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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 ML20217M7121999-10-19019 October 1999 Safety Evaluation Supporting Amend 135 to License NPF-43 ML20207A8901999-05-25025 May 1999 Safety Evaluation Supporting Amend 133 to License NPF-43 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 ML20207F9951999-03-0303 March 1999 Safety Evaluation Supporting Amend 132 to License NPF-43 ML20203F8651999-02-0808 February 1999 Safety Evaluation Supporting Amend 131 to License NPF-43 ML20203F8441999-02-0808 February 1999 Safety Evaluation Supporting Amend 130 to License NPF-43 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 ML20153C4781998-09-16016 September 1998 Safety Evaluation Supporting Amend 128 to License NPF-43 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant ML20237E1751998-08-25025 August 1998 Safety Evaluation Supporting Amend 127 to License NPF-43 ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20237E2071998-08-25025 August 1998 Safety Evaluation Supporting Amend 126 to License NPF-43 ML20237C5571998-08-20020 August 1998 Safety Evaluation Supporting Amend 125 to License NPF-43 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 ML20237D1491998-08-0404 August 1998 Safety Evaluation Supporting Amend 124 to License NPF-43 ML20237D3471998-07-31031 July 1998 Safety Evaluation Supporting Amend 123 to License NPF-43 ML20236M7511998-07-0909 July 1998 Safety Evaluation Supporting Amend 121 to License NPF-43 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 ML20249A8451998-06-12012 June 1998 Safety Evaluation Supporting Amend 120 to License NPF-43 ML20248K9301998-06-0202 June 1998 Safety Evaluation Supporting Amend 119 to License NPF-43 ML20248F1511998-05-28028 May 1998 Safety Evaluation Supporting Amend 118 to License NPF-43 ML20216C1491998-04-0303 April 1998 Safety Evaluation Supporting Amend 117 to License NPF-43 ML20217A7921998-03-17017 March 1998 Safety Evaluation Supporting Amend 115 to License NPF-43 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 ML20217E3431997-09-30030 September 1997 Safety Evaluation Supporting Amend 114 to License NPF-43 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 ML20084R7051995-05-23023 May 1995 Safety Evaluation Supporting Amend 104 to License NPF-43 ML20071N5701994-08-0101 August 1994 Safety Evaluation Supporting Amend 102 to License NPF-43 ML20070J6781994-07-18018 July 1994 Safety Evaluation Supporting Amend 101 to License NPF-43 ML20059J4591994-01-25025 January 1994 Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement ML20059E0411994-01-0404 January 1994 Safety Evaluation Supporting Amend 96 to License NPF-43 ML20057B6241993-09-0707 September 1993 Safety Evaluation Supporting Amend 92 to License NPF-43 ML20057A0231993-08-27027 August 1993 Safety Evaluation Supporting Amend 91 to License NPF-43 ML20125C8041992-12-0808 December 1992 Safety Evaluation Accepting Util 920729 Revised Feedwater Nozzle Analysis for Plant,Per Generic Ltr 81-11 ML20115H5581992-10-15015 October 1992 Safety Evaluation Supporting Amend 88 to License NPF-43 ML20099K5301992-08-18018 August 1992 Safety Evaluation Supporting Amend 86 to License NPF-43 ML20099G3341992-07-31031 July 1992 Safety Evaluation Supporting Amend 85 to License NPF-43 ML20210E1451992-06-0909 June 1992 Safety Evaluation Supporting Amend 82 to License NPF-43 ML20096A8331992-04-22022 April 1992 Safety Evaluation Supporting Amend 81 to License NPF-43 ML20094K2011992-03-0909 March 1992 Safety Evaluation Supporting Amend 80 to License NPF-43 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 ML20217M7121999-10-19019 October 1999 Safety Evaluation Supporting Amend 135 to License NPF-43 05000341/LER-1999-004, :on 990913,HPCI Sys Was Noted Inoperable.Caused by Failed HPCI Room Temp Switches.Replaced Temp Switches & HPCI Was Restored to Operable Status.With1999-10-13013 October 1999
- on 990913,HPCI Sys Was Noted Inoperable.Caused by Failed HPCI Room Temp Switches.Replaced Temp Switches & HPCI Was Restored to Operable Status.With
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 05000341/LER-1999-003, :on 990625,HPCI Sys Flow Controller Failed. Caused by Failure of Control Amplifier for Automatic HPCI Flow Control Loop.Replaced Control Amplifier Circuit Card. with1999-07-26026 July 1999
- on 990625,HPCI Sys Flow Controller Failed. Caused by Failure of Control Amplifier for Automatic HPCI Flow Control Loop.Replaced Control Amplifier Circuit Card. 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-99-0088, 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 05000016/LER-1999-001, :on 990604,protected Area Access Was Found Unlocked.Caused by Human Error.Reinforced That Custodial Agent Issued Key Is Responsible for Ensuring That Protected Area Access Gate Is Locked1999-06-25025 June 1999
- on 990604,protected Area Access Was Found Unlocked.Caused by Human Error.Reinforced That Custodial Agent Issued Key Is Responsible for Ensuring That Protected Area Access Gate Is Locked
05000341/LER-1999-002, :on 990518,RRP Trip Resulted in Manual Reactor Scram.Caused by Previous Actions Taken to Minimize Risk for RRP Trip Were Not Effective.Preventive Maint Activity to Change RRP MG Set Brushes Has Been Revised.With1999-06-17017 June 1999
- on 990518,RRP Trip Resulted in Manual Reactor Scram.Caused by Previous Actions Taken to Minimize Risk for RRP Trip Were Not Effective.Preventive Maint Activity to Change RRP MG Set Brushes Has Been Revised.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 ML20207A8901999-05-25025 May 1999 Safety Evaluation Supporting Amend 133 to License NPF-43 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 ML20207F9951999-03-0303 March 1999 Safety Evaluation Supporting Amend 132 to License NPF-43 ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20203F8441999-02-0808 February 1999 Safety Evaluation Supporting Amend 130 to License NPF-43 ML20203F8651999-02-0808 February 1999 Safety Evaluation Supporting Amend 131 to License NPF-43 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 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 ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 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 05000341/LER-1998-011, :on 981014,cracking in Silicone Fire Barrier Penetration Seal Occurred Due to High Temps.Caused by Inappropriate Translation of Vendor Matl Info Into Penetration Seal Design.With1998-11-13013 November 1998
- on 981014,cracking in Silicone Fire Barrier Penetration Seal Occurred Due to High Temps.Caused by Inappropriate Translation of Vendor Matl Info Into Penetration Seal Design.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 05000341/LER-1998-010, :on 981007,SRV as Found Settings Exceed TS Setpoint Tolerance Criteria.Caused by Oxide Bonding Between Pilot Valve Disc & Seat.All 15 Pilot Valve Assemblies Were Replaced.With1998-10-28028 October 1998
- on 981007,SRV as Found Settings Exceed TS Setpoint Tolerance Criteria.Caused by Oxide Bonding Between Pilot Valve Disc & Seat.All 15 Pilot Valve Assemblies Were Replaced.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 05000341/LER-1998-009, :on 980914,inadvertent Deenergization of Safety Bus 72F While Transferring from Alternate to Normal Power Resulted in ESF Actuations.Caused by Personnel Error. Operator Involved Was Counseled.With1998-10-0808 October 1998
- on 980914,inadvertent Deenergization of Safety Bus 72F While Transferring from Alternate to Normal Power Resulted in ESF Actuations.Caused by Personnel Error. Operator Involved Was Counseled.With
05000341/LER-1998-008, :on 980908,RHR/LPCI Sys Injection Line Inboard Isolation Check valve,E1100F050B,failed to Meet TS Leakage Criteria.Caused by Degraded Soft Seat.Subject Valve Was Refurbished with New Soft Seat1998-10-0808 October 1998
- on 980908,RHR/LPCI Sys Injection Line Inboard Isolation Check valve,E1100F050B,failed to Meet TS Leakage Criteria.Caused by Degraded Soft Seat.Subject Valve Was Refurbished with New Soft Seat
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 ML20153C4781998-09-16016 September 1998 Safety Evaluation Supporting Amend 128 to License NPF-43 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 ML20237E2071998-08-25025 August 1998 Safety Evaluation Supporting Amend 126 to License NPF-43 ML20237E1751998-08-25025 August 1998 Safety Evaluation Supporting Amend 127 to License NPF-43 ML20237C5571998-08-20020 August 1998 Safety Evaluation Supporting Amend 125 to License NPF-43 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 ML20237D1491998-08-0404 August 1998 Safety Evaluation Supporting Amend 124 to License NPF-43 1999-09-30
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UNITED STATES ijg; NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20555-OD01 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 91 TO FACILITY OPERATING LICENSE NO. NPF-43 D_ETROIT EDISON COMPANY FERMI-2 DOCKET NO. 50-341
1.0 INTRODUCTION
By letter dated March 23, 1993, the Detroit Edison Company (DECO or the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No. NPF-43 for Fermi-2.
The proposed amendment would revise the semiannual reporting requirement for the Radioactive Effluent Release P,eport to an annual reporting requirement in accordance with a recent change to 10 CFR 50.36a.
The amendment would also modify TS 6.8.3 to allow the Plant Manager to delegate, in writing, approval authority for plant procedures to a management representative responsible for that functional area vice the "Section Superintendent."
2.0 EVALUATION The proposed replacement of the word " Semiannual" with " Annual" for the Radioactive Effluent Release Report will bring the title of this report in compliance with the new requirements of 10 CFR 50.36a. This will permit submittal of the report on an annual basis rather than semiannual, thus reducing the frequency of regulatory review.
In addition, the submittal date has been extended from 60 to 90 days after January 1 of each year. This extension will provide the additional time necessary for preparation and review of a report that will contain data gathered over a longer time period. This time period for submittal is acceptable to the staff.
With respect to the proposed change relating to the Plant Manager's delegation of approval for Plant Procedure changes, currently, Technical Specification 6.8.3 allows the Plant Manager to delegate approval authority in writing for specific types of procedures to a Section Superintendent. This reflected the organizational titles in effect at the time of the approval of this specification.
Changing the designation as proposed to " management representative responsible for a functional area," retains the intent that approval authority be limited to the appropriate level of management experience. The change allows flexibility in assigning titles reducing the need for the future TS changes and is acceptable to the staff.
9309100301 930827 PDR ADOCK 05000341 P
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no connents.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment changes recordkeeping, reporting, and administrative procedures and requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
The 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 Commission's 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:
Timothy G. Colburn Date:
August 27, 1993
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