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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval ML20217E9071997-10-0202 October 1997 Safety Evaluation Accepting Licensee Request for Relief from Certain ISI Requirements of ASME Boiler & Pressure Vessel Code,Section XI for Plant,Unit 2 ML20210R0501997-08-22022 August 1997 Safety Evaluation Accepting Revised Fermi-2 Control Ctr HVAC Sys Design Criteria in Design Criteria Document Submitted by Detroit Edison ML20138L7961997-02-19019 February 1997 SER Related to Inservice Testing Program Relief Request Detroit Edison Co,Fermi Unit 2 ML20133L7371997-01-0202 January 1997 Safety Evaluation Supporting Amend 11 to License DPR-9 ML20059J4591994-01-25025 January 1994 Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement ML20125C8041992-12-0808 December 1992 Safety Evaluation Accepting Util 920729 Revised Feedwater Nozzle Analysis for Plant,Per Generic Ltr 81-11 ML20246B2891989-04-28028 April 1989 Safety Evaluation Supporting Amend 9 to License DPR-9 ML20244B7141989-04-0404 April 1989 SER Accepting Util Responses to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability ML20237A7051987-12-10010 December 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 2 Requiring Confirmation That Interface Established W/Nsss or W/Vendors of Each Reactor Trip Sys Components.Response Acceptable ML20237A6971987-12-10010 December 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 1 Requiring Confirmation That All Reactor Trip Sys Components Identified as safety-related.Response Acceptable ML20237B4091987-12-0808 December 1987 SER Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing (Reactor Trip Sys Components, All Other safety-related Components) ML20236L6551987-11-0404 November 1987 SER Re Generic Ltr 83-28,Item 2.2.1, Equipment Classification Programs for All Safety-Related Components. Util 831103 Response Acceptable ML20236A3981987-10-15015 October 1987 Safety Evaluation Re Potential Hazards Associated W/ Operation of & Potential Explosion Accidents at Rockwood Stone,Inc Quarry.Hazards Considered Insignificant,Based on Util Confirmatory Analysis & Independent NRC Evaluation ML20235S8731987-10-0606 October 1987 Safety Evaluation Re First 10-yr Interval Inservice Insp Program.Relief Granted from Exam & Testing Requirements of ASME Code & Alternate Methods Imposed Through Document ML20236D7421987-07-28028 July 1987 Safety Evaluation Re Main Steam Instrument Line Leaks. Licensee Satisfactorily Resolved Problems Re Main Steam Instrument Line Leaks Which Occurred in Jan 1987 & Recurred in Apr 1987 ML20206B5371987-04-0707 April 1987 Safety Evaluation Supporting Util Request to Amend License Condition 2.C(10), Emergency Diesel Generator Lube Oil Surveillance Program. NRC Does Not Agree Condition Should Be Revised by Substituting for Mar 1985 Ltr ML20207R8541987-03-12012 March 1987 Safety Evaluation Re Facility Mark I Containment Vacuum Breaker Structural Integrity.Licensee Restored Safety Margins of Breakers by Replacing Critical Parts W/Adequate Matl.Corrective Action Acceptable ML20212E3161987-02-27027 February 1987 Safety Evaluation Re Operation of Rockwood Stone,Inc Quarry Near Plant ML20212J8421987-02-26026 February 1987 Safety Evaluation Approving Individual to Serve as Shift Operations Advisor,Per Generic Ltr 84-16 IR 05000341/19850501987-01-16016 January 1987 Safety Evaluation Re Proposed Fire Protection Mod to Independent Alternative Safe Shutdown Capability to Satisfy Open Items in Insp 50-341/85-50 ML20215E0061986-12-12012 December 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components ML20203L5701986-08-19019 August 1986 Safety Evaluation Supporting Proposed Tech Specs Re Alternative Shutdown Sys.Acceptability Based,In Part,On Performance of Tests in Accordance W/Reg Guide 1.68, Initial Test Programs for Water-Cooled Nuclear Plants ML20207H5551986-07-16016 July 1986 SER Re Corrective Actions for Emergency Diesel Generators. Concurs W/Licensee Proposed Special Bearing Insp,Provided Envelope Provided by Demonstration Test Program Not Exceeded ML20154L4261985-04-18018 April 1985 Safety Evaluation Supporting 1983 ASME Code,Section XI, Paragraph IWV-3520 Requirement for Periodic Closure Verification Testing of Normally Closed Check Valves w/safety-related Functions 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20205P9721999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fermi 2 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 NRC-99-0005, Monthly Operating Rept for Dec 1998 for Fermi 2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fermi 2.With ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 NRC-99-0021, 1998 Annual Financial Rept for Detroit Edison Co. with1998-12-31031 December 1998 1998 Annual Financial Rept for Detroit Edison Co. with NRC-98-0153, Monthly Operating Rept for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0097, Monthly Operating Rept for June 1998 for Fermi,Unit 21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Fermi,Unit 2 NRC-98-0127, Annual Rept for Period 970701-9806301998-06-30030 June 1998 Annual Rept for Period 970701-980630 NRC-98-0079, Monthly Operating Rept for May 1998 for Fermi 21998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Fermi 2 NRC-98-0076, Monthly Operating Rept for Apr 1998 for Fermi 21998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Fermi 2 NRC-98-0072, Monthly Operating Rept for Mar 1998 for Fermi 21998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Fermi 2 NRC-98-0050, Monthly Operating Rept for Feb 1998 for Fermi 21998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Fermi 2 NRC-98-0019, Monthly Operating Rept for Jan 1998 for Fermi 21998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Fermi 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20197A9921997-12-15015 December 1997 Rev 0 to Efp,Unit 1 Fermi 1 Sar NRC-97-0131, Monthly Operating Rept for Nov 1997 for Fermi 21997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Fermi 2 ML20248H1151997-10-31031 October 1997 Rev 1 to Colr,Cycle 6 for Fermi 2 1999-09-30
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SAFETY EVALUATION BY OFIICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS RELATED TO AMENDMENT NO.15 TO FACILITY OPERATING LICENSE NO. DPR-9 DETROIT EDISON COMPANY ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 DOCKET NO. 50-16
1.0 INTRODUCTION
By letter dated January 28,1998, and supplement" 1 by letters dated August 26,1998, and October 22,1998, the Detroit Edison Company (CdCo or the licensee) submitted a request for a change to the Enrico Fermi Atomic Power Plant Unit 1 (Fermi 1) Technical Specifications (TS) appended to Facility Operating License No. DPR-9. The requested changes would:. (1) include requirements for control of effluents, per 10 CFR 50.36a, with provisions for tritium effluent monitoring or analysis; (2) include dose limit requirements; (3) include a requirement to develop dose calculation methods; (4) include an annual reporting requirement per 10 CFR 50.36a; and (5) correct a typographical error.
2.0 EVALUATION The final rule, dated July'29,1996, for Decomrnissioning of Nuclear Power Reactors, revised 10 CFR 50.36a to clarify applicability of this section to alllicensees of power reactors whether operating or not. As a result of the revision of 10 CFR 50.36a, DECO is required to have additional effluent TS for Fermi 1. The licensee has requested to add requirements, per 10 CFR 50.36a, for control of effluents with provisions for tritium effluent monitoring or analysis, for dose limits, for development of a dose calculation method, and for annual reporting. In addition, the licensee requested to correct typographical errors.
The proposed amendment includes a requirement to establish and follow procedures for the control of effluents. The proposed changes involve adding requirements in Section F of the TS to
- ensure procedures for effluent release are in place before any planned discharges. In addition, the licensee requested to add provisions for tritium to the TS because tritium was detected in the residual secondary sodium at Fermi 1 in early 1998. One proposed requirement is to sample and analyze liquid radioactive effluents before being discharged. The effluent would be analyzed by
. gamma spectral analysis and tritium analysis. If the liquid effluent has not been processed to remove particulates, then the effluent is required to be monitored by a radiation monitor during
- discharges. Another proposed requirement is to monitor or sample and analyze radioactive
- gaseous effluents and airborne radioactive particulates for tritium during the cutting of pipe containing sodium and during sodium processing. NRC staff agrees with the licensee that sample analysis is appropriate for performing dose calculations. NRC staff has determined that these additional requirements are acceptable.
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The proposed dose limit requirements include an effluent dose limit that is the numerical limit in 10 CFR 20.1301, and guidelines using criteria from 10 CFR Part 50, Appendix 1. The proposed changes involve adding requirements in Section F of the TS. NRC staff finds these proposals acceptable.
Another proposal in this amendment is to include a requirement to establish a dose calculation method for the control of effluents. The proposed cnanges involve adding requirements in Section F of the TS to assure the development of a dose calculation method used to show compliance with effluent release limits prior to any planned releases. NRC staff has determined that this change is acceptable.
The proposed amendment also includes a requirement for an annual effluent report par 10 CFR 50.36a. This report would specify to the NRC the quantity of radioactive effluents released and the calculated doses of the release. The proposed change involves adding, to Section H.8 of the TS, the annual reporting to the NRC of radioactive effluents released and the related dose calculations. NRC staff finds this request acceptable.
Finally, the licensee requested to correct a typographical error in section numbering. On page 6 of the TS, the numbering of the Facility Monitoring Surveillances section will be corrected from "E" to "H."
3.0 STATE CONSULTATION
in accordance with the NRC regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes Fermi 1 TS with respect to the administrative procedures or requirements. NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The NRC staff has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FB 35987) on July 1,1998. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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5.0 CONCLUSION
The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the NRC regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Wu, NMSS/LLDP Date: January 6,1999
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