Nuclear Regulatory Commission NRC Atomic Safety and Licensing Board Public Service Commission of Wisconsin Wisconsin's Environmental Decade, Inc. | | _ ^D hw tb Exe utive Vice President Sol Burstein cc: Nuclear Regulatory Commission NRC Atomic Safety and Licensing Board Public Service Commission of Wisconsin Wisconsin's Environmental Decade, Inc. |
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| | UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION THE ATOMIC SAFETY AND LICENSING BOARD i |
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| 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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| * THE ATOMIC SAFETY AND LICENSING BOARD i
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| In the Matter of ) | | In the Matter of ) |
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| U.S. Nuclear Regulatory Commission Hill Farms State Office Washington, D.C. 20555 Building 4802 Sheboygan Avenue ' | | U.S. Nuclear Regulatory Commission Hill Farms State Office Washington, D.C. 20555 Building 4802 Sheboygan Avenue ' |
| Dr. Richard F. Cole Madison, Wisconsin 53702 I Atomic Safety and Licensing Board U.S. Nuclear Regulato;y Commssion Kathleen M. Falk, Esquire j Washington, D.C. 20555 Wisconsin's Environmental Decade, Inc. - Suite 205 i | | Dr. Richard F. Cole Madison, Wisconsin 53702 I Atomic Safety and Licensing Board U.S. Nuclear Regulato;y Commssion Kathleen M. Falk, Esquire j Washington, D.C. 20555 Wisconsin's Environmental Decade, Inc. - Suite 205 i |
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| Dr. J. Venn Leeds 302 East Washington Avenue 10807 Atwell Madison, Wisconsin 53703 Houston, Texas 77096 Docketing and Service Section i | | Dr. J. Venn Leeds 302 East Washington Avenue 10807 Atwell Madison, Wisconsin 53703 Houston, Texas 77096 Docketing and Service Section i |
| Karen D. Cyr, Esquire Office of the Secretary U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory | | Karen D. Cyr, Esquire Office of the Secretary U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory I |
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| | Office of the Executive Commission Legal Director Washington, D.C. 20555 Washington, D.C. 20555 |
| I Office of the Executive Commission Legal Director Washington, D.C. 20555 Washington, D.C. 20555
| | , Patrick Walsh, Esquire Assistant Attorney General State of Wisconsin Department of Justice 114 East State Capital Madison, Wisconsin 53702 Ms. Jacqueline K. Reynolds Assistant Secretary to the Commission Public Service Commission of Wisconsin Hill Farms State Office Building 4802 Sheboygan Avenue l Madison, Wisconsin 53702 l |
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| , Patrick Walsh, Esquire Assistant Attorney General State of Wisconsin Department of Justice 114 East State Capital Madison, Wisconsin 53702 Ms. Jacqueline K. Reynolds Assistant Secretary to the Commission Public Service Commission of Wisconsin Hill Farms State Office Building | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability ML20217A5911999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issues Matrix Encl 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics ML20212J7431999-09-30030 September 1999 Forwards Insp Repts 50-266/99-15 & 50-301/99-15 on 990830- 0903.No Violations Noted.Inspectors Concluded That Util Licensed Operator Requalification Training Program Satisfactorily Implemented NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel ML20212K7651999-09-29029 September 1999 Forwards Insp Repts 50-266/99-13 & 50-301/99-13 on 990714-0830.No Violations Noted.Operators Responded Well to Problems with Unit 1 Instrument Air Leak & Unit 2 Turbine Governor Valve Position Fluctuation ML20212D5771999-09-15015 September 1999 Discusses Review of Response to GL 88-20,suppl 4,requesting All Licensees to Perform Ipeee.Ser,Ter & Supplemental TER Encl ML20211Q6451999-09-0808 September 1999 Forwards Operator Licensing Exam Repts 50-266/99-301OL & 50-301/99-301OL for Exams Conducted on 990726-0802 at Point Beach Npp.All Nine Applicants Passed All Sections of Exam ML20211Q4171999-09-0606 September 1999 Responds to VA Kaminskas by Informing That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Weeks of 001016 & 23.Validation of Exam Will Occur at Station During Wk of 000925 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump ML20211K5261999-08-31031 August 1999 Forwards Insp Repts 50-266/99-14 & 50-301/99-14 on 990726- 30.Areas Examined within Secutity Program Identified in Rept.No Violations Noted ML20211F6941999-08-27027 August 1999 Provides Individual Exam Results for Applicants That Took Initial License Exam in July & August of 1999.Completed ES-501-2,copy of Each Individual License,Ol Exam Rept, ES-303-1,ES-303-2 & ES-401-8 Encl.Without Encl NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months ML20211E8791999-08-24024 August 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Point Beach Nuclear Power Plant,Units 1 & 2.Licensees Provided Requested Info & Responses Required by GL 96-01 ML20211F1501999-08-24024 August 1999 Submits Summary of Meeting Held on 990729,in Region III Office with Util Re Proposed Revs to Plant Emergency Action Level Criteria Used in Classifying Emergencies & Results of Recent Improvement Initiatives in Emergency Preparedness 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached ML20210L9141999-08-0404 August 1999 Informs That Versions of Info Re WCAP-14787,submitted in 990622 Application for Amend,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210K5221999-08-0404 August 1999 Discusses Point Beach Nuclear Plant,Units 1 & 2 Response to Request for Info in GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 ML20210G6011999-07-30030 July 1999 Discusses 990415 Complaint OSHA Received from Employee of Wisconsin Electric Power Co Alleging That Employee Received Lower Performance Appraisal for 1998 Because Employee Raised Safety Concerns While Performing Duties at Point Beach NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal ML20210H0211999-07-28028 July 1999 Forwards Insp Repts 50-266/99-09 & 50-301/99-09 on 990528-0713.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210G2441999-07-26026 July 1999 Discusses 990714 Meeting with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 ML20209H5471999-07-14014 July 1999 Forwards Insp Repts 50-266/99-12 & 50-301/99-12 on 990614-18.One Violation Noted,But Being Treated as non-cited violation.Long-term MOV Program Not Sufficiently Established to close-out NRC Review of Program,Per GL 89-10 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20196J4161999-06-30030 June 1999 Discusses Relief Requests Submitted by Wisconsin Electric on 980930 for Pump & Valve Inservice Testing Program,Rev 5. Safety Evaluation Authorizing Relief Requests VRR-01,VRR-02, PRR-01 & ROJ-16 Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions ML20196D4931999-06-18018 June 1999 Forwards Insp Repts 50-266/99-08 & 50-301/99-08 on 990411- 0527.No Violations Noted.Operator Crew Response to Equipment Induced Challenges Generally Good.Handling of Steam Plume in Unit 1 Turbine Bldg Particularly Good ML20195J9471999-06-16016 June 1999 Discusses Ltr from NRC ,re Arrangements Made to Finalized Initial Licensed Operator Exam to Be Administered at Point Beach Nuclear Plant During Week of 990726 ML20196A2931999-06-16016 June 1999 Ack Receipt of Transmitting Changes to Listed Sections of Point Beach Nuclear Plant Security Plan & ISFSI Security Plan,Submitted IAW 10CFR50.54(p).No NRC Approval Is Required Since Changes Do Not Decrease Effectiveness ML20195J9251999-06-14014 June 1999 Discusses 990610 Telcon Between Wp Walker & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Point Beach Nuclear Power Plant for Week of 990816 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 ML20206T3691999-05-17017 May 1999 Ltr Contract,Task Order 242 Entitled, Review Point Beach 1 & 2 Conversion of Current TS for Electrical Power Systems to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20206N5561999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Point Beach Npp.Organization Chart Encl ML20206P2551999-05-12012 May 1999 Forwards Handout Provided to NRC by Wisconsin Electric at 990504 Meeting Which Discussed Several Recent Operational Issues & Results of Recent Improvement Initiatives in Engineering ML20206N5331999-05-12012 May 1999 Forwards RAI Re & Suppl by Oral Presentation During 980604 Meeting,Requesting Amend for Plant,Units 1 & 2 to Revise TSs 15.3.12 & 15.4.11 ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure ML20206K0391999-05-0707 May 1999 Forwards Insp Repts 50-266/99-06 & 50-301/99-06 on 990223- 0410.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure NPL-99-0242, Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage1999-04-27027 April 1999 Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage NPL-99-0246, Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl1999-04-27027 April 1999 Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl ML20206C2361999-04-22022 April 1999 Forwards 1998 Annual Rept to Stockholders of Wepc Which Includes Certified Financial Statements,Per 10CFR50.71 NPL-99-0230, Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC1999-04-19019 April 1999 Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC 05000301/LER-1999-002, Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italic1999-04-16016 April 1999 Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italics NPL-99-0219, Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire1999-04-15015 April 1999 Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire 05000266/LER-1999-001, Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics i1999-04-0808 April 1999 Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics in Rept NPL-99-0174, Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 9807141999-03-30030 March 1999 Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 980714 ML20206B8231999-03-30030 March 1999 Forwards Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981103 for Point Beach Power Plant.One Deficiency Identified for Manitowoc County.County Corrected Deficiency Immediately NPL-99-0177, Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.751999-03-30030 March 1999 Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.75 05000301/LER-1999-001, Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics1999-03-10010 March 1999 Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics NPL-99-0122, Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 &1999-03-0303 March 1999 Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 & 2 NPL-99-0111, Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months1999-03-0303 March 1999 Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months NPL-99-0116, Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld1999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld NPL-99-0115, Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 21999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0114, Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage1999-02-25025 February 1999 Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage NPL-99-0086, Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure1999-02-24024 February 1999 Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure NPL-99-0101, Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld1999-02-19019 February 1999 Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld ML20203F7301999-02-10010 February 1999 Forwards Revs to Security Plan Sections 1.2,1.3,1.4,2.1,2.5, 2,6,2.8,6.1,6.4,6.5,B-3.0,B-4.0,B-5.0 & Figure R Dtd 990210. Evaluation & Description of Plan Revs Also Encl to Assist in NRC Review.Encls Withheld NPL-99-0067, Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 21999-02-0202 February 1999 Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 2 NPL-99-0064, Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement1999-02-0202 February 1999 Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement NPL-98-1032, Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld1999-01-27027 January 1999 Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld 05000266/LER-1998-029, Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications1999-01-26026 January 1999 Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications NPL-99-0031, Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr1999-01-15015 January 1999 Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr NPL-99-0004, Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 21999-01-11011 January 1999 Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0012, Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld1999-01-0808 January 1999 Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld 1999-09-30
[Table view] Category:LEGAL/LAW FIRM TO NRC
MONTHYEARML20212C2211987-01-27027 January 1987 FOIA Request for Daily Average Emission Readings for Pantex Plant,Test Reactor Area,Point Beach Nuclear Power Plant, Tarapur Atomic Power Plant & Nuclenor Power Plant ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20078F9781983-10-0707 October 1983 Informs That Licensee Will File Response to Wisconsin Environ Decade,Inc Petition Served on 830923 by 831017.Svc List Encl ML20072N9161983-07-13013 July 1983 Notifies of Vr Harding Employment at Law Firm Per Disciplinary Rule 9-102.Harding Will Not Participate in Any Case Currently Pending Before NRC ML20072P0611983-07-13013 July 1983 Informs That Author Will Be Associate in Law Firm General Corporate Practice & Will Not Participate in Any Cases Now Pending Before Nrc.Certificate of Svc Encl ML20072P0461983-07-13013 July 1983 Informs That Vr Harding,Formerly of Oeld,Will Be Associate in Law Firm General Corporate Practice.Harding Will Not Participate in Any Cases Now Pending Before NRC ML20072P0191983-07-13013 July 1983 Notifies of Author Employment at Law Firm Per Disciplinary Rule 9-102.Author Will Not Participate in Any Case Currently Pending Before NRC ML20072P0091983-07-13013 July 1983 Notifies of Vr Harding Employment at Law Firm Per Disciplinary Rule 9-102.Harding Will Not Participate in Any Case Currently Pending Before NRC ML20072N9381983-07-13013 July 1983 Notifies of Author Employment at Law Firm Per Disciplinary Rule 9-102.Author Will Not Participate in Any Case Currently Pending Before NRC ML20023C3831983-05-13013 May 1983 Opposes Wisconsin Environ Decade 830506 Request to Provide Westinghouse Proprietary Info from Licensee.Decade Petition for Discretionary Commission Review Does Not Entitle Petitioner to Proprietary Info.Svc List Encl ML20073Q4091983-04-27027 April 1983 Forwards Info Re Steam Generator Tube Repair,Requested in Aslab 830322 Order.Westinghouse Proprietary Info Withheld (Ref 10CFR2.790) ML20028D5131983-01-17017 January 1983 Requests Issuance of Initial Decision Authorizing OL Amends to Permit Sleeving of Steam Generator Tubes.Licensee & NRC Filed Proposed Findings of Fact & Conclusions of Law on 821223 & 830110,respectively.Certificate of Svc Encl ML20064H4141983-01-10010 January 1983 Forwards Replacement P 2 of Licensee 821220 Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision.Citations Supporting Paragraphs 3 & 4 Added 05000266/LER-1982-017, Forwards 821210 Rev to Licensee 821115 LER 82-017/01T-1 Containing Addl Info Re Eddy Current Indication on Inner Diameter of Sleeve.W/O Rev.Svc List Encl1983-01-0707 January 1983 Forwards 821210 Rev to Licensee 821115 LER 82-017/01T-1 Containing Addl Info Re Eddy Current Indication on Inner Diameter of Sleeve.W/O Rev.Svc List Encl ML20028C3001983-01-0404 January 1983 Forwards Licensee 830104 Brief Opposing Wi Environ Decade 821220 Appeal of ASLB 821210 Order Dismissing Decade 820810 Petition to Intervene.Expeditious Action Requested Due to Steam Generator Repair Schedule.Svc List Encl ML20070H3921982-12-20020 December 1982 Forwards Licensee Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision Re Repair of Corroded Steam Generator Tubes ML20027E7281982-11-0909 November 1982 Informs of Completed Visual Fiberscope Insp for Loose Parts in Unit 1 Steam Generators.Insp Revealed Presence of Several Foreign Objects in Secondary Side of Steam Generator.Loose Parts Bear No Relationship to Sleeving.Svc List Encl ML20063P0641982-10-0707 October 1982 Forwards Documentation Re Steam Generator Replacement Application Filed Prior to 820819 Establishment of Aslb. Documentation Consists of Steam Generator Repair Repts & Correspondence Between Licensee & Commission.W/O Encl ML20069F8271982-09-24024 September 1982 Forwards Documentation Re Steam Generator Replacement Application Filed Prior to 820819 Establishment of Aslb. Documentation Consists of Steam Generator Repair Repts & Correspondence Between Licensee & Commission.W/O Encl ML20065C2771982-09-21021 September 1982 Disputes Conclusions in Wi Environ Decade Re Intergranular Attack Detection by Eddy Current Insp.Svc List Encl ML20027B3751982-09-16016 September 1982 Forwards Response to ASLB Question on Radiolysis in Sleeve/Tube Annulus,Per 820909 Conference Call.Notarized Affidavit Forthcoming.Svc List Encl ML20063H0151982-08-26026 August 1982 Memorializes Wi Environ Decade,Nrc & Util Agreement & ASLB Approval of Rescheduling Conference Call on Decade Motion Concerning Litigible Issues for 820909.Svc List Encl ML20062N0631982-08-18018 August 1982 Confirms Licensee Understanding W/Wi Environ Decade Re Time for Filing Decade Amend to Decade Motion Concerning Litigable Issues.Licensee Provided Disputed Documents to Decade on 820818.Amend to Motion Due 820820.Svc List Encl ML20063C6291982-08-0909 August 1982 Forwards Licensee Response to Wi Environ Decade Motion Re Litigable Issues & Wd Fletcher Statement.Proprietary Versions Served on NRC & Decade.Nonproprietary Version Served on Remainder of Svc List ML20058B9481982-07-21021 July 1982 Memorializes 820719 Telcon Re Anticipated Late Filing of Wi Environ Decade Motion on Litigable Issues.Decade Directed to File two-thirds of Motion by 820720 & one-third by 820721. Svc List Encl ML20058B9261982-07-21021 July 1982 Memorializes 820720 Telcon W/Wi Environ Decade Re Identification of Litigable Issues.Svc List Encl ML20063E3891982-07-0909 July 1982 Advises That Alternate Upper Joint Design Will Not Be Used in Sleeving Program.Licensee Will Not Provide Requested Info & NRC Will Not Need to Issue SER Suppl.Certificate of Svc Encl ML20063E3271982-07-0808 July 1982 Advises That Util Does Not Object to NRC 820630 Request for Clarification of ASLB 820526 Memorandum & Order.Util Does Object to Wi Environ Decade Requesting Ruling Re Waiver of Party Right to Withdraw Info.Svc List Encl 05000266/LER-1982-007, Opposes Wi Environ Decade Re LER 82-007.Issues Advanced Re Decontamination Process & Removal of Mechanical Plugs Constitute ill-conceived Attempt to Raise New Issues Unrelated to Case1982-06-16016 June 1982 Opposes Wi Environ Decade Re LER 82-007.Issues Advanced Re Decontamination Process & Removal of Mechanical Plugs Constitute ill-conceived Attempt to Raise New Issues Unrelated to Case ML20053F0211982-06-0707 June 1982 Summarizes 820601 Telcon Re Scheduling Matters.Ltr to Serve as Minutes of Telcon.Schedule of Proceeding Adopted as List ML20052G8771982-05-14014 May 1982 Summarizes 820507 Conference Call Re Dispute W/Wi Environ Decade on Release of Workers Involved in Fall,1981 Demonstration Sleeving Program.Notice of Appearance & Certificate of Svc Encl ML20052B6771982-04-26026 April 1982 Forwards Util 820423 Ltr to HR Denton Responding to Request for Info Re Radiation Exposure Estimates for Installation of Sleeves in Steam Generator Tubes Per WCAP-9960,Revision 1, Sleeving Rept. Encl Withheld (Ref 10CFR2.790) ML20052A2231982-04-23023 April 1982 Corrects Typographical Error in Licensee 820423 Ltr Transmitting Nonproprietary Version of WCAP-9960,Revision 1, Point Beach Steam Generator Sleeving Rept. Proprietary Info Not Marked ML20052A2361982-04-23023 April 1982 Informs That Wi Environ Decade 820416 Reply to Licensee Response to Decade Motion to Compel Expressly Prohibited by 10CFR2.736 ML20054C5271982-04-16016 April 1982 Forwards Reprint of Revision 1 to Point Beach Steam Generator Sleeving Rept. Reprint Replaces Rept Transmitted in Util 820312 Ltr & Includes Marks Which Delineate Proprietary Info.Rept Withheld (Ref 10CFR2.790) ML20054C2691982-04-14014 April 1982 Forwards RA Wiesemann Testimony in Response to ASLB 820325 Questions ML20050V2701982-04-12012 April 1982 Objects to Intervenor Representative Contact of Licensee Employee W/O Prior Consent of Licensee Counsel ML20050H0571982-04-0909 April 1982 Responds to P Bloch 820405 Question.Suggestion of Tour of Westinghouse Facilities Intended as Request to Present Demonstrative Evidence as Part of Evidentiary Record on Proprietary Issues.Related Correspondence ML20050C2501982-03-30030 March 1982 Advises That,Based on Review of Listed Documents Filed by Wi Environ Decade,Westinghouse Will Not Conduct cross-examination ML20050C4291982-03-30030 March 1982 Notifies That No Hearing Need Be Convened to cross-examine Westinghouse,Nrc & Wi Environ Decade,Inc Testimony Re Proprietary Nature of Steam Generator Sleeving Rept.Svc List Encl ML20042B7351982-03-22022 March 1982 Advises That Licensee Will Respond to ASLB Second Question in 820304 Telcon in Brief to Be Filed on 820408.Svc List Encl ML20049H8571982-03-0101 March 1982 Opposes Wi Environ Decade Request That Reporter Transcribing Telcon Prepare Separate Page Summarizing Schedules Established.Schedules Would Be Subj to Reporter Interpretation.Svc List Encl ML20040D7601982-01-26026 January 1982 Requests ASLB Replace 820107 Protective Agreement Attached to Supplementary Order,W/Encl Modified Agreement.Certificate of Svc Encl ML20040C0911982-01-21021 January 1982 Advises That Nonproprietary Versions of Point Beach Steam Generator Sleeving Rept for Wi Electric Power Co & Steam Generator Repair Rept,San Onofre Unit 1, Submitted to NRC for Placement in PDR ML20039E1381981-12-31031 December 1981 Forwards RA Wiesemann Affidavit Per ASLB 811221 Order, Proposed Protective Agreement,Motion for Reconsideration, Motion Authorizing Discovery & Notice of Appearance.Related Correspondence ML20039E1221981-12-29029 December 1981 Forwards Table of Contents & Legal Citations Omitted from Licensee 811228 Brief in Response to Wi Environ Decade Exceptions to Memorandum & Order Authorizing Interim Operation W/Up to Six Tubes Sleeved Rather than Plugged ML20062M6391981-12-14014 December 1981 Advises That Licensee Will Respond If Wi Environ Decade Petitions for Leave to File Addl Contentions.Related Correspondence ML20038A9821981-11-12012 November 1981 Forwards Licensee Response to Wi Environ Decade Oral Motion for Disclosure of Proprietary Info ML20005C0821981-11-0606 November 1981 Forwards Util 811106 Ltr Submitting Sleeving Demonstration Result,Pursuant to ASLB 811105 Memorandum & Order, Authorizing Issuance of License Amend for Return to Power W/Up to Six Degraded Tubes Sleeved Rather than Plugged ML20005C1251981-11-0606 November 1981 Provides Schedule for Util Response to Intervenor Oral Motion for Disclosure of Info Re Tests Conducted for Safety Purposes.Response Will Be Filed on 811112,10 Days After Receipt of Transcript of 811030 Proceeding 1987-01-27
[Table view] |
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$$b!$ "$"%"o'!" September 25, 1980 Herbert Grossman, Esq. Dr. Richard F. Cole Chairman Atomic Safety and Licensing Board j Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission '
U.S. Nuclear Regulatcry Commission Washington, D.C. 20555 l Washington, D.C. 20555 !
i Dr. J. Venn Leeds I 10807 Atwell Houston, Texas 77096 Re: Wisconsin Electric Power Company (Point Beach Nuclear Plant Unit 1) Docket No.
50-266 CO (Modification of License)
Gentlemen:
Wisconsin Electric Power Company has been served with copies of correspo..dence to Senator William Proxmire and Congressman Clement Zablocki from William Dircks, Acting Executive Director for Operations, and to Kathleen M. Falk, Wisconsin's Environmental Decade, Inc., from James Murray, Office of Executive Legal Director, regarding letters directed to Senator Proxmire, Congressman Zablocki and the Commissioners from Wisconsin's Environmental Decade, Inc.
dealing with the subject matter of the above captioned proceeding.
Wisconsin Electric has responded to the allegations set forth in !
the letters to Senator Proxmire and Congressman Zablocki by letters l dated September 24, 1980. The letter to Senator Proxmire is i enclosed with this letter; an identical letter was sent to l Congressman Zablocki.
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SHAW, PITTMAN, POTTS & TROWBRIDOE A copy of this letter and the enclosed letter to Senator Proxmire is being served on all parties to the above proceeding.
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.S*nc ely, *
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.P Joh H. O'Neill, Jr.
I cou sel for Wisconsi M lectric P wer Company Enclosures cc: Service List
Wisconsin Electncmeacoursur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 September 24, 1980 .
The Honorable William Proxmire United States Senate Washington, D.C. 20510 l
Dear Senator Proxmire:
The Nuclear Regulatory Commission (NRC) recently provided us with a copy of a letter to you from Wisconsin's Environmental Decade, Inc. (Decade), dated August 8, 1980, which asserts that a dangerous condition exists at Wisconsin Electric Power Company's Point Beach Nuclear Plant, Unit 1. Of course, such is not the case. Decade, in its opposition to i nuclear power, has over the years become somewhat accomplished '
in linking series of statements out of context, selected facts, half-truths, and outright distortions, and we believe that you should be apprised of the actual facts. We invite you to compare the information in this letter with the hyperbole and alarmist allegations presented to you by Decade.
The two steam generators in Point Beach Unit I have been subject to c form of corrosion, called intergranular attack, on the steam generator tubes within the long. crevice in the' thick (23 inch)' metal boundary (tubesheet) between the reactor coolant and steam generator water. At times this corrosion has resulted in a crack in a tube itself permitting a leak of reactor coolant into the steam generator. All tubes which have exhibited cracks or significant intergranular attack have been removed from service by plugging. All steam generator tubes are now subject to a periodic inspection program to detect evidence of intergranular attack prior to any evidence of a leak. This problem is not unique to Point Beach Unit 1, but has been observed in a number of nuclear plants of approximately the same age and design, both in this country and abroad.
Decade asserted in its letter to you that " Point Beach Unit 1, which previously experienced the single worst tube rupture of any plant in this country, is also presently experiencing the worst observed rate of continuing tube degradation of any of the nation's nuclear reactors." Neither statement is factually correct. Of course, what is important l l is whether there is any safety significance to a tube rupture l or tube degradation -- whether or not it is the " worst", best, I or somewhere in between. There was no health or safety impact l
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1 The Honorable William Proxmire September 24, 1980 Page 2 i
from the steam generator tube leaks or tube rupture at ' Point Beach. Any radiological releases from steam generator tube leakage was many time below the maximum allowable. Wisconsin Electric, its consultants, and the NRC have considered the safety significance of the steam generator tube degradation problem at Point Beach. Wisconsin Electric has taken certain '
actions with NRC concurrence to insure that Point Beach Unit 1 continues to operate safely while the most effective repair i
program for the steam generators is selected and implemented. '
In its letter to you, Decade engages in a vitriolic attack on the NRC. Decade may be venting its frustration in having failed to convey to the NRC that its position on the steam generator tube degradation problem has any merit. But i again Decade's attack missed the mark by a wide margin. If {
anything, the NRC has become cautious in the extreme since Three Mile Island. Decade's quote from the Kemeny Commission s Report is incomplete--perhaps deliberately so.
In fact, the NRC has been responsive to the steam generator concerns. The NRC Commissioners were formally briefed on the steam generator tube degradation problems at
' Point Beach on two occasions, once by representatives from Decade. Decade raised the safety issues set forth in its letter to you by petitions to the Commission on two separate occasions. After preparing a safety evaluation report, which addressed Decade.'s concerns, the Director, Nuclear Reactor Regulation, rejected Decade's position as unfounded on each occasion. The Director's decision was not overturned by the Commissioners after their review. We should point out that the NRC would have conducte,d its review without Decade's involve-
- ment.
Decade cites a 1975 American Physical Society report in support of its allegations. Again Decade quotes material out of context. The purpose of the American Physical Society
j study was to critique the light water reactor safety program in general and the emergency core cooling system (ECCS) interim acceptance criteria established by the Atomic Energy Commission in particular. The American Physical Society report pointed i out areas where it believed additional research or conservation could be introduced in the ECCS analysis. The question postulated by the American Physical Society deals with a loss-of-coolant accident to the reactor followed by a number of steam generator tube ruptures which in theory could result in restricted flow of emergency cooling to the reactor core. I The principal reason that this concern is not applicable to the situation at Point Beach Unit 1 is fairly
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4 i The Honorable William Proxmire September 24, 1980 Page 3 simple. The postulated problem requires a number of
, " double-ended" breaks of steam generator tubes. The tube degradation at Point Beach occurs within the 23-inch tubesheet.
Thus, a tube break would be physically restrained by the tubesheet, and the postulated double-ended breaks of steam
generator tubes could simply not occur. To demonstrate the integrity of Lne steam generator tubes, on a periodic schedule, the tubes are subjected to a hydrostatic test--a high differential pressure across the tubes approximating the forces :
which might be caused by a loss-of-coolant accident. '
Wisconsin Electric has taken a number of steps to insure the plant is being operated safely notwithstanding the :
steam generator tube problem. The plant is being operated at a
, lower temperature at approximately 804 power level in order to
- inhibit the rate of tube degradation, which appears to be
- related to temperature. The Company is conducting more frequent periodic inspections of all steam generator tubes and is regularly conducting the hydrostatic differential pressure test described above to insure the integrity of the system boundaries. These measures have been approved by the NRC and, i . in some cases, have been confirmed by an NRC Order. Most recent inspections appear to indicate a reduction in the rate of tube degradation.
Decade's complaints that it has not been afforded an
- opportunity for.a hearing on these issues go to the NRC Confirmatory orders confirming the actions taken by Wisconsin Electric. Decade has petitioned for a public hearing regarding these Orders. An Atomic Safety and Licensing Board presently has before it the question of whether, as a matter of law, Decade has a right to such a hearing. The " stinging dissent"
{ by two NRC Commissioners referred to by Decade goes only to the policy question relating to the circumatances as to when a public hearing should be provided. It has nothing to do with the merits of the situation at Point Beach.
Wisconsin Electric has one of the finest operating records of any utility in the country at its Point Beach Nuclear Plant. No one is more interested in the absolute safe operation of the Point Beach Plant than those of us responsible for its opera'lon c and maintenance. The actions that have been taken at Point Beach insure its safe operation until necessary repairs are accomplished.
The Honorable William Proxmire September 24, 1980 Page 4 We appreciate this opportunity to set the fact's straight. We, of course, would be happy to answer any questions that you might have.
Very truly yours,
_ ^D hw tb Exe utive Vice President Sol Burstein cc: Nuclear Regulatory Commission NRC Atomic Safety and Licensing Board Public Service Commission of Wisconsin Wisconsin's Environmental Decade, Inc.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION THE ATOMIC SAFETY AND LICENSING BOARD i
In the Matter of )
)
WISCONSIN ELECTRIC POWER COMPANY ) Docket No. 50-266 CO (Point Beach Nuclear Piant, ) (Modification of License)
Unit 1) )
SERVICE TIST Herbert Grossman, Esq. C. F. Riederer, P. E.
i Chairman Public Service Commission
- Atomic Safety and Licensing Board of Wisconsin l'
U.S. Nuclear Regulatory Commission Hill Farms State Office Washington, D.C. 20555 Building 4802 Sheboygan Avenue '
Dr. Richard F. Cole Madison, Wisconsin 53702 I Atomic Safety and Licensing Board U.S. Nuclear Regulato;y Commssion Kathleen M. Falk, Esquire j Washington, D.C. 20555 Wisconsin's Environmental Decade, Inc. - Suite 205 i
Dr. J. Venn Leeds 302 East Washington Avenue 10807 Atwell Madison, Wisconsin 53703 Houston, Texas 77096 Docketing and Service Section i
Karen D. Cyr, Esquire Office of the Secretary U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory I
Office of the Executive Commission Legal Director Washington, D.C. 20555 Washington, D.C. 20555
, Patrick Walsh, Esquire Assistant Attorney General State of Wisconsin Department of Justice 114 East State Capital Madison, Wisconsin 53702 Ms. Jacqueline K. Reynolds Assistant Secretary to the Commission Public Service Commission of Wisconsin Hill Farms State Office Building 4802 Sheboygan Avenue l Madison, Wisconsin 53702 l
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