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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212B9961999-09-15015 September 1999 Proposed Tech Specs Page 3.3-52,deleting Condition G as Well as or G from Condition H,Per TS Change Request TSCR-003 ML20210B9411999-07-16016 July 1999 Proposed Tech Specs Revising SLMCPR to Support Operation with GE-12 Fuel with 10x10 Pin Array ML20206P7401999-05-10010 May 1999 Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 with 10x10 Pin Array ML20206P2321999-05-10010 May 1999 Proposed Tech Specs Section 3.7.4,providing Specific Conditions & Required Actions for Control Bldg Barrier Degradation (as Opposed to Ventilation Train Degradation) ML20206J3011999-04-30030 April 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 3.4.3.1 to Implement More Appropriate Safety Valve & Safety Relief Valve Setpoint Tolerances ML20205P8031999-04-12012 April 1999 Proposed Tech Specs Re Relaxation of Excess Flow Check Valve Surveillance Testing ML20204A7541999-01-22022 January 1999 Proposed Tech Specs Re Spent Fuel Racks Storage Update ML20202E5931999-01-22022 January 1999 Proposed Tech Specs SR 3.8.1.7 Re Rev to DG Surveillance Requirement ML20206S2421999-01-21021 January 1999 Proposed Tech Specs Surveillance Requirement 3.8.1.7 for EDGs ML20154P6621998-10-15015 October 1998 Proposed Tech Specs 3.6.1.3,revising Condition E to Add Time Limit for Plant Operation If Penetration Flow Path Isolated by Single Purge Valve with Resilient Seal & Adding TS for Cb/Sbgt IAS NG-98-0720, Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements1998-04-17017 April 1998 Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements ML20217B8271998-04-15015 April 1998 Proposed Tech Specs Re RTS-300,revising Reactor Vessel pressure-temp Curve Update ML20203M5021998-02-26026 February 1998 Proposed Tech Specs Re Improved Conversion of Plant ML20199K9601998-02-0303 February 1998 Proposed Tech Specs Re Standby Liquid Control Operability Requirements ML20199K9871998-02-0303 February 1998 Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing Operability Requirements ML20198P8871998-01-0909 January 1998 Proposed Tech Specs Section 3.7.B LCO for PCIVs Revised to Allow 72 Hours to Isolate Failed Valve Associated W/Closed Sys ML20203G5331997-11-21021 November 1997 Proposed Tech Specs Marked Up Pages for Improved TS for Rev a Showing Changes for Rev B ML20211J2331997-10-0303 October 1997 Proposed Tech Specs,Supplementing thermal-hydraulic Analysis Included as License Rept in 930326 to Murley NG-97-1010, Proposed Tech Specs Change for Instrument Setpoints1997-06-10010 June 1997 Proposed Tech Specs Change for Instrument Setpoints ML20141D3621997-05-0909 May 1997 Proposed Tech Specs Revising Definitions of LSSS & Instrument/Channel Calibration to Ref New Program Being Added to TS for Control of Instrument Setpoints NG-97-0847, Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions1997-05-0909 May 1997 Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions ML20115E0301996-07-0505 July 1996 Proposed TS Table 3.6.B.2-1,raising Reactor Water Conductivity Limit to Support Implementation of Noble Metal Chemical Addition at Plant as Method to Enhance Effectiveness of HWC in Mitigating IGSCC ML20101Q7191996-04-0909 April 1996 Proposed Tech Specs Re Recirculation Pump Trip Min Operable Channels ML20097A1871996-01-30030 January 1996 Proposed Tech Specs Revising Certain CR Scram Insertion Time Testing Limits ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20099L8491995-12-22022 December 1995 Proposed Tech Spec 3.7, Plant Containment Sys ML20095H2371995-12-15015 December 1995 Proposed Tech Specs,Incorporating EDG Conditional Surveillance & Editorial Clarifications ML20095A9011995-11-30030 November 1995 Proposed Tech Specs to Implement Option I-D Reactor Stability Solution ML20094M4131995-11-15015 November 1995 Proposed Tech Specs Re RPT Operability & Surveillance Requirements ML20087F5831995-08-0707 August 1995 Proposed Tech Specs Sections 6.5.2.8 & 6.5.3 Re Changes to Audit Program ML20086R8061995-07-21021 July 1995 Proposed Tech Specs,Eliminating Inappropriate Condition Surveillance in Sections 4.5 & 4.8,clarifying Requirements Governing Spent & New Fuel Storage in Section 5.5 ML20087H7021995-04-28028 April 1995 Proposed Tech Specs Bases Page 3.5-20,adding Clarification for Single Core Spray Pump Requirement ML20082S0201995-04-21021 April 1995 Proposed Tech Specs Reflecting Deletion of TS 6.5.3.1.2 Due to Audit Frequency Requirements Being Removed from TS ML20082D1171995-03-28028 March 1995 Proposed TS Table 3.2-A, Isolation Actuation Instrumentation ML20081C9891995-03-10010 March 1995 Proposed Tech Specs,Removing Redundant LCOs & SRs for Containment Hydrogen & Oxygen Monitors ML20080Q0851995-03-0101 March 1995 Proposed Tech Specs Modifying Pump & Valve Surveillance Criteria for LPCI & Core Spray Subsystems,Rhr Svc Water, Hpci,Esw & River Water Supply Systems from Once Every Three Months to Frequency Specified by DAEC ASME Section XI IST ML20080Q8731995-03-0101 March 1995 Proposed Tech Specs Reflecting Rev to TS Table of Contents, Incorporating New Section ML20078R9171995-02-13013 February 1995 Proposed TS Section 6.5.2.8 & 6.5..3.1,reflecting Deletion of Audit Frequency Requirements ML20080H5651995-02-13013 February 1995 Proposed Tech Specs Re Bases for Shutdown Cooling Piping Safety Limit ML20077A9191994-11-10010 November 1994 Proposed Tech Specs Re Offgas Radiation Monitors ML20149G9241994-10-28028 October 1994 Proposed Tech Specs,Deleting Plan for Integrated Scheduling of Plant Mods ML20076K9591994-10-20020 October 1994 Revised Proposed TS to TS Changes RTS-246 & RTS-246A ML20072F1651994-08-15015 August 1994 Proposed Tech Specs Increasing Allowable Main Steam Isolation Valve & Deleting TS Requirements Applicable to MSIV LCS ML20071Q6211994-07-29029 July 1994 Proposed Tech Specs Revising Isi/Ist Program Requirements ML20070H3321994-07-12012 July 1994 Proposed Tech Specs Surveillance Frequencies for Rod Block Instrument Sys ML20070E0621994-06-30030 June 1994 Proposed Tech Specs Re Addition of Control Bldg Chiller Operability & Surveillance Requirements ML20070E0411994-06-30030 June 1994 Proposed Tech Specs,Clarifying Requirements for Audit of Conformance to Tss,Deleting Requirement for Safety Committee Oversight of Audits & Allowing Designation of Signature Authority ML20070E0251994-06-30030 June 1994 Proposed Tech Specs Re Revision of ESW Flow Requirement 4.8.e.1 ML20069G9181994-05-27027 May 1994 Proposed TS Section 3.7, Containment Sys ML20069A9961994-05-0606 May 1994 Proposed TS SRs Section 4.6.G, Primary Sys Boundary Structural Integrity, Deleting SR Which Refers to ISI Program Interval,Allowing DAEC Current ISI Program Interval to Be Extended Per Ruling in Fr 57FR34666 1999-09-15
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B9961999-09-15015 September 1999 Proposed Tech Specs Page 3.3-52,deleting Condition G as Well as or G from Condition H,Per TS Change Request TSCR-003 ML20210B9411999-07-16016 July 1999 Proposed Tech Specs Revising SLMCPR to Support Operation with GE-12 Fuel with 10x10 Pin Array ML20206P7401999-05-10010 May 1999 Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 with 10x10 Pin Array ML20206P2321999-05-10010 May 1999 Proposed Tech Specs Section 3.7.4,providing Specific Conditions & Required Actions for Control Bldg Barrier Degradation (as Opposed to Ventilation Train Degradation) ML20206J3011999-04-30030 April 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 3.4.3.1 to Implement More Appropriate Safety Valve & Safety Relief Valve Setpoint Tolerances ML20205P8031999-04-12012 April 1999 Proposed Tech Specs Re Relaxation of Excess Flow Check Valve Surveillance Testing ML20204A7541999-01-22022 January 1999 Proposed Tech Specs Re Spent Fuel Racks Storage Update ML20202E5931999-01-22022 January 1999 Proposed Tech Specs SR 3.8.1.7 Re Rev to DG Surveillance Requirement ML20206S2421999-01-21021 January 1999 Proposed Tech Specs Surveillance Requirement 3.8.1.7 for EDGs ML20207E9931999-01-0707 January 1999 Rev 15 to Pump & Valve IST Program for Daec ML20205P8091998-11-30030 November 1998 Excess Flow Check Valve Testing Relaxation ML20154P6621998-10-15015 October 1998 Proposed Tech Specs 3.6.1.3,revising Condition E to Add Time Limit for Plant Operation If Penetration Flow Path Isolated by Single Purge Valve with Resilient Seal & Adding TS for Cb/Sbgt IAS ML20236T8621998-06-15015 June 1998 Third Ten Yr Interval ISI Summary Rept Refueling Outage 15 from 961116-980522 for DAEC Palo,Ia NG-98-0720, Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements1998-04-17017 April 1998 Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements ML20217B8271998-04-15015 April 1998 Proposed Tech Specs Re RTS-300,revising Reactor Vessel pressure-temp Curve Update ML20203M5021998-02-26026 February 1998 Proposed Tech Specs Re Improved Conversion of Plant ML20199K9601998-02-0303 February 1998 Proposed Tech Specs Re Standby Liquid Control Operability Requirements ML20199K9871998-02-0303 February 1998 Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing Operability Requirements ML20198P8871998-01-0909 January 1998 Proposed Tech Specs Section 3.7.B LCO for PCIVs Revised to Allow 72 Hours to Isolate Failed Valve Associated W/Closed Sys ML20203G5331997-11-21021 November 1997 Proposed Tech Specs Marked Up Pages for Improved TS for Rev a Showing Changes for Rev B ML20211J2331997-10-0303 October 1997 Proposed Tech Specs,Supplementing thermal-hydraulic Analysis Included as License Rept in 930326 to Murley NG-97-1010, Proposed Tech Specs Change for Instrument Setpoints1997-06-10010 June 1997 Proposed Tech Specs Change for Instrument Setpoints NG-97-0847, Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions1997-05-0909 May 1997 Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions ML20141D3621997-05-0909 May 1997 Proposed Tech Specs Revising Definitions of LSSS & Instrument/Channel Calibration to Ref New Program Being Added to TS for Control of Instrument Setpoints ML20138D9791996-12-0505 December 1996 Rev 9 to Offsite Dose Assessment Manual for Gaseous & Liquid Effluents ML20115E0301996-07-0505 July 1996 Proposed TS Table 3.6.B.2-1,raising Reactor Water Conductivity Limit to Support Implementation of Noble Metal Chemical Addition at Plant as Method to Enhance Effectiveness of HWC in Mitigating IGSCC ML20101Q7191996-04-0909 April 1996 Proposed Tech Specs Re Recirculation Pump Trip Min Operable Channels ML20108B6271996-03-15015 March 1996 Rev 0 to Third Ten-Yr Insp Interval ISI Plan for DAEC Palo, Ia ML20097A1871996-01-30030 January 1996 Proposed Tech Specs Revising Certain CR Scram Insertion Time Testing Limits ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20099L8491995-12-22022 December 1995 Proposed Tech Spec 3.7, Plant Containment Sys ML20095H2371995-12-15015 December 1995 Proposed Tech Specs,Incorporating EDG Conditional Surveillance & Editorial Clarifications ML20095A9011995-11-30030 November 1995 Proposed Tech Specs to Implement Option I-D Reactor Stability Solution ML20094M4131995-11-15015 November 1995 Proposed Tech Specs Re RPT Operability & Surveillance Requirements ML20129H0041995-10-13013 October 1995 Weld Ref Sys ML20087F5831995-08-0707 August 1995 Proposed Tech Specs Sections 6.5.2.8 & 6.5.3 Re Changes to Audit Program ML20086R8061995-07-21021 July 1995 Proposed Tech Specs,Eliminating Inappropriate Condition Surveillance in Sections 4.5 & 4.8,clarifying Requirements Governing Spent & New Fuel Storage in Section 5.5 ML20087H7021995-04-28028 April 1995 Proposed Tech Specs Bases Page 3.5-20,adding Clarification for Single Core Spray Pump Requirement ML20082S0201995-04-21021 April 1995 Proposed Tech Specs Reflecting Deletion of TS 6.5.3.1.2 Due to Audit Frequency Requirements Being Removed from TS ML20082D1171995-03-28028 March 1995 Proposed TS Table 3.2-A, Isolation Actuation Instrumentation ML20081C9891995-03-10010 March 1995 Proposed Tech Specs,Removing Redundant LCOs & SRs for Containment Hydrogen & Oxygen Monitors ML20080Q8731995-03-0101 March 1995 Proposed Tech Specs Reflecting Rev to TS Table of Contents, Incorporating New Section ML20080Q0851995-03-0101 March 1995 Proposed Tech Specs Modifying Pump & Valve Surveillance Criteria for LPCI & Core Spray Subsystems,Rhr Svc Water, Hpci,Esw & River Water Supply Systems from Once Every Three Months to Frequency Specified by DAEC ASME Section XI IST ML20080H5651995-02-13013 February 1995 Proposed Tech Specs Re Bases for Shutdown Cooling Piping Safety Limit ML20078R9171995-02-13013 February 1995 Proposed TS Section 6.5.2.8 & 6.5..3.1,reflecting Deletion of Audit Frequency Requirements ML20078L1201995-01-26026 January 1995 Rev 13 to Pump & Valve IST Program for Daec ML20077A9191994-11-10010 November 1994 Proposed Tech Specs Re Offgas Radiation Monitors ML20149G9241994-10-28028 October 1994 Proposed Tech Specs,Deleting Plan for Integrated Scheduling of Plant Mods ML20076K9591994-10-20020 October 1994 Revised Proposed TS to TS Changes RTS-246 & RTS-246A ML20072F1651994-08-15015 August 1994 Proposed Tech Specs Increasing Allowable Main Steam Isolation Valve & Deleting TS Requirements Applicable to MSIV LCS 1999-09-15
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RTS-289 Attachment 2 to
. . NG-96-0063 Page1 of1 PROPOSED CHANGE IRTS-2891 TO THE DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS The holders of license DPR-49 for the Duane Arnold Energy Center propose to amend Appendix A (Technical Specifications) to said license by deleting cenain current pages and replacing them with the attached, new pages. The List of Affected Pages is given below.
LIST OF AFFECTED PAGES l
3.3-5 i i
SUMMARY
OF CHANGES:
The following list of proposed changes is in the order that the changes appear in the Technical Specifications (TS). ,
Page Description of Changes 3.3-5 Changes the average control rod scram insertion time limit specified in Section 3.3.D.1 for rod position 46 from "0.35" '
seconds to "0.44" seconds.
3.3-5 Changes the average control rod scram insertion time limit for the three fastest control rods in all groups of four control rods in a 2X2 array specified in Section 3.3.D.2 for rod position 46 from "0.37" se.conds to "0.44" seconds.
9602050200 960130 PDR ADOCK 05000331 p PDR
DAEC-1 LIMI' TING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT l 3. During operation with Limiting 3. When a Limiting Control Rod Pattern Control Rod Patterns, either: exists and one RBM channel is.
l l a. both RBM channels shall be OPERABLE, inoperable, an Instrument I or Functional Test of the operable RBM channel shall be performed within l b. with one RBM channel inoperable, control rod withdrawal shall be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to rod withdrawal.
blocked within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless OPERABILITY is restored within this time period, or l c. with both RBM channels inoperable, control rod withdrawal shall be blocked until OPERABILITY of at least one channel is restored.
1 D. Scram Insertion Times D. Scram Insertion Times l
- 1. The average scram insertion time, 1. After each refueling outage all based on the deenergization of the OPERABLE rods shall be scram time scram pilot valve at time zero, of tested from-the fully withdrawn all OPERABLE control rods in the position to the drop-out of the reed reactor power operation condition switch at the rod position required shall be no greater than: by Specification 3.3.D. The nuclear i system pressure shall be above 950 psig (with saturation temperature). l*
This testing shall be completed-Average Scram prior to exceeding 40% pow.er.
Rod Insertion During all scram time testing below Position Times (Sec) 20% power, the Rod Worth Minimizer shall be OPERABLE or a second 46 -1H W O N Y licensed operator shall verify that 38 . 7 the operator at the reactor console 26 1.86 is following the control rod 06 3.41 program.
- 2. The average scram insertion times for the three fastest control rods of all groups of four control rods in a 2 x 2 array shall be no greater than:
Average Scram Rod Insertion Position Times (Sec) 46 4dm O.W 38 .1 26 1.97 06 3.6R
- 3. Maximum scram insertion time to rod position 04 of any OPERABLE control rod should not exceed 7.00 seconds.
Amendment No. 720,J A2,180 3.3-5 MAR 111992
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RTS-289 Attachment 3 to
. NG-96-0063 I
Page1ofI l
. SAFETY ASSESSMENT '
i
- By letter dated January 30,1996, IES Utilities Inc. submitted a request for revision of the Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC). The l
- proposed amendment would increase the required average control rod scram insertion j time to position 46 from 0.35 seconds to 0.44 seconds for all Operable control rods and j increase the required average control rod scram insertion time to position 46 from 0.37 to j 0.44 seconds for the three (3) fastest control rods for all groups of four (4) control rods in
- a 2X2 array.
Assessment:
i The amount of reactivity inserted at rod position 46 (corresponding to 5% of rod !
insertion) is small and the time required to insert this amount of reactivity is not j explicitly considered in the plant transient analysis. A generic BWR/2-5 study l performed on behalf of the BWR Owner's Group has demonstrated that relaxing the l 5% rod insertion time requirement had a negligible impact on plant transient I performance. We have confirmed that this generic study is applicable to the DAEC. I Increasing the allowable average scram insertion time to rod position 46 for all Operable control rods in addition to increasing the allowable average scram insertion I time to rod position 46 for the three fastest control rods in any 2X2 array would still demonstrate that the CRD system will perform its intended function.
Consequently, based upon the above, we have concluded that the proposed mereases m j average control rod scram insertion time for all Operable control rods to rod position 46 i to 0.44 seconds and for the three fastest control rods for all groups of four in a 2X2 array to position 46 to 0.44 seconds are acceptable.
1 i
RTS-289 Attachment 4 to NG-96-0063 Page1of1 ENVIRONMENTAL CONSIDERATION 10 CFR Section 51.22(c)(9) identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perform an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and (3) result in a significant increase in individual or cumulative occupational radiation exposure. IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR Section 51.22(b),
no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Attachment I to this letter, the proposed amendment does not involve a significant hazards consideration.
- 2. The proposed amendment includes changes which have been evaluated generically for BWR/2-5 plants to have a negligible impact on plant transient performance. This change does not significantly impact any safety analysis or threaten any safety limits. This change will not adversely affect normal or transient plant operation. There will be no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
- 3. The proposed amendment includes changes which have been evaluated generically for BWR/2-5 plants to have a negligible impact on plant transient performance. This change does not significantly impact any safety analysis or threaten any safety limits. This change will not adversely affect normal or transient plant operation. There will be no significant increase in either individual or cumulative occupational radiation exposure.
RTS-289 Attachment 5 to NG-96-0063 Page1ofI O GENuclearEnergy GeneralBecueCompany tis cunnerAmve.sanJose.cA sstzs SIE~-96001 DRF A12-000384 cc: Matt Brandt, Duane Arnold.
January 4,1996 LS. Post, GE R. E; Kingston, GE~
To: Ron Ballou, GE From: Nader Sadeghi
Subject:
Slow ScramTunes at 5% Insertion Duane Arnold requested that GE evaluate the importance of the degradation of 5%
insertion time. The purpose of this letter is to respond to this request.
The degradation of the 5% insertion time for the core average does not significantly impact any safety analysis or threaten any safety limits. The 5% insertion time has been relaxed for BWR/2-5s as part of the standard Improved Technical Specification (ITS) upgrade (EAS-56-0889, BWR/2-5 Scram Time TMhnical Specification, August 1989).
The change in the 5% insertion scram time to 0.44 see was generically assessed for the-most limiting transient (load rejection without bypass) to have less than a 0.01 impact on-the ACPR. This impact is considered negligible in view that the operating limit MCPR is based on average scram speed, but faster mds insert more scram reactivity than the slower rods. Meeting the 20% insertion time is more important in its effect on transient performance than meeting the 5% insertion time requirement because the peak total reactivity of the load reject without bypass event occurs sometimes after 0.44 sec. The ODYN Option B type requirements only have the 20% insertion point.
In the event that the original 5% insertion time required by Tbchnient Specifications is not met, the safety limit MCPR would not be exceeded if the insertion time to 5% does not exceed the ITS value of 0.44 see and the 20% insertion does not exceed its limit.
Please call me if there are any questions on this information.
.a sa 4 L:.
N. Sadeghi. Senior Engineer (408) 925-1162, M/C 747