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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 EVAt.UATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE OPERATION OF THE ROCKWOOD STONE INC OUARRY DETROIT EDISON COMPANY (DECO) 1 FERMI-2 DOCKET NO. 50-3411
1.0 INTRODUCTION
In a telephone conversation on June 24, 1986, the staff conveyed to DECO a concern regardino the potential effects of operations at the Rockwood Stone, Incorporated, (RSI) quarry on the safe operation of the Fermi-2 plant. This
_q uarry has operated since 1982, producing dolomitic limestone for the con-struction industry. Previously described existing quarries with respect to the Fermi-? site are at least eight miles away from the site. In a [[letter::IA-86-512, Responds to FOIA Request.App Documents,Including NUREG-0020, NUREG-0030,NUREG-0090 & 691121 Rept to ACRS, Enrico Fermi Atomic Power Plant, Available in PDR|letter dated July 24, 1986]], the licensee provided an analysis of the potential effects of the RSI quarry operations on the Fermi-2 plant. This Safety Evaluation describes the staff's review of the July 24, 1986, submittal and its findings with respect to the safe operation of Fermi-2.
2.0 EVALUATION The operation of the RSI quarry involves the use of explosives for the purpose of blasting quarry stone. The explosive used is Ammonium Hitrate Fuel 011 (ANF01, which has a TNT Eouivalence of 1.08. .The, explosives are shipped to the quarry by truck in approximately 40,000 pound quantities, with a maximum onsite storage of about 80,000 pounds.
One hazard associated with the operation of the RSI quarry is an air blast
- due to a potential explosion of bulk quantities of ANFO. Deco has estimated the blast overpressure considering an explosion of 80,000 pounds '
of'ANFO. Specifically, using the guidelines of Regulatory Guide 1.91, DECO estimated that the blast overpressure effects are insignificant with respect l to safety-related plant structures beyond a distance of 1989 feet from the explosion. The staff has performed an independent analysis of the potential i
blast effects of such an explosion. The results indicate that the potential air blast effects of either an explosion at the quarry or an explosion of a shipment at its nearest point to the Fermi-2 plant are insignificant with respect to the plant structures.
The explosions postulated also have been reviewed with respect to potential ground effects at the Fermi-2 site. DECO considered the ground effects due
, to nonnal blasting operations at the RSI quarry and in its engineering judgement has concluded that the ground effects at the Fermi-2 site due to
- normal blasting would be insignificant. Deco also noted that there has D
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not been any detectable indication on the active site seismograph or the i peak shock recorders during quarry blasting activities due to normal .
explosions. However, DECO did not address potential ground effects due. l to accidental explosions of bulk quantities of ANF0, either at the RSI .
quarry or.during shipments to the quarry. :
[' The staff has considered the potential ground effects due to the detonation of the maximum stored inventory of 80,000 pounds of ANFO at the RSI quarry, as well as the. detonation of a shipment of 40,000 pounds at the closest approach (two miles.from Fermi-2). In a previous review of.another nuclear '
power plant, the staff had analyzed the detonation of 82,000 pounds of
~ explosives. Its findings for that case were that the free field peak ground acceleration was.less than 0.02g at a. distance of 8700 feet. The Fermi-2 safety-related structures are designed to meet an operating basis earthquake acceleration _of 0.08g. Furthermore, the plant is designed to shut down safely after an earthquake as great as 0.15g. . Hence, in view of the Femi-2 seismic design values, as well'as the distances involved with respect to the postulated explosions, it is reasonable to expect that: '
the potential ground motion at the Fermi-2 plant site is acceptably low.
However, there is a possibility that differences in subsurface. geology between the Fermi-2 site and the previously analyzed site could affect l ground motion and hydrostatic pressures. Hence, DECO needs to provide a
- confirmatory analysis of the postulated explosions and their effects on
< ground motion and peak hydrostatic pressures in order to demonstrate that the hazard is insignificant. The analysis should include a review of the construction activities for Fermi-2 (as well as the inactive Fermi-1 plant) and list any damages to structures (onsite or offsitel due to the blasting.
that has occurred at the RSI quarry. Deco also needs to make availahle to the staff any reports or other results of investigations in regard to such damages.
Another potential hazard essessad is that related to;the dewatering activ-ities at the RSI quarry and +' potential for redirecting contaminated groundwater from its normal ....it to east course. According to Deco's de-scription of the location of the quarry, it is situated approximately one i mile away from the lake shore and three miles from the Femi-2 plant. The J. Fermi-2 FSAR (Fig. 2.4-24) indicates that the contour lines of water levels
! measured in the dolomite are approximately parallel to the lake shore. This ,
l means that the groundwater gradient is primarily toward the lake and normal F to the shoreline. Hence, the permeability of the fractured dolomite is likely to be greatest in a direction normal to the lake shore, where flow paths have been developed. On this basis, a dewatering operation is expected to i .. intercept flow primarily in " front" and "back" of the cuarry relative to i
the shoreline. The inflow from the sides is expected to be much less. In view of the above considerations, the staff concurs with Deco's assessment i that the dewatering activities at the RSI quarry would not have any dis-cernible effect on the groundwater flow at the Fermi-2 site.
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3-t 3.0 ~ CONCLUSIONS ,
The' staff has reviewed the potential hazards associated with the operation of and the potential explosion accidents at the RSI quarry and has deter-mined that present and future dewatering activities at the PSI quarry are not expected to have any appreciable effect on the established groundwater flow in the vicinity of the Fermi-2 site. With respect to postulated explosions of bulk quantities of the explosives used for RSI quarry blasting, the staff finds that they 'do not pose a significant hazard to the safe
-operation of the Fermi-2 plant. The staff has reason to believe that the associated ground motion and peak hydrostatic pressures may also be in-significant. However, Deco needs to provide a confirmatory analysis of the postulated explosions to demonstrate that the ground motion-and hydrostatic pressure change hazards are insignificant with respect to the Fermi-2 plant in order to fully allay the staff's concerns relative to the effects of the RSI quarry operation on the continued safe operation of the Fermi-2 plant.
Principal Contributor: K.lCampe,NRR 4
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Mr. B. Ralph Sylvia .
Detroit Edison Company Femi-2 Facility
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Mr. Harry H. Voigt. Esq.. Ronald C. Callen LeBoeuf, Lamb, Leihy & MacRae Adv. Planning Review Section-1333 New Hampshire Avenue, N. W. Michigan Public Service Connission Washington, D. C. 20036 6545 Mercantile Way P. O. Box 30221 John Flynn, Esq. Lansing, Michigan 48909
-Senior Attorney .
Detroit Edison Company Regional Administrator, Region III 2000 Second Avenue U. S. Nuclear Regulatory Commission Detroit, Michigan 48226 799 Roosevelt Road .
Glen Ellyn, Illinois 60137 Mr. Dennis R. Hahn, Chief Nuclear Facilities and Environmental-
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Monitoring Section Office Division of Radiological Health P. O. Box 30035 Lansing, Michigan- 48909 Mr. Steve Frost .
Supervisor-Licensing Detroit Edison Company Fermi Unit 2 6400 North Dixie Highway Newport, Michican 48166 Mr. Thomas Randazzo
. Director,. Regulatory Affairs Detroit Edison Company Fermi Unit. 2 6400 North Dixie Highway Newport, Michigan 48166 Mr. Walt Rogers U. S. Nuclear Regulatory Commission Resident Inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Office of Civil Preparedness
, 963 South Raisinville
!- Monroe, Michigan 48161 l
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