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
[Table view] |
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p recq l o UNITED STATES l 8' N NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 l
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\*****/ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT N0. 98 TO FACILITY OPERATING LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309
1.0 INTRODUCTION
In a telephone conference on September ?, 1986, the licensee, Maine Ycakee ;
Atomic Power Company (NYAPCO), for the Maine Yankee plant informed the staff of 4 a non-conservatism in their large break LOCA analysis. . Appendix K to 10 CFR 50 requires that the axial power shape which results in the most severe consequences should be used in the ECCS evaluation model LOCA calculations. It was determined that the most severe power shape for the Maine Yankee plant was a flattened ;
power shape rather than the highly peaked axial power distribution that had t been used in the LOCA evaluations. During Cycle 9 operation of the Maine Yankee plant, the licensee imposed administrative limits on power peaking factors to assure compliance with 10'CFR 50.46.
To support Cycle 10 operation of the Maine Yankee plant, the licensee proposed changes in their approved ECCS evaluation model (EM). These changes consisted of a method for selecting the appropriate power shapes to be used in the analysis and a modification to the injection delta P penalty for steam-water interaction effects. These changes to the EM were approved by the staff in Reference 1. The EM calculation method remains valid for the full spectum of .
breaks. However, since a full break spectrum was not analyzed for each axial I power shape selected, the staff required the licensee to justify the spectrum }
of breaks analyzed for each reload, J In Reference 2, the licensee provided the results of the LOCA limit calculations performed for Cycle 10 operation. Included in the submittal were associated Technical Specification changes. Within Reference 3, the licensee provided justification for the break spectrum analysis which was performed for the axial power shapes chosen with the approved methodology. These submittals are the subject of this evaluation.
2.0 EVALUATION 2.1 Break Spectrum In Reference 3, the licensee provide'd the results of the break spectrum analysis which was performed to support Cycle 10 operation. Using its approved EM methodology, the licensee selected worst case axial power shapes at the 52%, 65%, 73% and 85% core elevations for ultimate use in calculating LOCA limits at these elevations. The licensee performed separate break =
spectrum analysis for each of these power shapes to determine the worst case break size at each elevation. The analysis was performed using a combination-of the upper (previous (Cycle 73% and 85%) power5) break spectrum analysis and new analysis for the-Six break shapes.
8706220162 870615 91 DR ADOCK 050
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shape; four breaks were analyzed for the 85% shape; three breaks were analyzed for the 52% and 73% shapes. The licensee provided justification to demonstrate that the cases selected were adequate to determine the worst case break for each shape.
As a result of the analysis, the licensee concluded that the worst case break ,
for the 52% and 65% shapes was a cold leg guillotine break with a discharge coefficient of 0.8. A split break in the cold leg, with area equal to twice the cross-sectional area of the pipe, with a discharge coefficient of 1.0 was determired to be the limiting break size for the 73% and 85% power shapes.
The-staff reviewed the information supplied by the licensee and determined that the approach used by the licensee to determine the worst case break was reasonable. However, additional information was requested to confirm the licensee'>s judgment that the more limited break spectrum analysis performed for the 52%, 73% and 85% power shapes was sufficient to identify the worst case break. This information was provided in Reference 4. Using this additional information, the staff independently confirmed the licensee's :
judgment that the more limited break spectrum was adequate. Therefore, the staff finds that the licensee's analysis complies with the break spectrum requirements in Section I.C.1 of Appendix K to 10 CFR 50, 2.2 LOCA Limits In Reference 2, the licensee provided the results of the LOCA Limits ;
evaluation performed for Cycle 10. Separate analysis were performed for the 1 52%, 65",, 73% and 85% core elevations. Allowable linear heat generation rates were calculated for each elevation to assure compliance with the requirements I of 10 CFR 50.46. The break size analyzed at each elevation was the worst case break determined by the break spectrum analysis discussed above. For all ,
cases, peak cladding temperatures were less than 2200* F, local cladding oxidation ]
was much less than the allowed 17% of cladelng thickness, and less than one :
percent hydrogen generation was calculated.' !
1 The staff finds that these analyses were performed using an approved EM in conformance with Appendix K to 10 CFR 50, and the results all satisfy the requirements of 10 CFR 50.46. Thus, the staff finds the calculated LOCA limits acceptable.
1 2.3 Technical Specification As a part of Reference 2, the licensee proposed changes to the Maine Yankee plant Technical Specifications (TS) to reflect the results of the new LOCA analyses. These changes included modifications to TS 3.10.C.1, 3.10.C.3.1.1, 3.10.C.3.1.2 and the addition of Figure 3.10-12 to TS 3.10, The staff has reviewed these changes and find them acceptable. Specifically, the addition of Figure 3.10-12 simply reflects the results of the new LOCA limits evaluation found acceptable above. The remainder of the changes are editorial in nature, either reflecting the addition of the fioure or clarifying text.
The staff finds that the revised LOCA limits for the Maine Yankee plant satisfy the requirements of 10 CFR 50.46. Additionally, the modifications to the Technical Specifications appropriately reflect the results of the analysis. Therefore, the staff concludes that Cycle 10 operation with the proposed changes is acceptable. ~
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase ,
in the amounts, and no significant change in the types, of any effluents that f may be released offsite, and that there is no significant increase in individual or. cumulative occupational radiation exposure. The Commission has previously j issued a proposed finding that this amendment involves no significant hazards '
consideration.and~ there has been no.public comment on such finding. Accordingly, i this amendment meets the eligibility criteria for categorical exclusion set L forthin10CFR51.22(c)(9). Pursuantto.10CFR51.22(b),noenvironmental impact statement or environmental assessment need be prepared in connection with the . issuance of this amendment.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that (1) there l is reasonable assurance that the health and safety of the public will not be endangered'by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be-inimical to the common defense and security or to the health and safety of the public.
Date: June 15,1987 Principal Contributor:
N. Lauben R. Jones j y
REFERENCES i
- 1. Letter from P. Sears .(NRC) to J. Randazza (MYAPC0), "ECCS Evaluation Model Modifications Related to Axial Power Shape -Issue, Phase I," January 6, 1987. o 1
2.- Letter from J. Randazza (MYAPCO) to Document Control Desk (NRC),
'" Proposed Change No.130 - Technical Specification 3.10 LOCA limits."
February 24, 1987.
- 3. Letter from G. Whittier (MYAPCO) to A. Thadani (NRC), " Maine Yankee LOCA Analysis," February 23, 1987.
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Letter from G. Whittier to Document Control Desk (NRC) " Maine Yankee LOCA Analysis", June 8, 1987.
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