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| | -4 SHAW. PITTMAN. PoTTs & TROWBRIDGE DOLKETED a panTNEmSw.m escLUDING PmorESSIONAL CompomATlONS USNRC 2300 N STREET, N. W. |
| | WASHINGTON. D. C. 20037 |
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| | JOMN ENGEL. P C.'. LoutSE a. MATMEwS s c wMITER'S DIRECT DIAL NUM.E R (202) 663-8051 Sheldon J. Wolfe, Chairman Oscar H. Paris Administrative Judge Administrative Judge Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Frederick J. Shon Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of GPU NUCLEAR CORPORATION, et al. |
| | (Steam Generator Plugging Criteria) |
| | Docket Nos. 50-289-OLA-1 and 50-289-OLA-2 |
| | |
| | ==Dear Administrative Judges:== |
| | |
| | Attached for the information of the Board and the parties is a letter dated October 3, 1986 from Licensee to the Staff provid-ing information relevant to Change Request 148. |
| | Sincerely, h0]DO g Bruce W. Churchill Counsel for Licensee Enclosure cc: Service List (attached) b |
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| | i O |
| | DOCKETED USNRC UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 86 0CT 16 P132 B e f o r e t h e A t o m i c S a f e t y a n d L i c e n s i n g B A a-r d rg ; v . , |
| | 00 Cat.ilhu n M "J . :1 Bhl X In the Matter of ) |
| | ) |
| | GPU NUCLEAR CORPORATION, et al. ) Docket Nos. 50-289-OLA-1 |
| | ) 50-289-OLA-2 |
| | ) (Steam Generator (Three Mile Island Nuclear ) Plugging Criteria) |
| | Station, Unit No. 1) ) |
| | SERVICE LIST Sheldon J. Wolfe, Chairman Docketing and Service Section (3) |
| | Administrative Judge U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C. 20555 Board Panel U.S. Nuclear Regulatory Commission Three Mile Island Alert, Inc. |
| | Washington, D.C. 20555 315 Peffer Street Harrisburg, PA 17102 Oscar H. Paris Administrative Judge Thomas Y. Au Atomic Safety and Licensing Assistant Counsel Commonwealth Board Panel of Pennsylvania U.S. Nuclear Regulatory Commission Dept. of Environmental Resources Washington, D.C. 20555 Bureau of Environmental Resources Room 505 Executive House Frederick J. Shon P.O. Box 2357 Administrative Judge Harrisburg, PA 17120 Atomic Safety and Licensing Board Panel Louise Bradford U.S. Nuclear Regulatory Commission Three Mile Island Alert, Inc. |
| | Washington, D.C. 20555 1011 Green Street Harrisburg, PA 17102 Mary E. Wagner, Esq. (2) |
| | Office of Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing Appeal Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 f Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
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| | GPU Nuclear Corporation i Uhl 100 Interpace Parkway I g Parsippany. New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number: |
| | October 3, 1986 5000-86-1050 5211-86-2174 Office of Nuclear Reactor Regulation Attn: J. F. Stolz, Director PhR Projects Directorate No. 6 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 |
| | |
| | ==Dear Mr. Stol:== |
| | Three Mile Island Nuclear Station Unit 1 (DfI-1) |
| | Operating Licensing No. DPR-50 Docket No. 50-289 Regulatory Guide 1.121 Extent of Applicability to OTSG's This letter is a follow-up to prior discussions regarding the applicability of Regulatory Guide 1.121 to Once Through Steam Generators (OTSG's). |
| | The once through steam generators employed on B6W designed plants use a vertical vessel with a straight tube fixed at both a lower and upper tubesheet. Characteristic of this design is that any differential thermal expansion between the tubes and the steam generator shell, during either steady state or transient modes of operation, give rise to axial strain in the tubes and hence axial tube loads. In addition, any pressure differential between the primary and secondary sides can also produce axial loads, although these are always much smaller than the thermal expansion induced loads. The pressure differential on the tubes also produces tube stresses oriented in the circumferential (hoop) direction. All analyses for once through steam generators show that the axial loads are controlling, and where there have been instances of in service cracking, as at Bil, the cracks are circumferential1y oriented as would be expected because of the critical loading (axial) conditions. |
| | In contrast to once through steam generators, recirculation steam generators of the type used in Westinghouse and Combustion Engineering designed plants are vertical shell vessels with a U-tube design in which both inlet and outlet ends of each tube are fixed to a single tubesheet. The tubes are not GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation |
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| | . , . . _ ~. - . |
| | J. F. Stolz, Director October 3, 1986 Page Two j |
| | axially restrained to any significant degree and are free to expand. |
| | Temperature differences between inlet and outlet legs give rise to modest bending moments in the U bends, but no significant axial loads are produced. |
| | The dominant and controlling tube loads, and therefore stresses, are in the hoop direction due to internal pressure. This direction of dominant stress is confirmed in the recirculation steam generators in which observed cracks have been predominantly in the axial direction. |
| | , In summary, both recirculation and once through steam generators have pressure induced tube loading which cause circumferential tube stresses, but 4 |
| | the once through steam generators uniquely have a dominant axial tube load. |
| | The axial tube load, however, is not force or pressure driven but rather thermally driven and hence, self limited. This latter type load is described in the ASME Section III Code as a secondary type stress. For the purposes of reviewing the applicability of Regulatory Guide 1.121 to once through steam generators, the subsequent discussion uses the nomenclature, definitions and |
| | ; underlying methodology contained in the ASME Section III Code. |
| | ASME Code - Primary and Secondary Stresses |
| | 'The ASME Boiler and Pressure Vessel Code, Section III, Subsection NB, provides definitions for the categorization of loads and stresses into primary, secondary and peak stress components. Code allowable stresses are dependent upon the load effects considered (i.e., primary stresses alone or l in combination with secondary stresses) and the frequency of the stress e occurrence. |
| | A thermal stress is classified as a secondary stress and not classified as a primary stress, (NB-3213.8, NB-3213.9). A secondary stress is a normal or shear stress developed by the constraint of adjacent material or by self |
| | , constraint of the structure-(i.e., the thermal induced axial tube load in OTSG's). A basic characteristic of a secondary stress is that it is self l limiting. Local yielding and/or minor strain can relax the loads which l originally caused the stress to occur, and failure from one application of such secondary stresses is not expected. Thermal induced stress (secondary stress) is developed in a solid body (i.e., the composite OTSG shell and fixed tubes) whenever a volume of material is prevented from assuming the i size and shape that it freely should take under a change in temperatere.. |
| | General thermal stress is associated with distortion of the structure in which it occurs (NB-3213.13). |
| | : These Code definitions are applicable to pressure vessels (i.e., OTSG) and j to penetrations. In the application of Regulatory Guide 1.121 to OTSG's, it l 1s not proposed to simply disregard thermal stress as is done in Section XI l |
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| | J. F. Stolz, Director October 3, 1986 Page Three of the Code where, for ductile materials only, primary stresses are considered when performing flow stability evaluations. Rather, we should extract the physical understanding that is the basis for Code guidance. |
| | Conceptually, if a less stiff part of a structure (i.e., tube) is displaced to its yield strength by a more massive part of a structure (i.e., shell), |
| | solely because of there being a temperature difference between them, an increase in stress in the less stiff structure much beyond the yield strength ~will not occur because strain deformation of the less stiff member will bring it into size conformance with the more massive member. With reasonable ductility of materials (metals) usually encountered, parting or other mechanical failure of the less stiff member will not occur. |
| | Regulatory Guide 1.121 Applicability In assessing the integrity of steam generator tubes, with or without flaws, Regulatory Guide 1.121 makes use of margins to be applied to calculated tube loads to assure sufficient conservatism exists in comparing predicted to required tube capacity. These margins are based upon factoring normal loads by 3 and accident loads by 1.428. For recirculation steam generators, these-factors have been applied to pressure effects (a primary load) in assessing repair limits. Since pressure effects are the predominant and critical recirculation generator load, this application of load increase by 3 or 1.428 provides the necessary margin. |
| | For the case of OTSG's, application of Regulatory Guide 1.121 factors is equally appropriate for primary stresses as for recirculation generators. |
| | We show the results of this factor application to OTSG primary stresses in Table 1, attached. Code allowables are never exceeded. Since OTSG's have a significant axial tube load '(stress) which is not a primary but rather a secondary stress, a treatment of this secondary stress in a manner consistent with the underlying development of the Code would not involve application of safety factors to these secondary' stresses. These secondary stresses are more significant in considering fatigue resistance. A Code consistent, and conservative approach is to apply the Regulatory Guide 1.121 margins to strain and determine the new load in recognition of the load redistribution that occurs. This redefined load could then be used in assessing tube failure and the impact of tube flaws. |
| | Summary In summary, we believe Regulatory Guide 1.121 is a technically sound approach when applied to evaluating steam generators with predominant primary stresses. In the case of once through steam generators, meaningful strain-limited or secondary stresses exist. In this latter case, we conclude |
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| | l} |
| | J. F. Stolz, Director October 3, 1986 Page Four that Regulatory Guide 1.121 is not directly applicable in cases where significant secondary stress exists. We believe a proper approach is to put margin on total strain and demonstrate that the component has the capacity to resist the resulting stress and not fail. This approach will ensure a high reliability of tube integrity under all normal and accident loading conditions. |
| | V t! uly yours, |
| | ' F. ic h R. F. Wi son Vice President Technical Functions |
| | /amm Attachment cc: R. Conte J. Thoma , |
| | bcc: J. Peter Paine (EPRI) |
| | J. Lang (EPRI) |
| | T. Gerber (EPRI) |
| | J. Cuvilier (B&W) |
| | B. Churchill (Shaw, Pittman) |
| | ~ |
| | 4 |
| | |
| | y TABLE 1 OTSG TUBING DESIGN BASIS AXIAL STRESSES (based-on unflawed tube) |
| | Maximum Normal Operating Stress Design Basis (DB) 3XDB Sect. III Allow. |
| | Mechanical (I) 6,809 20,427 23,000 (Primary) |
| | Mechanical + Thermal (2) 17,571 52,713 69,000 (Primary + Secondary) |
| | Maximum Accident Stress Design Basis (DB) 1.4280B Sect. III Allow. |
| | Mechanical (3) 8,920 12,666 27,600 (Primary) |
| | Mechanical + Thermal (3) 49,841 No Limit; Evaluation (Primary + Secondary) not required for secondary stresses (1) O to 15% power change (2) Cooldown from 15% power (3) Main steam line break |
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| | 'i GENERAL REFERENCES |
| | : 1. ASME Code - Section III |
| | : 2. Lang, J., F. , et al, Analysis of Leak-Before Break for Steam Generator Tubes, Proceedings-of Third International Topical Meeting on Reactor Thermal Hydraulics, Vol. 2 Sessions 13 -21, C. Chong and G. Brown, Eds, Newport, Rhode Island, October 15-18, 1985. |
| | : 3. Griesbach, T., et al, Analysis Methods for Evaluating Leak-Before-Breaks in U-Tube Steam Generators, Ibid. |
| | : 4. Babcock & Wilcox Topical Report No. BAW-10146, Determination of Minimum Required Tube Wall Thickness for 177-FA Once-Through Steam Generators , Oct.1980. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M0721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Pass Dates ML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L0061999-10-0101 October 1999 Discusses GL 97-06 Issued by NRC on 971231 & Gpu Response for Three Mile Island .Staff Reviewed Response & Found No New Concerns with Condition of SG Internals or with Insp Practices Used to Detect Degradation of SG Internals ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212K8771999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Three Mile Island on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Provides Historical Listing of Plant Issues & Insp Schedule ML20212K8551999-09-30030 September 1999 Informs That During 990921 Telcon Between P Bissett & F Kacinko,Arrangements Were Made for Administration of Licensing Exams at Facility During Wk of 000214.Outlines Should Be Provided to NRC by 991122 ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211A4261999-08-19019 August 1999 Forwards Insp Rept 50-289/99-04 on 990606-0717.Two Severity Level 4 Violations Occurred & Being Treated as Noncited Violations ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210N7601999-08-10010 August 1999 Informs That NRC Staff Reviewed Applications Dtd 990629, Which Requested Review & Approval to Allow Authority to Possess Radioactive Matl Without Unit Distinction Between Units 1 & 2.Forwards RAI Re License Amend Request 285 ML20210N7191999-08-0606 August 1999 Forwards Notice of Partial Denial of Amend to FOL & Opportunity for Hearing Re Proposed Change to TS 3.1.12.3 to Add LCO That Would Allow Continued HPI Operation ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210B8231999-07-21021 July 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) for Three Mile Island Nuclear Station,Unit 2 in Response to Licensee Application Dtd 990309,requesting Reduction in Amount of Insurance for Unit to Amount Listed ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20209H9401999-07-15015 July 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Application for Exemption Dtd 990309. Proposed Exemption Would Reduce Amount of Insurance for Onsite Property Damage Coverage as Listed ML20209G2451999-07-15015 July 1999 Advises That Suppl Info in Support of Proposed License Transfer & Conforming Adminstrative License Amends,Submitted in & Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident ML20216D9861999-07-12012 July 1999 Forwards RAI Re 981019 Application Request for Review & Approval of Operability & SRs for Remote Shutdown Sys. Response Requested within 30 Days of Receipt of Ltr ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209D8451999-07-0808 July 1999 Forwards Insp Rept 50-289/99-06 on 990608-11.No Violations Noted.Overall Performance of ERO Very Good & Demonstrated, with Reasonable Assurance,That Onsite Emergency Plans Adequate & That Util Capable of Implementing Plan ML20209D6291999-07-0808 July 1999 Forwards Notice of Withdrawal & Corrected TS Pages 3-21 & 4-9 for Amend 211 & 4-5a,4-38 & 6-3 for Amend 212,which Was Issued in Error.Amends Failed to Reflect Previously Changes Granted by Amends 203 & 204 ML20209D5141999-07-0808 July 1999 Forwards RAI Re 981019 Application & Suppl ,which Requested Review & Approval of Revised Rc Allowable Dose Equivalent I-131 Activity Limit with Max Dose Equivalent Limit of 1.0 Uci/Gram.Response Requested within 30 Days 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License ML20196J7651999-06-29029 June 1999 Provides Updated Info Re Loss of Feedwater & Loss of Electric Power Accident Analyses to Support TS Change Request 279 Re Core Protection Safety Limit,As Discussed at 990616 Meeting ML20196J7701999-06-29029 June 1999 Forwards LAR 285 for License DPR-50,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20209C0391999-06-29029 June 1999 Forwards LAR 77 to License DPR-73,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-2 License to Amergen,Radioactive Matl May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20196G2061999-06-23023 June 1999 Requests That NRC Update Current Service Lists to Reflect Listed Personnel Changes That Occurred at TMI 05000289/LER-1999-006, Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements1999-06-23023 June 1999 Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements ML20196D2171999-06-17017 June 1999 Forwards Pmpr 99-9, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508- 0604.New Summary Personnel Table Was Added to Rept Period.Matl Scientist Joined Staff Period ML20196A0431999-06-15015 June 1999 Providess Notification That Design Verification Activities Related to Calculations Supporting Analytical Values Identified in Gpu Nuclear Ltr to NRC Has Been Completed 05000289/LER-1999-004, Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT1999-06-0909 June 1999 Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT ML20212K2541999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20212K2671999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20195E2751999-06-0404 June 1999 Informs That PCTs & LOCA Lhr Limits Submitted in Util Ltr for LOCA Reanalysis Performed in Support of TMI-1 20% Tube Plugging Amend Request Have Been Revised.Revised PCT & LOCA Lhr Limit Values Are Provided on Encl Table 1 ML20195E3281999-06-0404 June 1999 Forwards Application for Amend to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20195C5721999-06-0202 June 1999 Forwards Description of Gpu Nuclear Plans for Corrective Actions for 1 H Fire Barriers in Fire Zones AB-FZ-3,AB-FZ-5, AB-FZ-7,FH-FZ-2 & Previous Commitments for Fire Zones CB-FA-1 & FH-FZ-6 ML20207E2561999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Change in ECCS Analyses at TMI-1 ML20195B2461999-05-21021 May 1999 Forwards Itemized Response to NRC 990506 RAI for TS Change Request 279 Re Core Protection Safety Limit ML20206R6461999-05-13013 May 1999 Forwards Rev 39 of Modified Amended Physical Security Plan for TMI 05000289/LER-1999-003, Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC1999-05-0707 May 1999 Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC ML20206K6301999-05-0707 May 1999 Provides Addl Info Re TMI-1 LOFW Accident re-analysis Assumptions for 20% Average SG Tube Plugging as Discussed on 990421 ML20206H0781999-04-30030 April 1999 Forwards Rev 0 to 1092, TMI Emergency Plan. Summary of Changes Encl ML20206J4811999-04-30030 April 1999 Provides Summary of Activities at TMI-2 During First Quarter of 1999.TMI-2 RB Was Not Inspected During Quarter.Routine Radiological Surveys of Auxiliary & Fuel Handling Bldgs Did Not Identify Any Significant Adverse Trends ML20206E4121999-04-27027 April 1999 Requests That TS Change Request 257 Be Withdrawn ML20206C5211999-04-23023 April 1999 Requests Mod to Encl Indemnity Agreement Number B-64,on Behalf of Gpu & Affiliates,Meed,Jcpl,Penelec & Amergen Energy Co,Llc.Ltr Supersedes & Withdraws 990405 Request Submitted to NRC ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 1999-09-09
[Table view] Category:LEGAL/LAW FIRM TO NRC
MONTHYEARML20245D6071989-03-27027 March 1989 Forwards Endorsements 113 & 114 to Nelia Policy NF-220, Endorsements 133 & 134 to Nelia Policy NF-164,Endorsement 143 to Nelia Policy NF-1 & Endorsement 86 to Nelia Policy NF-195 ML20245D3421989-03-20020 March 1989 Forwards Listed Endorsements,Including Endorsements 14,163, 144,94,75,39 & 31 to Nelia Policies NF-295,NF-100,MAELU Policy MF-29,NELIA Policy NF-182,MAELU Policy MF-61,NELIA Policy NF-281 & Maelu Policy MF-112,respectively ML20235T8911989-01-18018 January 1989 Forwards Endorsements 130 & 131 to Nelia Policy NF-164, Endorsements 107 & 108 to Maelu Policy MF-44,Endorsements 94 & 95 to Nelia Policy NF-107,Endorsements 110 & 111 to Nelia Policy NF-220 & Endorsements 97 & 98 to Maelu Policy MF-73 ML20155F3881988-10-0505 October 1988 Forwards Endorsements 108 & 109 to Nelia Policy NF-220 & Endorsements 95 & 96 to Maelu Policy MF-73 ML20155A2501988-06-0303 June 1988 Forwards Endorsements 4 & 4 to Nelia Certificate NW-78 & Maelu Certificate MW-18 & Endorsements 3 & 3 to Nelia Certificate NW-125 & Maelu Certificate MW-46,respectively ML20154K8561988-05-18018 May 1988 Forwards Endorsements 93 & 94 to Maelu Policy MF-73 & Endorsements 106 & 107 to Nelia Policy NF-220 ML20148N5151988-03-30030 March 1988 Forwards Endorsements 1 & 2 to Maelu Certificate MW-46 & Nelia Certificate NW-125 ML20148K1111988-03-22022 March 1988 Forwards Listed Endorsements to Listed Policies,Including Endorsement 102 to Maelu Policy MF-26,Endorsement 123 to Nelia Policy NF-76,Endorsement 71 to Maelu Policy MF-56 & Endorsement 89 to Nelia Policy NF-189 ML20236N8881987-11-0606 November 1987 Forwards Joint Motion for Approval of Settlement Agreement & for Termination of Proceeding,Per Discussions Between Util & NRC in Response to 871002 Order.Svc List Encl ML20236A0041987-10-13013 October 1987 Forwards Usc Comment on Proposed Rule 10CFR50 Re Proposed Rev of Backfitting Process for Power Reactors ML20235J0031987-09-21021 September 1987 Forwards Endorsements 122 & 123 to Nelia Policy NF-164, Endorsements 99 & 100 to Maelu Policy MF-44,Endorsements 100 & 101 to Nelia Policy NF-220 & Endorsements 87 & 88 to Maelu Policy MF-73 ML20236E6991987-07-28028 July 1987 Forwards Consent Motion & Proposed Order & Affidavit of Nondisclosure Agreed to by G Johnson & Jp Hickey by 870728 Telcon.Mod Incorporated Subsequent to 870723 Version Included.Served on 870729 ML20235N7431987-07-0707 July 1987 Forwards Endorsements 98 & 85 to Nelia Policy NF-220 & Maelu Policy MF-73,respectively ML20235D6741987-07-0606 July 1987 Forwards Rev of Recipient Proposed Stipulations to Obviate Need for Appearance of AB Beach as Staff Witness,Per Request.Desire to Explore Subj Expressed.W/O Stated Encl. Service List Encl.Related Correspondence ML20215D6311987-06-11011 June 1987 Requests That NRC Identify,By Name,All Individuals to Whom Request for Admission Number 102 Refers & Identify Basis for Making Such Allegation.Related Correspondence ML20215D6551987-06-11011 June 1987 Forwards Affirmation for Util Partial Response to NRC Staff First Request for Admissions.Certificate of Deponent & Transcript Corrections for J Barton 870407 Deposition Encl. Related Correspondence ML20215J6731987-06-10010 June 1987 Forwards Payment to Meeks Which Represents Allowable Witness Travel & Subsidence Fees.Related Correspondence ML20214R9871987-06-0101 June 1987 Forwards Notice of Deposition of Rd Parks,Inadvertently Omitted from Friday Transmittal.Related Correspondence ML20214S1231987-05-29029 May 1987 Confirms 870528 Conversation Re Agreement to Postpone Beach Deposition,Previously Noticed for 870601,to Enable Further Consideration of Stipulated Testimony Which May Obviate Need for Beach to Appear.W/Svc List.Related Correspondence ML20234F3251987-05-27027 May 1987 Appeals Denial of FOIA Request for Bb Hayes on Individual Operator Actions Re Falsification of Leak Rate Test Data at Facility ML20214E3101987-05-11011 May 1987 Forwards Endorsements 120 & 97 to Nelia Policies NF-164 & NF-220 & Endorsements 97 & 84 to Maelu Policies MF-44 & MF-73,respectively ML20205R4751987-04-0101 April 1987 Informs That R Arnold,B Kanga & J Barton Deposed in 1984 by King Counsel Addressing King Involvement W/Quiltec & Related Info.Depositions Available Upon Request.Related Correspondence ML20212C7991987-02-18018 February 1987 Forwards Endorsements 93 & 81 to Nelia Policy NF-220 & Maelu Policy MF-73,respectively ML20211A0911987-02-16016 February 1987 Advises That Herbein Declines Board Invitation in Request & Order to Comment on Numerous Employees Memorandum of Law Re Inquiry Into TMI-2 Leak Rate Data Falsification ML20214X3211986-11-0505 November 1986 Appeals Denial of FOIA Request for 860912 Memo from Ja Fitzgerald to Ofc of Investigations Re Investigation of Individual Actions Concerning Leak Rate Data Falsification Data at Facility ML20203N8791986-10-14014 October 1986 Forwards Licensee to NRC Re Change Request 148. W/Svc List.Related Correspondence ML20210S8941986-10-0202 October 1986 Forwards MPR Assoc,Inc Providing Estimate of Percentage of Billable Hours Attributable to Work Performed for Util ML20215B5801986-09-30030 September 1986 Forwards Listed Items of Evidence Including Annotated Computer Printouts for Leak Rate Tests 147,146 & 145 on 781018 & Strip Chart Traces Showing Effects of Hydrogen Additions in Instances When Leak Rate Tests Not Performed ML20214R6491986-09-23023 September 1986 Forwards Employees for Witness Hw Hartman Proposed Impeachment Questions,For Info.Requests That Questions Be Withheld from All Parties Prior to Hw Hartman Testimony.W/O Encls.Related Correspondence ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20214P9291986-09-16016 September 1986 Forwards GP Miller Proposed Questions for Eh Stier.W/O Encl. Related Correspondence ML20211C6091986-09-12012 September 1986 FOIA Request for Records Re Investigation Rept on Individual Operator Actions on Falsification of Leak Rate Test Data at TMI-2 and Documentation of Conversations Between NRC & DOJ ML20214M6371986-09-0808 September 1986 Advises of Util Decision Not to File Findings in Response to Proposed Findings of Other Parties.Util 860815 Proposed Findings Stand.Certificate of Svc Encl.Related Correspondence ML20209H6251986-09-0303 September 1986 Forwards Endorsements 91 & 92 to Nelia Policy NF-220 & Endorsements 79 & 80 to Maelu Policy MF-73 ML20203M6841986-08-27027 August 1986 Forwards Proposed Questions of Jg Herbein for D Haverkamp. Jg Herbein Requests That Questions Not Be Provided to D Haverkamp Prior to Appearance Before Board.Related Correspondence ML20203L4601986-08-22022 August 1986 Forwards Prepared Statements of RR Booher,Cl Guthrie & Wh Zewe Re Leak Rate Data Falsification.Related Correspondence ML20203L2021986-08-21021 August 1986 Forwards Prepared Statements of Kr Hoyt,Ba Mehler & Fj Scheimann Re Inquiry Into Leak Rate Data Falsification. Related Correspondence ML20203L2281986-08-20020 August 1986 Lists Proposed Addl Agenda Items for 860825 Prehearing Conference,Including Opening Statements by Parties at Start of Technical & Individual Responsibility Testimonies,Per Request.Related Correspondence ML20205F3861986-08-16016 August 1986 Forwards C Husted Proposed Findings of Fact & Conclusions of Law for Filing in Proceeding.W/O Encl.Related Correspondence ML20205F5801986-08-15015 August 1986 Forwards Employee Prepared Statements.Statements of Booher, Guthrie,Hoyt,Mehler,Scheimann & Zewe Will Be Filed When Available.Time Extension Requested.Certificate of Svc Encl. Related Correspondence ML20205F4261986-08-15015 August 1986 Forwards Proposed Findings of Fact & Conclusions of Law in Form of Recommended Initial Decision.W/Certificate of Svc ML20205F6591986-08-15015 August 1986 Forwards Testimony of GP Miller Re Inquiry Into Facility Leak Rate Data Falsification.Related Correspondence ML20205C2161986-08-0808 August 1986 Informs That JW Garrison & Rs Hutchison Held Position of Shift Foreman/Shift Supervisor During 780930-790328,per ASLB 860801 Memorandum & Order.Related Correspondence ML20204F7941986-07-30030 July 1986 Notifies That on 860729,US District Court for Middle District of State of PA Granted Motion for Suppression of Info Re Inquiry Into Leak Rate Data Falsification.Goldberg Will Advise NRC of Contents of Sealed Order ML20207J6881986-07-25025 July 1986 Forwards Response to Motion to Suppress Re Inquiry Into Facility Leak Rate Data Falsification,Per ASLB 860604 Protective Order.W/O Encl ML20203E5181986-07-22022 July 1986 Informs That Representation Made by Licensee in 860717 Motion for Deferral of Hearing Schedule Re Objection to Proposed Schedule,Premature & Not Formalized by Staff.Staff Will Advance Position in Answer to Motion ML20207J8211986-07-21021 July 1986 Forwards Proposed Employee Questions to Be Put to Stier, Russell,Capra,Rockwell,Kirkpatrick & Wermiel Per Board 860522 Order.W/O Encl.Related Correspondence ML20207E5461986-07-18018 July 1986 Forwards Response to Aamodt 860630 Response to Ofc of Investigations Rept & Motion for Summary Disposition,For Filing in Inquiry Into Leak Rate Data Falsification Proceeding ML20207D9681986-07-18018 July 1986 Forwards Proposed Corrections to Transcript of Evidentiary Hearing Re Gpu.Certificate of Svc Encl ML20207E7721986-07-18018 July 1986 Forwards Husted Proposed Corrections to Transcript of 860623-26 & 0701 Hearings.W/O Encl.Related Correspondence 1989-03-27
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H5351990-09-10010 September 1990 Forwards Encls 1-3 of Generic Ltr 90-07 Re Operator Licensing Exam Schedule ML20059G0641990-08-31031 August 1990 Advises That Util Agreed to Revised Frequency of Once Every 12 Months for Corrective Actions Audits Per Tech Spec Change Request 65 Based on 900718 & 19 Discussions ML20059F1691990-08-30030 August 1990 Requests Exemption from Requirements of 10CFR50,App J, Section III.D.1(a) for Facility Re Schedule Requirements for Connecting Type a Testing w/10-yr Inservice Insp Interval, Per 10CFR50.12(a)(2) ML20064A4661990-08-30030 August 1990 Responds to 900803 SALP Rept 50-289/89-99.TMI Does Not Expect to Be Lead Plant for Installation of Advanced Control Sys.Maint Backlog Goals Established.Info on Emergency Preparedness & Engineering/Technical Support Encl ML20059C8791990-08-29029 August 1990 Forwards TMI-1 Semiannual Effluent & Release Rept for Jan - June 1990, Including Executive Summary of Effluent Release Rept,Disposal & Effluent Release Data & Assessment of Radiation Doses.No Changes to ODCM for Reporting Period ML20059D5491990-08-29029 August 1990 Responds to NRC Re Notice of Violation & Proposed Imposition of Civil Penalty Re Personnel Inattentiveness & Failure of Site Managers to Correct Condition.Shift & Immediate Supervisor Discharged ML20059C7851990-08-27027 August 1990 Forwards Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility, Updating Minor Changes to Pages 6,8,9 & 13 ML20059C1091990-08-24024 August 1990 Forwards Rev 6 to Physical Security Contingency Plan.Rev Withheld ML20059B8251990-08-24024 August 1990 Forwards Payment of Civil Penalty in Amount of $50,000,per NRC ML20056B4651990-08-20020 August 1990 Corrects Statement Made in 900716 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Rosemount Transmitters. Identified That Only Half of Operating Crews Provided W/ Briefing on Bulletin ML20058Q1851990-08-17017 August 1990 Requests That Distribution List for TMI-2 Correspondence Be Updated to Be Consistent W/Recently Implemented Organizational Changes.Ee Kintner,Mb Roche & Wj Marshall Should Be Deleted ML20058Q1721990-08-13013 August 1990 Forwards TMI-2 Effluent & Offsite Dose Rept,First Quarter 1990, Update ML20058Q1821990-08-13013 August 1990 Advises That Util Will No Longer Provide Annual Update to Dewatering Sys for Defueling Canisters Sys Description,Per NRC .W/Completion of Defueling & Shipment of All Defueling Canisters Offsite,Sys Has Been Deactivated ML20058M7201990-08-0303 August 1990 Forwards Rev 2 to TER 3232-019, Div Technical Evaluation Rept for Processed Water Disposal Sys. Mods Include Elimination of Pelletizer & Relocation of Druming Station to Discharge of Blender/Dryer ML20055J4581990-07-27027 July 1990 Responds to Violations Noted in Insp Rept 50-289/90-10. Corrective Actions:Missing Support Brace on Cable Tray Support Found & Corrected ML20055J4561990-07-27027 July 1990 Advises That Info Contained in Generic Ltr 90-06,not Applicable to Current Nonoperating & Defueled Condition of Facility.Generic Ltr Will Be Reevaluated,If Decision Made to Restart Facility ML20055H6901990-07-20020 July 1990 Forwards Rev 25 to TMI-2 Organization Plan for NRC Review & Approval.Rev Proposes Consolidation of Plant Operations & Maint Sections Into Plant Operation & Maint Section ML20055G4431990-07-19019 July 1990 Forwards Rev 12 to 990-1745, TMI-1 Fire Hazards Analysis Rept & Update 9 to FSAR for TMI-1 ML20055G8781990-07-19019 July 1990 Discusses Compliance W/Reg Guide 1.97 Re Containment High Range Radiation Monitors,Per 900507-11 Insp.Physical Separation of Power Cables & Required Isolation Will Be Provided to Satisfy Reg Guide Category 1 Requirements ML20055F9601990-07-11011 July 1990 Forwards, 1990 TMI Nuclear Station Annual Emergency Exercise Scenario to Be Conducted on 900912.W/o Encl ML20044A9531990-07-0909 July 1990 Forwards Util Response to Weaknesses Identified in Maint Team Insp Rept 50-289/89-82.Corrective Actions:Engineering Personnel Reminded to Assure Documented Approval Obtained Prior to Proceeding W/Work ML20055E0481990-07-0505 July 1990 Documents Action Taken by Util to Improve Heat Sink Protection Sys & Current Status of Sys.Main Feedwater Logic Circuits Modified Prior to Startup from 8R Outage to Eliminate Potential for Inadvertent Isolation ML20055E0011990-07-0202 July 1990 Forwards Revs 1 & 2 to Topical Rept 067, TMI-1 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.5.4 ML20055C9971990-06-28028 June 1990 Forwards Rev 27 to Physical Security Plan.Rev Withheld ML20055D2071990-06-28028 June 1990 Forwards Certification of TMI-1 Simulation Facility,Per 10CFR55.45.b.5.Resumes of Personnel Involved Encl. Resumes Withheld (Ref 10CFR2.790(a)(6)) ML20055D0861990-06-25025 June 1990 Documents Deviation from Requirements of Reg Guide 1.97,per Insp on 900507-11.Based on Most Limiting Analysis,Existing Range of 0-1,200 Psi Sufficient.Deviation Consistent W/B&W Owners Group Task Force Evaluation of Reg Guide ML20043H4851990-06-18018 June 1990 Forwards Application for Amend to License DPR-50,consisting of Tech Spec Change Request 179 ML20043H4031990-06-18018 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements or Corrective Actions. ML20043F9921990-06-11011 June 1990 Forwards Listing of Exam Ref Matl Sent on 900601 in Response to 900505 Ltr ML20043F0661990-06-0404 June 1990 Forwards Inservice Insp Data Rept for Period 880816-900304. Owner Rept for Repairs or Replacements Performed on ASME Section XI Class 1 & 2 Components,Also Encl ML20055C9041990-05-23023 May 1990 Advises That App a to Rept Is Set of Recommendations from Safety Advisory Board on Possible Research Opportunities ML20043B2391990-05-18018 May 1990 Revises Commitments in Encl Met Ed 800430 Ltr Re QA of Diesel Generator Fuel Oil.Requirement for QC Review for Acceptability Prior to Filling Diesel Generator Fuel Oil Storage Tanks Deleted from Procedure ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5311990-05-15015 May 1990 Responds to Violations Noted in Insp Rept 50-289/89-82. Corrective Actions:Periodic Insp Program Established Utilizing Checklist for Stored Equipment & Existing Tool Rooms Will Be Purged of Controlled or Unneeded Matls ML20043A2321990-05-11011 May 1990 Forwards TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5) Technical Rept 069.Evaluations Conclude That Test & Insp Results Demonstrate TMI-1 Reactor Bldg post- Tensioning Sys in Good Condition ML20042G2741990-05-0404 May 1990 Forwards Semiannual Update of Projects Listed in Categories A,B & C of long-range Planning Program Integrated Schedule ML20012F2621990-04-0202 April 1990 Responds to Violation Noted in Insp Rept 50-289/89-26. Corrective Actions:Util Policy of Shift Supervisor Involvement in Bypassing & Resetting Safety Sys Expanded to Include Shutdown Conditions & Technicians Briefed ML20012F2611990-04-0202 April 1990 Provides Supplemental Response to Station Blackout Rule. Target Reliability of 0.975 Chosen for Emergency Diesel Generators.Diesel Generator Reliability Program May Change Based on Final Resolution of Generic Issue B-56 ML20012F2731990-03-30030 March 1990 Confirms 900328 Conversations & Provides Technical Basis for Planned Actions to Correct Present Power Limitation Due to High Steam Generator Secondary Side Differential Pressure. Main Turbine Will Be Tripped from 80% Power ML20042D8281990-03-23023 March 1990 Fulfills Requirements of Tech Spec Section 4.19.5.a Re once-through Steam Generator Tubes post-inservice Insp Rept for Unscheduled Outage 8U-1 ML20012D7001990-03-22022 March 1990 Forwards Util Response to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Site Mgt & Staff Hour Categories Added to Response ML20012D7121990-03-21021 March 1990 Forwards Rev 0 to TMI-1 Cycle 8 Core Operating Limits Rept. ML20012C4771990-03-12012 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f). Current Design Adequate W/O Addl Tech Specs ML20012B8241990-03-12012 March 1990 Forwards Application for Tech Spec Change Request 199 to License DPR-50,revising Tech Specs Re Steam Generator Tube Insp Requirements ML20055C3931990-02-23023 February 1990 Documents Interpretation of Tech Spec 4.19.5.a Re once- Through Steam Generator Tube post-inservice Insp Rept for Refueling Interval 8R.Total of Eight Tubes Removed from Svc by Plugging ML20011F5251990-02-23023 February 1990 Documents Interpretation of Tech Spec 5.3.1.1 Re Design Features of Fuel Assemblies in Light of Issuance of Generic Ltr 90-02.Tech Spec Change Request Re Utilization of Dummy Fuel Rods or Open Water Channels Will Be Filed by 900420 ML20011F6651990-02-22022 February 1990 Forwards Updated Status Summary of Consideration of TMI-1 PRA Recommendations as of 891231.Changes to Torque Switch Settings for DH-V-4A & B Will Be Implemented in Refueling Outage 8 Re Closing Against High Differential Pressure ML20006C2901990-01-26026 January 1990 Provides Addl Info Supporting Deferral of Seismic Qualification Util Group Walkdowns to 10R Outage.Performance of Walkdowns Provide Proper Scheduling & Priority for Resolution of USI A-46 for TMI-1 ML20011E1221990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Audit Rept Determined That Operation of Decay Heat Closed Cooling Water Sys Consistent W/Design Basis Documents ML19354E8601990-01-25025 January 1990 Requests Approval for Use of B&W Steam Generator Plugs Mfg W/Alternate Matl (nickel-base Alloy/Alloy 600).Alloy 600 Has Superior Corrosion Resistance to Primary Water Stress Corrosion Cracking 1990-09-10
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JOMN ENGEL. P C.'. LoutSE a. MATMEwS s c wMITER'S DIRECT DIAL NUM.E R (202) 663-8051 Sheldon J. Wolfe, Chairman Oscar H. Paris Administrative Judge Administrative Judge Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Frederick J. Shon Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of GPU NUCLEAR CORPORATION, et al.
(Steam Generator Plugging Criteria)
Docket Nos. 50-289-OLA-1 and 50-289-OLA-2
Dear Administrative Judges:
Attached for the information of the Board and the parties is a letter dated October 3, 1986 from Licensee to the Staff provid-ing information relevant to Change Request 148.
Sincerely, h0]DO g Bruce W. Churchill Counsel for Licensee Enclosure cc: Service List (attached) b
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DOCKETED USNRC UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 86 0CT 16 P132 B e f o r e t h e A t o m i c S a f e t y a n d L i c e n s i n g B A a-r d rg ; v . ,
00 Cat.ilhu n M "J . :1 Bhl X In the Matter of )
)
GPU NUCLEAR CORPORATION, et al. ) Docket Nos. 50-289-OLA-1
) 50-289-OLA-2
) (Steam Generator (Three Mile Island Nuclear ) Plugging Criteria)
Station, Unit No. 1) )
SERVICE LIST Sheldon J. Wolfe, Chairman Docketing and Service Section (3)
Administrative Judge U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C. 20555 Board Panel U.S. Nuclear Regulatory Commission Three Mile Island Alert, Inc.
Washington, D.C. 20555 315 Peffer Street Harrisburg, PA 17102 Oscar H. Paris Administrative Judge Thomas Y. Au Atomic Safety and Licensing Assistant Counsel Commonwealth Board Panel of Pennsylvania U.S. Nuclear Regulatory Commission Dept. of Environmental Resources Washington, D.C. 20555 Bureau of Environmental Resources Room 505 Executive House Frederick J. Shon P.O. Box 2357 Administrative Judge Harrisburg, PA 17120 Atomic Safety and Licensing Board Panel Louise Bradford U.S. Nuclear Regulatory Commission Three Mile Island Alert, Inc.
Washington, D.C. 20555 1011 Green Street Harrisburg, PA 17102 Mary E. Wagner, Esq. (2)
Office of Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing Appeal Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 f Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555
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GPU Nuclear Corporation i Uhl 100 Interpace Parkway I g Parsippany. New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
October 3, 1986 5000-86-1050 5211-86-2174 Office of Nuclear Reactor Regulation Attn: J. F. Stolz, Director PhR Projects Directorate No. 6 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stol:
Three Mile Island Nuclear Station Unit 1 (DfI-1)
Operating Licensing No. DPR-50 Docket No. 50-289 Regulatory Guide 1.121 Extent of Applicability to OTSG's This letter is a follow-up to prior discussions regarding the applicability of Regulatory Guide 1.121 to Once Through Steam Generators (OTSG's).
The once through steam generators employed on B6W designed plants use a vertical vessel with a straight tube fixed at both a lower and upper tubesheet. Characteristic of this design is that any differential thermal expansion between the tubes and the steam generator shell, during either steady state or transient modes of operation, give rise to axial strain in the tubes and hence axial tube loads. In addition, any pressure differential between the primary and secondary sides can also produce axial loads, although these are always much smaller than the thermal expansion induced loads. The pressure differential on the tubes also produces tube stresses oriented in the circumferential (hoop) direction. All analyses for once through steam generators show that the axial loads are controlling, and where there have been instances of in service cracking, as at Bil, the cracks are circumferential1y oriented as would be expected because of the critical loading (axial) conditions.
In contrast to once through steam generators, recirculation steam generators of the type used in Westinghouse and Combustion Engineering designed plants are vertical shell vessels with a U-tube design in which both inlet and outlet ends of each tube are fixed to a single tubesheet. The tubes are not GPU Nuclear Corporation is a subsidiary of the General Pubhc Utilities Corporation
. , . . _ ~. - .
J. F. Stolz, Director October 3, 1986 Page Two j
axially restrained to any significant degree and are free to expand.
Temperature differences between inlet and outlet legs give rise to modest bending moments in the U bends, but no significant axial loads are produced.
The dominant and controlling tube loads, and therefore stresses, are in the hoop direction due to internal pressure. This direction of dominant stress is confirmed in the recirculation steam generators in which observed cracks have been predominantly in the axial direction.
, In summary, both recirculation and once through steam generators have pressure induced tube loading which cause circumferential tube stresses, but 4
the once through steam generators uniquely have a dominant axial tube load.
The axial tube load, however, is not force or pressure driven but rather thermally driven and hence, self limited. This latter type load is described in the ASME Section III Code as a secondary type stress. For the purposes of reviewing the applicability of Regulatory Guide 1.121 to once through steam generators, the subsequent discussion uses the nomenclature, definitions and
- underlying methodology contained in the ASME Section III Code.
ASME Code - Primary and Secondary Stresses
'The ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, provides definitions for the categorization of loads and stresses into primary, secondary and peak stress components. Code allowable stresses are dependent upon the load effects considered (i.e., primary stresses alone or l in combination with secondary stresses) and the frequency of the stress e occurrence.
A thermal stress is classified as a secondary stress and not classified as a primary stress, (NB-3213.8, NB-3213.9). A secondary stress is a normal or shear stress developed by the constraint of adjacent material or by self
, constraint of the structure-(i.e., the thermal induced axial tube load in OTSG's). A basic characteristic of a secondary stress is that it is self l limiting. Local yielding and/or minor strain can relax the loads which l originally caused the stress to occur, and failure from one application of such secondary stresses is not expected. Thermal induced stress (secondary stress) is developed in a solid body (i.e., the composite OTSG shell and fixed tubes) whenever a volume of material is prevented from assuming the i size and shape that it freely should take under a change in temperatere..
General thermal stress is associated with distortion of the structure in which it occurs (NB-3213.13).
- These Code definitions are applicable to pressure vessels (i.e., OTSG) and j to penetrations. In the application of Regulatory Guide 1.121 to OTSG's, it l 1s not proposed to simply disregard thermal stress as is done in Section XI l
l
a
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J. F. Stolz, Director October 3, 1986 Page Three of the Code where, for ductile materials only, primary stresses are considered when performing flow stability evaluations. Rather, we should extract the physical understanding that is the basis for Code guidance.
Conceptually, if a less stiff part of a structure (i.e., tube) is displaced to its yield strength by a more massive part of a structure (i.e., shell),
solely because of there being a temperature difference between them, an increase in stress in the less stiff structure much beyond the yield strength ~will not occur because strain deformation of the less stiff member will bring it into size conformance with the more massive member. With reasonable ductility of materials (metals) usually encountered, parting or other mechanical failure of the less stiff member will not occur.
Regulatory Guide 1.121 Applicability In assessing the integrity of steam generator tubes, with or without flaws, Regulatory Guide 1.121 makes use of margins to be applied to calculated tube loads to assure sufficient conservatism exists in comparing predicted to required tube capacity. These margins are based upon factoring normal loads by 3 and accident loads by 1.428. For recirculation steam generators, these-factors have been applied to pressure effects (a primary load) in assessing repair limits. Since pressure effects are the predominant and critical recirculation generator load, this application of load increase by 3 or 1.428 provides the necessary margin.
For the case of OTSG's, application of Regulatory Guide 1.121 factors is equally appropriate for primary stresses as for recirculation generators.
We show the results of this factor application to OTSG primary stresses in Table 1, attached. Code allowables are never exceeded. Since OTSG's have a significant axial tube load '(stress) which is not a primary but rather a secondary stress, a treatment of this secondary stress in a manner consistent with the underlying development of the Code would not involve application of safety factors to these secondary' stresses. These secondary stresses are more significant in considering fatigue resistance. A Code consistent, and conservative approach is to apply the Regulatory Guide 1.121 margins to strain and determine the new load in recognition of the load redistribution that occurs. This redefined load could then be used in assessing tube failure and the impact of tube flaws.
Summary In summary, we believe Regulatory Guide 1.121 is a technically sound approach when applied to evaluating steam generators with predominant primary stresses. In the case of once through steam generators, meaningful strain-limited or secondary stresses exist. In this latter case, we conclude
l}
J. F. Stolz, Director October 3, 1986 Page Four that Regulatory Guide 1.121 is not directly applicable in cases where significant secondary stress exists. We believe a proper approach is to put margin on total strain and demonstrate that the component has the capacity to resist the resulting stress and not fail. This approach will ensure a high reliability of tube integrity under all normal and accident loading conditions.
V t! uly yours,
' F. ic h R. F. Wi son Vice President Technical Functions
/amm Attachment cc: R. Conte J. Thoma ,
bcc: J. Peter Paine (EPRI)
J. Lang (EPRI)
T. Gerber (EPRI)
J. Cuvilier (B&W)
B. Churchill (Shaw, Pittman)
~
4
y TABLE 1 OTSG TUBING DESIGN BASIS AXIAL STRESSES (based-on unflawed tube)
Maximum Normal Operating Stress Design Basis (DB) 3XDB Sect. III Allow.
Mechanical (I) 6,809 20,427 23,000 (Primary)
Mechanical + Thermal (2) 17,571 52,713 69,000 (Primary + Secondary)
Maximum Accident Stress Design Basis (DB) 1.4280B Sect. III Allow.
Mechanical (3) 8,920 12,666 27,600 (Primary)
Mechanical + Thermal (3) 49,841 No Limit; Evaluation (Primary + Secondary) not required for secondary stresses (1) O to 15% power change (2) Cooldown from 15% power (3) Main steam line break
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'i GENERAL REFERENCES
- 1. ASME Code - Section III
- 2. Lang, J., F. , et al, Analysis of Leak-Before Break for Steam Generator Tubes, Proceedings-of Third International Topical Meeting on Reactor Thermal Hydraulics, Vol. 2 Sessions 13 -21, C. Chong and G. Brown, Eds, Newport, Rhode Island, October 15-18, 1985.
- 3. Griesbach, T., et al, Analysis Methods for Evaluating Leak-Before-Breaks in U-Tube Steam Generators, Ibid.
- 4. Babcock & Wilcox Topical Report No. BAW-10146, Determination of Minimum Required Tube Wall Thickness for 177-FA Once-Through Steam Generators , Oct.1980.
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