|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999
Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A
ML20210R8281999-08-13013 August 1999
Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2
ML20209J2321999-07-16016 July 1999
Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs
ML20196K1941999-06-30030 June 1999
Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual
ML20209C2951999-06-29029 June 1999
Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205L2631999-04-0505 April 1999
Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in
ML20205J9321999-03-30030 March 1999
Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months
ML20205J9741999-03-30030 March 1999
Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info
ML20205J9911999-03-30030 March 1999
Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20199L6921999-01-21021 January 1999
Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR
ML20199L7741999-01-21021 January 1999
Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem
ML20199E0361999-01-12012 January 1999
Proposed Tech Specs Section 3.10, Fuel Handling & Storage, Eliminating Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS
ML20196H4571998-11-30030 November 1998
Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days
ML20196F6451998-11-30030 November 1998
Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document
ML20196K5861998-11-0505 November 1998
Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station
ML20155D8091998-10-29029 October 1998
Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2
ML20195J9041998-09-24024 September 1998
Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept
ML20151S7991998-08-31031 August 1998
Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20236W8401998-07-31031 July 1998
Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20247D7761998-05-0505 May 1998
Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20246Q3481998-04-29029 April 1998
TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C
ML20217G1481998-03-27027 March 1998
Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20216C6381997-08-29029 August 1997
Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates
ML20196G8781997-07-18018 July 1997
Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program
ML20148K6141997-06-0505 June 1997
Proposed Tech Specs,Updating Revised TS to Format Consistent W/Recently Approved TS Upgrade for DNP & Proposed Other Miscellaneous Changes Re Decommissioning Status of Unit 1
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20196G0271997-05-0101 May 1997
Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test
ML20138G3321997-04-29029 April 1997
Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing
ML20138B3231997-04-21021 April 1997
Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20137G3981997-03-26026 March 1997
Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment
ML20135F7321997-03-0303 March 1997
Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E
ML20135D9461997-02-24024 February 1997
Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c
ML17187A7991997-02-17017 February 1997
Proposed Tech Specs 3/4.7.K & 3/4.8.C Re Issues Resulting from Comeds Efforts to Reconstitute Design Basis of Chrs
ML20138L3701997-02-17017 February 1997
Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements
ML20138L4011997-02-17017 February 1997
Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20134D2191997-01-27027 January 1997
Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K
1999-08-13
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196K1941999-06-30030 June 1999
Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20196K5861998-11-0505 November 1998
Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20116F3971996-06-30030 June 1996
Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20064G1081994-02-14014 February 1994
Quad-Cities Nuclear Station 1994 Mgt Plan
ML20063H8141994-02-11011 February 1994
Revised Procedures,Including Rev 16 to Qep 120-0, Technical Director Index 58 & Rev 3 to Qep 120-T10, Key Point History Listing
ML20063F9231994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to ODCM,Quad-Cities Station
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML20062J3681993-10-28028 October 1993
Station,Third Ten-Yr Interval IST Plan
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20099B9741992-07-27027 July 1992
Temporary Procedure Secondary Containment Preventative Maint Program
ML20102A5971992-07-0202 July 1992
Corrected Chapter 11 to, Environ Radiological Monitoring Table of Contents, Odcm,Revs 0.C & G
ML20097G0781992-05-31031 May 1992
Rev 0.G to Odcm,Chapter 11,pages 11-i,11-6,11-9,11-10,11-12 & 11-15
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20079H0121991-10-0202 October 1991
Tech Spec Upgrade Program
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20082H1951991-08-15015 August 1991
Tech Spec Upgrade Program,Proposed Amend Section 3.4/4.4, 'Standby Liquid Control Sys.'
ML20085B5901991-07-29029 July 1991
Tech Spec Upgrade Program
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20082M2261991-04-30030 April 1991
Rev 10 to Quad-Cities Process Control Program for Processing of Radioactive Wet Waste
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
ML20055E8101990-07-0101 July 1990
Rev 3 to Pump & Valve Inservice Testing Plan for Quad-Cities Nuclear Power Station Units 1 & 2
ML20058E8601990-04-30030 April 1990
Rev 55 to AOP 1BOA PRI-10, Loss of Rh Cooling Unit 1
ML20029B1981990-04-30030 April 1990
Rev 9 to, Quad-Cities Process Control Program for Processing Radioactive Wet Waste.
ML20055C3401990-02-13013 February 1990
Revised Dssp Procedures,Consisting of Rev 2 to Dssp 100-B, Rev 2 to Dssp 100-B1 & Rev 3 to Dssp 100-A2/B2
1999-06-30
[Table view] |
Text
ATTACHMENT 2 (Cont'd)
PROJECT INSTRUCTION COM-PI-010 TITLE: NUTECH - EDS INTERFACE CONTROL CLIENT: Commonwealth Edison Company
SUBJECT:
IE Bulletin 79-14 and TAP Piping Evaluation Quad Cities Units 1 & 2 Dresden Units 2 & 3 l'
l.0 PURPOSE This Project Instruction outlines the procedure to be used to control the interface between NUTECH and the other engineering consultant (EDS Nuclear, Inc.)
currently involved with piping analysis for the subject stations.
2.0 SCOPE OF NUTECH SERVICES 2.1 NUTECH will interface with EDS to obtain data necessary to account for the effects of interface loads on nuclear The inter-safety-related piping within NUTECH's scope. face will also inv transmittal to EDS. This Instruction addresses the interface requirements between the two organizations.
A complete listing of the piping This subject listingtoidentifies this inter-
- face is attached (Exhibit A).
the technical data and schedule required. The informa-tion that will be transmitted between organizations is generally categorized as follows:
2.1.1 From NUTECH to EDS o 79-14 Loads on EDS Piping o Pipe Anchor Locations
- o Support Loading 2.1.2 From EDS to NUTECH o Bechtel Walkdown Information o Support Modification Drawings I
o Pipe Anchor Loading 8212270313 021216 PDR ADOCK 05000237 PDR 0 o ff o %
APPR W//M/ _
/4-/ft
_Q AEM(NISTilATOR
~0 ATE
/O /.82 R EVISION : 0 g APPR: [//wh R OJECT MAN AGER _ r DATE APPR: M 7hs.@+ 1 TfM MHz "DATE P A GE _1_ O F 9 ENGINEERIN:: MANAGER QEP 008.1
PROJECT INSTRUCTION COM-PI-010 Revision 0 TITLE: NUTECH - EDS INTERFACE CONTROL Pace 2 of 9 2.2 NUTECH will use the data transmitted by EDS as design input. This design input will be controlled according to the NUTECH QA program requirements. NUTECH will consider all data received from EDS as final, unless otherwise noted. See Article 5.0 for the technical j data requirements.
l 2.3 Data transmitted between EDS and NUTECH will La formally transmitted and verified by receipt acknowledgment l Revision level of the information will be con-
' form.
trolled.
2.4 Initial issue od NUTECH loading data will be Revision 0.
Subsequent data revisions will be Revision 1, 2, 3, etc.
Initial issue of NUTECH drawings will be Revision A.
Subsequent drawing revisions will be Revision B, C, D, etc.
2.5 The initial issue of EDS loading data and drawings will be Revision 0. Subsequent revisions to loading data and drawings will be Revision 1, 2, 3, etc.
2.6 NUTECH and EDS will be responsible for transmitting a'll revisions of the interface data and drawings to the other organization.
3.0 PROJECT INTERFACE PERSONNEL 3 . l' EDS Nuclear Project Manager W. F. Tschudi Piping Project Engineer C. Y. Wong Pipe Support Project Engineer O. W. Zuniga 3.2 NUTECH, San Jose Office Project Manager T. J. Victorine Assistant Project Manager M. K. Mitchell Engineering Manager (Quad Cities) N. A. McClean Engineering Manager (Dresden) T. P. Khatua Piping Project Engineer (Quad Cities)A. K. Kundu Piping Project Engineer (Dresden) A. S. Herlekar Pipe Support Project Engineer T. W. Soo Hoo i 3.3 NUTECH, Chicago Office Project Manager G. T. Seeley Engineering Manager J. W. Muffett Piping Project Engineer J. A. Gavula Field Engineer A. Casill 1
1 l
1
~
PROJECT INSTRUC'ilOl4 COM-PI-010 so 0 TITLE: NUTECH - EDS INTERFACE CONTROL 9 6.2 The records generated.within NUTECH and transmitted to EDS shall be controlled and retained in accordance with the NUTECH QA program' requirements.
1 6.3 The records generated by EDS and transmitted to NUTECH will be controlled by NUTECH as design input in accordance with the NUTECH QA program requirements.
e 4
e 1
nutech
FROJECT INSTHUCTION COM-PI-010 l Revision 0 TITLE: NUTECH - EDS INTERFACE CONTROL Pace 3 of 9 4.0 COMMUNICATION RESPONSIBILITIES 4.1 Formal Communications All correspondence is to be signed by and addressed to the respective project manager for this interface. All design input will be transmitted by letter. NUTECH letter numbers will use serial numbers COM-23-XXXX (Dresden) or COM-24-XXXX (Quad Cities). All incoming and outgoing correspondence will be controlled as required by the NUTECH QA program. A receipt acknowledg-ment for data transmitted by NUTECH is required.
Mr. R. H. Mirochna and Mr. G. Frizzell of Commonwealth Edison Company will receive a copy of the. transmittal letter and all attachments for all formal dat'a transmittals.
4.2 Informal Communications All telephone conversations, telecopied data, material distributed at meetings, etc. will be confirmed by formal transmittal within 30 days. NUTECH internal ,
distribution of design input shall be in accordance with the NUTECH QA program.
5.0 TECHNICAL INTERFACE REQUIREMENTS 5.1 Exhibit A (COM- 2 4 -19 3, Revision 0) lists all of the piping affected in this interface. This listing will be used to track schedule commitments and technical data required. As such, it (COM-24-193) will be revised independently from this interface instruction.
5.2 Exhibit B consists of sample form which will be utilized to transmit piping displacement or loading information. All piping analyses input data will be
- controlled through the use of these forms whenever possible.
5.3 Exhibit C consists of a sample form which will be used l j NUTECH to transmit pipe support load information to TDS.
6.0 RECORDS 6.1 The record retention of design input shall be the responsibility of the organization which produces the design input.
I nutech
kevis5onb Pcgo 5 cf 9 EXHIBITJ
- NU'"ECM/EDS INTERFACE DATA TRANSMISSION SCHEDULE COM-24-193, Revision 0 Plants Quad Cities Unit 1 f.ine Numbers Data Transfer Cosutit Dates Note Note Note Note Note
.Braach Pipe Run Pipe SSDP A B C D E Conements P&ID SR-37/SR-39 1-1032-3* 1-1406-10" --- -- -- -- --- i Branches into 1032A & 10323 1-1032A-2* l-1006A-12* -- -- -- --- NU R CH was able to qualify these SR-37
SR-37 1-10328-2* 1-10065-12" -- -- ---- 3, SR-37/SR-39 1-1079-3* l-10143-14" X - --- -- - - - - - - Branches into 1032C & 1032D Note 1-1032C-2" l-1006C-12" X -- - --- --- NUTECH was able to qualify these SR-37
, lines without adding an anchor SR 1-10323-2" 1-1006D-12" X --- -- - - -
]
SR-37 1-1033A-3" 1-1006A-12" X --- -- ---- 10/15 SR-37 1-1033B-3* 1-1006B-12" X --- - - --- 10/15 SR-37 1-1034A-3" 1-1006C-12" X -- -- -- 9/30 SR-37 1-10348-3" 1-1006D-12* X --- -- -- 9/30 SR-37 1-1035A-3* l-1016C-1"4" X -- 10/15 SR-37 1-10358-3* l-1016D-14" X --- -- 10/15 SR-37 1-1054A-3* 1-1016A-14* X --- - - 10/15 SR-37 1-10545-3" 1-10168-14* X -- -- - --- 10/15 SR-39/SR-46 1-2340-4* l-1406-10" 9/9 11/15 - - --- ----
SR-39 1-1036-3" 1-1010-18" X ---- --- ---
9/30 SR-39 l-1011-4* l-10098-18" X - - - - -- 9/30 SR-39 1-1065-3* l-1012B-16" X ---- -- - - - - 9/30 SR-39 1-1066-3* l-1012A-16" X -- --- ---- 10/15 SR-39 1-1C67-3* ' l-1010-18" X -- --- ---- 10/15 SR-39 1-1068-3" 1-1025-20" X ---- ---- --- 10/15 SR-39 1-1086-6* l-1010-18" --- -- - - - - - - 10/30 SR-46 1-2311-4* 1-2301-16" ---- ---- - -- 10/30 SR-46 1-2325-6" 1-2302-16* --- -- 9/17 10/30 Boundary coves such that MK.I loads can attenuate SR-34-1 -- 1-1603-18* 9/7 10/20 --- --
NOTES: A) NUTECB owes EDS Anchor locations B) EDS owes NUTECH Anchor Loads C) EDS owes NUTECH "As Modified" pipe support drawings and/or line isometric and/or math model D) NUTECH owes CS Loads on EDS designed supports E) NUTECH owes EDS branch line displacements. The NU"ECM information is final but unchecked.
Checked data will follow within four weeks.
r) EDS will confirm that their analysis is not overly conservative and contact NOTECH (CBO) by 9/24 to resolve whether the EDS supports need to be installed. Ceco needs to know resolution by 10/1/82.
1 1
- _ _ _ _ . -.__ y. .._. . . , - . .
.. . hevision 0 PEga 6'cf 9 EXHIDIT As NUTEClf/EDS INTERFACE DATA TRANSMISSION SCHEDt'LE COM-24-193, Revision 0 '
Plant: Quad Cities Unit 2 t,ine Ntrhers Data Transfer Co mt Dates Note Note Note Note Note P&ID Branch Pipe ,Run Pipe SSDP A B C D E 0:xvents SR-78/SR-79 2-1079-3" 2-1406-10" X 10/15 11/15 9/17 Ba..c2 a into 1032C & 1032D '
SR-79 2-1032C-2" 2-1006C-12" X 10/15 NUm31 may be able to qualify these lines u adding an anc.W . Date SR-79 2-1032D-2" 2-1006D-12" X 10/15I applies if line can't be qualified. y SR-79/ 2-1032-3" 2-1014A-14" 10/15 11/15 Branches into 1032A & 1032B Note F SR-81-1 SR 79 2-1032A-2" 2-1006A-12" 10/15 NUM31 may be able to qualify these SR-79 2-1032B-2" 2-1006B-12" 10/15 lines wittout adiing an anchor s
. ' SR-79 2-1033A-3" 2-1006A-12" X 10/15 SR-79 2-1033B-3" 2-1006B-12" X 10/15 SR-79 2-1034A-3" 2-1006C-12 k X -- 10/15 SR-79 2-1034B-3" 2-1006D-12" X- 10/15 SR-79 2-1035A-3" 2-1016C-14" X 10/15 SR-79 2-1035B-3" 2-10160-14" X 10/15 SR-79 2-1054A-3" 2-1016A-14" X 10/15 SR-79 2-10548-3" 2-1016B-14* X 10/15 SR-81-1/ 2-2340-4" 2-1406-10" X 10/15 11/15 By 9/17 NCIIDI shall verify that SR-87 first check valve can be included SR-81-1 2-1036-3 2-1010-13" X -
10/15 11 -1 2-1011-4" 2-1009A-18" X -
9/30 SR-81-1 2-1065-3" 2-1012A-16" X - 9/30 SR-81-1 2-1066-3" 2-1012B-16" X 9/30 SR-81-1 2-1067-3" 2-1010-18" X - 9/30 SR-81-1 2-1068-3" 2-1025-20" X 10/15 SR-dl-1 2-1086-6" 2-1010-18" 10/30 SI-87 2-2311-4" 2-2301-16" -
10/30 ,
SR-87 2-2325-6" 2-2302-16* y/17 10/30 Boundary noves such that NK-I loads can attc:wate SR-81 2-1025-20" X dcme 10/15 SR-76-1 2-1603-18" 9/7 10/20 -
IUIIS: A) NUIIDI oes IDS Anchor locations
. B) IDS owes NUIIDI Anchor Ioads C) C25 owes NUIIDI "As fedified" pipe supprt drawings and/or line isometric and/or math nodel D) NUIIDI cm IDS Inads on IDS designed supports E) NUIInt owes IDS branch line displacxrnents. 'Iha NUUDI informaticn is final but unchecked.
Checked data will folicw within four weeks.
r) IDS will confirm that their analysis is net overly conservative and contact NUIIDI (CBO) by 9/24 to resolve whether the IDS supports need to be installed. CIro needs to know resolution by 10/1/82.
. .... v e n a
.' - Revision 0
- Pcga 7 cf 9 EXHIBIT A NUTECH/EDS INTERFACE DATA TRANSMISSION SCHEDULE COM-24-193, Revision 0
' Plant: Dresden 2 & 3 Line Ntaiters Data Transfer Ctruit Dates Note Note tete Nota Note PEID Branch Pipe RLn Pipe SSEP A B C D E Ctsments SR-25 2-8503-4* -
9/17 IDS made no mods
,SR-29 2-1541A-3* 2-1531-18* 10/15 SR-29 2-1541B-3* 2-1531-18" 10/15 SR-29/ 2-2340-4" 2-1522-14" x 10/15 11/15 9/17 hm nas confirmed this is SR-51 in SSDP SR-51 2-2315-4" 2-2302-16* 12/30 SR-51 2-2311-4" 2-2301-16" - 12/30 SR-27 2-1406-8" done 10/15 SR-27 2-1403-10" done 10/15 SR-25 2-1603-18" 9/7 10/20 SR-360 3-1541A-3* 1531-18" '10/15 SR-360 3-15413-3" 3-1531-18" 10/15 SR-360/ 3-2340-4" 3-1522-14" 10/15 11/15 9/17 NUHEH has omf4M this is SR-374 not in SSDP SR-374 3-2315-4" 3-2302-16" -
1/31/83 SR-374 3-2311-4* 3-2301-16* 1/31/,83 SR-356 3-8503-8* 9/17 10/15 SR-356 3-1603-18" 9/7 10/20 NOIES: Al NUHDI owes CS Anctor Iccations B) IDS owes !(JUI3I Ax. hor TMc C) IDS oes h,mni "As itx!ified" pipe support drawirns and/cr line iscretric and/or cath mcdel D) hvm.3I oms IIS TW= on IDS designed sp El NUIIDI owes IDS branch line displacurnents. The hv3I'E infennation is final but u.rh.
Cher-ked data will follow within four weks.
i l
l
= ~ . kNLOCb Revisonb Pcgo 8 of 9
,' San Josi, Calif;rnia rire no Praect Quad Cities Nuclear Power Station Commonwealth Edison Company t er Cicnt' Commonwealth Edison Company DISPLACEMENT DATA AT RUN-BRANCH INTERSECTIONS PLANT: ~
~
BRANCH PIPE LINE NUMBERi RUN PIPE LINE NUMBER:
NUTECH DATA POINT:
COMPUTER RUN ID/DATE:
LOADING TYPE : Seismic Anchor Motions (SAM)
X Y Z CASE DISPL. (IN) DISPL. (IN) DISPL. (IN)
OBE SSE XX YY -
ZZ ROTATION (RAD) ROTATION (RAD) ROTATION (RAD)
OBE ,
SSE LOADING TYPE: Thermal Anchor Motions .(TAM) ,
X Y Z DISPL. (IN) DISPL. (IN) DISPL. (IN)
XX YY ZZ ROTATION (RAD) ROTATION (RAD) ROTATION (RAD)
(1) Responses to the earthquake components X and Y are combined absolutely.
Where X, Y, Z are in the Global Coordinate System with North indicated.
1 I
Revision p Prepared By/Date of ;
. N..U..E'MCLA, { Lace
,- hddM 0 S2:a J:ce. Cclif rala Page 9 of 9
- File No Project Dresden Nuclear Power Station Owner camemoalth FAison CCEpanV Client cumurwealth Edison Cup Support ID : Dir :
~
Icad (Ibs) Displ.(x10 In)
EWr THERM OBEI OBED LEVEL A&B LEVEL C LEVEL D
- Directions are Global. X is North and Y is up (Right Handed Coord.)
Revision Page Prepared Dy/Date of l
Checked By/Date -
1
- - - - . -, .,-_..-__.;_._..__.____.__,._________.,___,.___.,_,_._,...____