Similar Documents at Maine Yankee |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20196K4821999-07-0606 July 1999 Safety Evaluation Concluding That Because of Permanently Shutdown & Defueled Status of Myaps Facility,Confirmatory Orders No Longer Necessary for Safe Operation or Maint of Plant ML20206H1611999-05-0505 May 1999 Safety Evaluation Supporting Amend 164 to License DPR-36 ML20206G5731999-05-0303 May 1999 Safety Evaluation Supporting Amend 163 to License DPR-36 ML20205D5261999-03-26026 March 1999 SER Accepting Util Rev 1 to CFH Training & Retraining Program for Maine Yankee.Rev 1 to CFH Training & Retraining Program Consistent with Current Licensing Practice for Facilities Undergoing Decommissioning ML20204C4631999-03-16016 March 1999 Safety Evaluation Supporting Amend 162 to License DPR-36 ML20197C8231998-09-0303 September 1998 Safety Evaluation Supporting Request for Exemption from Certain Requirements of 10CFR50.54(q),10CFR50.47(b) & (C) & App E to 10CFR50 Re Emergency Planning ML20236U8451998-07-24024 July 1998 Safety Evaluation Accepting Rev 14 to Maine Yankee Atomic Power Co Operational QA Program ML20217H5241998-03-30030 March 1998 Safety Evaluation Supporting Amend 161 to License DPR-36 ML20202D3181997-11-26026 November 1997 Safety Evaluation Supporting Amend 160 to License DPR-36 ML20216F1511997-08-0808 August 1997 Safety Evaluation Supporting Amend 159 to License DPR-36 ML20141G6511997-05-19019 May 1997 Safety Evaluation Supporting Amend 158 to License DPR-36 ML20138G3541997-05-0202 May 1997 Safety Evaluation Supporting Amend 157 to License DPR-36 ML20058E2641993-11-0505 November 1993 Safety Evaluation Supporting Amend 143 to License DPR-36 ML20056F7831993-08-23023 August 1993 Safety Evaluation Supporting Amend 142 to License DPR-36 ML20127D5061993-01-11011 January 1993 Safety Evaluation Supporting Amend 136 to License DPR-36 ML20126H6211992-12-29029 December 1992 Safety Evaluation Supporting Amend 135 to License DPR-36 ML20059K9991990-09-20020 September 1990 SER Accepting Methodology Re Statistical Combination of Uncertainties for RPS Setpoints ML20059H5901990-09-12012 September 1990 Safety Evaluation Re Facility Response to Station Blackout Rule.Issue of Conformance to Station Blackout Rule Will Remain Open at Facility Until Identified Nonconformances Resolved ML20059D0501990-08-30030 August 1990 Safety Evaluation Supporting Amend 117 to License DPR-36 ML20055C2911990-02-20020 February 1990 Safety Evaluation Accepting Util Assessment of Asymmetric LOCA Loads Problem ML20246F6281989-07-10010 July 1989 Safety Evaluation Supporting Amend 113 to License DPR-36 ML20245J0571989-04-25025 April 1989 SER Re Accepting Facility Emergency Response Capability in Conformance to Reg Guide 1.97,Rev 3,w/exception of Instrumentation Re Variables Accumulator Tank Level & Pressure & Containment Sump Water Temp ML20245D4481989-04-24024 April 1989 Safety Evaluation Supporting Amend 111 to License DPR-36 ML20245D4351989-04-24024 April 1989 Safety Evaluation Supporting Amend 112 to License DPR-36 ML20155B4631988-09-27027 September 1988 Safety Evaluation Supporting Amend 107 to License DPR-36 ML20154A1411988-09-0707 September 1988 Safety Evaluation Supporting Amend 106 to License DPR-36 ML20150D7681988-07-0707 July 1988 Safety Evaluation Approving Util Inadequate Core Cooling Instrumentation Sys Contingent on Completion of Emergency Procedures & Operator Training & Submittal of Applicable Tech Specs ML20153A9641988-06-28028 June 1988 Safety Evaluation Accepting Util Proposed Reflood Steam Cooling Model ML20196G6871988-06-23023 June 1988 Safety Evaluation Supporting Amend 105 to License DPR-36 ML20151W5861988-04-26026 April 1988 Safety Evaluation Supporting Amend 104 to License DPR-36 ML20153B3381988-03-16016 March 1988 Safety Evaluation Supporting Util 831110,840216,0412,1214, 850618 & 0820 Responses to Generic Ltr 83-28,Item 2.2.2, Based on Stated Util Commitments,Insp Rept 50-309/86-07 & Actions Described in Procedure for Vendor Interface ML20149H2831988-02-17017 February 1988 Safety Evaluation Supporting Amend 103 to License DPR-36 ML20196C4301988-02-0909 February 1988 Safety Evaluation Supporting Amend 102 to License DPR-36 ML20235M4661987-09-29029 September 1987 Safety Evaluation Supporting Amend 101 to License DPR-36 ML20236F6441987-07-29029 July 1987 Safety Evaluation Supporting Util Response to Item 2.1 of Generic Ltr 83-28 ML20234B1781987-06-25025 June 1987 Safety Evaluation Supporting Amend 100 to License DPR-36 ML20216J0371987-06-25025 June 1987 Safety Evaluation Supporting Amend 99 to License DPR-36 ML20215E9301987-06-15015 June 1987 Safety Evaluation Supporting Amend 98 to License DPR-36 ML20214W3841987-06-0404 June 1987 SER Supporting Util 831110 Response to Generic Ltr 83-28, Item 2.2 (Part 1) Re Requirement for Program Description to Ensure All Components of safety-related Sys Identified as safety-related on Informational Matls ML20214M1491987-05-21021 May 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 2) Re Established Interface W/Nsss or Vendors of Each Component of Reactor Trip Sys ML20214J6001987-05-20020 May 1987 Safety Evaluation Supporting Amend 97 to License DPR-36 ML20210C6631987-04-23023 April 1987 Safety Evaluation Re Adequacy of Offsite Power Sys.Further Evaluation Cannot Continue Until All Requested Info Received.Surowiec Line Not Acceptable Substitute for Mason Line During Startup or Normal Operations ML20206U9231987-04-0909 April 1987 Safety Evaluation Supporting Amend 96 to License DPR-36 ML20197D4421987-04-0707 April 1987 Safety Evaluation Supporting 850807 Request for Relief from ASME Code,Section XI Inservice Testing Requirements for Pump & Valves ML20205M6391987-03-26026 March 1987 Safety Evaluation Accepting Upgraded Seismic Design Program Contingent on Licensee Commitment to Upgrade Items in Table 3 ML20197D4241987-03-26026 March 1987 Safety Evaluation Supporting Amend 94 to License DPR-36 ML20212N7091987-03-0404 March 1987 Safety Evaluation Supporting Amend 93 to License DPR-36 ML20211G4361987-02-14014 February 1987 Safety Evaluation Supporting Util 831110 Response to Generic Ltr 83-28,Item 4.5.2 Re on-line Testing for Reactor Trip Sys Reliability ML20210V1831987-02-0909 February 1987 Safety Evaluation Supporting Amend 92 to License DPR-36 ML20207N2181987-01-12012 January 1987 Safety Evaluation Supporting Util Response to NRC 860721 Request for Addl Info Re Reactor Coolant Pump Shaft Integrity,Per IE Info Notice 86-019 1999-07-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211M4841999-08-31031 August 1999 Replacement Pages 2-48,2-49 & 2-50 to Rev 14 of Defueled Sar ML20211D7111999-08-0909 August 1999 Rev 17 to Maine Yankee Defueled Safety Analysis Rept (Dsar) ML20196K4821999-07-0606 July 1999 Safety Evaluation Concluding That Because of Permanently Shutdown & Defueled Status of Myaps Facility,Confirmatory Orders No Longer Necessary for Safe Operation or Maint of Plant ML20206H1611999-05-0505 May 1999 Safety Evaluation Supporting Amend 164 to License DPR-36 ML20206G5731999-05-0303 May 1999 Safety Evaluation Supporting Amend 163 to License DPR-36 ML20205D5261999-03-26026 March 1999 SER Accepting Util Rev 1 to CFH Training & Retraining Program for Maine Yankee.Rev 1 to CFH Training & Retraining Program Consistent with Current Licensing Practice for Facilities Undergoing Decommissioning ML20204C4631999-03-16016 March 1999 Safety Evaluation Supporting Amend 162 to License DPR-36 ML20206D7491998-12-31031 December 1998 Co Annual Financial Rept for 1998. with ML20155G9591998-11-0303 November 1998 Rev 1 to Post-Shutdown Decommissioning Activities Rept ML20155D8651998-10-28028 October 1998 Public Version of, Maine Yankee Emergency Preparedness Exercise ML20197C8231998-09-0303 September 1998 Safety Evaluation Supporting Request for Exemption from Certain Requirements of 10CFR50.54(q),10CFR50.47(b) & (C) & App E to 10CFR50 Re Emergency Planning ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X1751998-08-0303 August 1998 Rev 16 to Defueled Sar ML20236U8451998-07-24024 July 1998 Safety Evaluation Accepting Rev 14 to Maine Yankee Atomic Power Co Operational QA Program ML20248D3011998-05-26026 May 1998 Rev 14,page 16 of 17,Section II of QA Program ML20247J0211998-05-11011 May 1998 Revised Page 16 of 17 of Section II of QA Program,Rev 14 ML20247D3451998-05-0606 May 1998 Rev 15 to Defueled SAR, Replacing List of Effective Pages ML20217J9811998-04-28028 April 1998 Part 21 Rept Re Incorrect Description of Drift Specification for Model 1154,gauge Pressure Transmitters,Range Code 0 in Manual Man 4514,Dec 1992.Cause Indeterminate.Will Issue & Include Errata Sheets in All Future Shipments to Users ML20217H5241998-03-30030 March 1998 Safety Evaluation Supporting Amend 161 to License DPR-36 ML20217D9691998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Maine Yankee.W/ ML20216D7681998-02-25025 February 1998 Rept to Duke Engineering & Services,Inc,On Allegations of Willfulness Related to Us NRC 971219 Demand for Info ML20203A3011998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Maine Yankee ML20202F3771998-01-31031 January 1998 Annual Rept of Facility Changes & Relief & Safety Valve Failures & Challenges ML20202E0541998-01-30030 January 1998 Rev 14 to Myaps Defueled Safety Analysis Rept ML20199K3211998-01-27027 January 1998 Rev 13 to Maine Yankee Atomic Power Co,Qa Program ML20199K3471998-01-22022 January 1998 Rev 14 to Maine Yankee Atomic Power Co QA Program ML20199C2281997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Maine Yankee ML20217R2301997-12-31031 December 1997 Myap Annual Financial Rept for 1997 ML20203F8551997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Maine Yankee ML20202D3181997-11-26026 November 1997 Safety Evaluation Supporting Amend 160 to License DPR-36 ML20198R6371997-11-0606 November 1997 Yankee Mutual Assistance Agreement ML20155G9511997-10-31031 October 1997 Rev 1 to M01-1258-002, Decommissioning Cost Analysis for Myaps ML20198P9431997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Maine Yankee ML20217K5191997-10-24024 October 1997 Part 21 Rept Re Five Valves That May Have Defect Related to Possible Crack within Forging Wall at Die Flash Line.Caused by Less than Optimal Forging Temperatures.Newer Temperature Monitoring Devices at Forging Area Heating Ovens Procured ML20211N0571997-10-0707 October 1997 Revised Pages to Jul/Aug 1994 SG Insp Summary Rept ML20198K0201997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Maine Yankee ML20199H1861997-09-25025 September 1997 Rev 12 to Maine Yankee Atomic Power Co,Qa Program ML20217A9251997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Maine Yankee ML20217R1051997-08-27027 August 1997 Myaps Post Shutdown Decommissioning Activities Rept ML20216F1511997-08-0808 August 1997 Safety Evaluation Supporting Amend 159 to License DPR-36 ML20210M4451997-07-31031 July 1997 Monthly Operating Rept for July 1997 for Myaps ML20151M1351997-07-21021 July 1997 Rev 0 to Technical Evaluation 172-97, Cable Separation Safety Assessment Rept ML20141H2691997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Maine Yankee ML20141B9951997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Maine Yankee.W/ ML20141G6511997-05-19019 May 1997 Safety Evaluation Supporting Amend 158 to License DPR-36 ML20138G3541997-05-0202 May 1997 Safety Evaluation Supporting Amend 157 to License DPR-36 ML20141G2871997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Maine Yankee ML20137Z1971997-04-14014 April 1997 Forwards to Commission Results of Staff Evaluation of Performance of Licensees W/Ownership Structure Similar to Plant ML20137N7541997-03-31031 March 1997 Rev 11 to Operational Quality Assurance Program ML20138B1491997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Maine Yankee 1999-08-09
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JAN 171960 MEMORANDUM FOR: R. Reid, Chief, Operating Reactors Branch #4, 00R FROM: G. Lainas, Chief, Plant Systems Branch, 00R
SUBJECT:
MAINE YANKEE STEAM GENERATOR WATER HAMMER EVALUATION Plant Name: Maine Yankee Atomic Power Station Docket No.: 50-309 Responsible Branch: ORB #4
, Project Manager: M. Fairtile Reviewing Brancn: Plant Systems Branch Review Status: Complete In response to Technical Assistance Request, TAC No. 7191, regarding water hammer in the Maine Yankee feedwater systems, the Plant Systems Branch has completed its review and found that acceptable precautions are being taken to minimize the occurrence of water hammer in the feedwater piping. The basis for our conclusions are provided in the enclosed Safety Evaluation Report and our consultants' report dated December 1979.
This completes our review of steam generator water hammer under TAC No. 7191.
. M G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Enclosures:
As stated
Contact:
S. MacKay X-27111 cc w/ enclosures:
See page 2 800s;anjfl ,
JAN 171980 cc w/ enclosures:
D. Eisennut
- 5. Hanauer B. Grimes
- E. Adensam W. Gannill M. Fairtile S. MacKay
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SAFETY EVALUATION REPORT 1
STEAM GENEPATOR WATER HAMMER MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-3C9 DECEMBER 1979 1
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1.0 INTRODUCTION
Steam generator water hammer has occurred in certain nuclear power plants as a result of the rapid condensation of steam in a steam generator feedwater line and the consequent acceler' tion of a slug of water which upon impact within the piping system causes undue stresses in the piping and its support system. The significance of these events varies from plant to plant. Since a total loss of feedwater could affect the ability of the plant to cool down after a reactor shutdown, the NRC is concerned about these events occurring, even though an event with potentially serious consequences is unlikely to happen.
Because of the continuing occurrence of water hammer events, the NRC, in September 1977, informed all PWR licensees that water hammer events due to the rapid condensation of steam in the feedwater lines of steam generators represented a safety concern and that further actions by licensees for Westinghouse and Combustion Engineering designed nuclear I steam supply systems are warranted to assure that an acceptably low risk to public safety due to such events is maintained. Accordingly, these ,
licensees were requested to submit proposed hardware and/or procedural l modifications, if any, which would be necessary to assure that the feedwater lines and feedrings remain filled with water during nomal as well as transient operating conditions. At the same time, the NRC ,
1 provided each PWR licensee with a copy of its consultant's report, "An Evaluation of PWR Steam Generator Water Hamer," NUREG-0291.
a
-2 The evaluation of the potential for steam generator water hammer at the Maine Yankee plant shows that the feedwater piping adjacent ,to the steam generator consists of a favoraoly short run of horizontal' piping and' I
that during seven years of successful operation it has experienced those conditions that might induce steam genera +ar water hammer; but no water hanner has occurred.
2.0 EVALUATION Our consultant EG&G Idaho Inc., prepared the attached evaluation of steam generator water harter at the Maine Yankee Plant as part of our technical assistance program. (Letter from J.A. Cearien, EG&G, to R.E. Tiller, 00E, dated Cecember 13, 1979.) We have reviewed this report together with the licensees submittals listed under item 4.0, 3.0 CO.';CtUS ION Based on our knowledge of water hammer phenomena, and our review of the licensees responses and the enclosed evaluation report, we concur with our consultants' conclusien that the potential for steam generator water hammer is sufficiently low to perm,it continued operation of this
. facil ity. However, even though steam generator water hamer is not likely to occur, the licensee should be vigilant and nonitor for water hanners that might impose significant stresses on the piping systems or their supports. We will continue to monitor reports from this licenses for indications of possible water hammer. If i
such indications appear in the future, this matter will be reexamined and any result in additional requirements to reduce /'
the probabflity of steam generator water hanmer at these facilities.
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We have concluded that steam generator water hammer is not likely to occur at this facility and, therefore, we find no undue risk to the health and safety of the public as a result of the continued
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operation of the Maine Yankee Atomic Power Station.
4.0 REFERENCES
4 4.1 J.L. French, Maine Yankee Atomic Power Company (MYAPC), letter to R.A. Purple, NRC,
Subject:
" Response to May 13, 1975 letter on Steam Generator Water Hammer," July 14, 1975.
4.2 R.H. Groce, MYAPC, letter to R.W. Reid, NRC,
Subject:
"Feedline Water Hammer," November 25, 1977.
a.3 C.C. Fri::le, MY'PC, letter to R. Colmar, NRC,
Subject:
" Maine Yankee Steam Generator Feedwater Piping," June 6,1979.
4.4 0.E. Moody, MYAPC, letter to R. Reid, NRC, dated November 15, 1979, in resconse to NRC request for information regarding the potential for steam generator water hammer.
4.5 J. A. Block, et al, An Evaluation of PWR Steam Generator Water Hammer, Creare, Inc., NUREG-0291 (December 1976).
I 4.6 W.E. Bennett, Waterhammer in Steam Generator Feedwater Lines, !
Westinghouse Technical Bulletin, NSD-TB-75-7, June 10,1975.
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