Similar Documents at Byron |
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209B7411999-06-30030 June 1999 Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20204H9781999-03-23023 March 1999 Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations ML20204H4291999-03-22022 March 1999 Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20202G9361999-01-30030 January 1999 Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex ML20198N3471998-12-29029 December 1998 Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values ML20198N2041998-12-29029 December 1998 Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements ML20198A0811998-12-14014 December 1998 Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys ML20196G6611998-11-30030 November 1998 Proposed Rev to Improved Tech Specs Section 3.1 ML20155J2051998-11-0505 November 1998 Proposed TS Converting to Its,Rev R ML20155J0041998-10-30030 October 1998 Proposed Tech Specs Section 5.6.2, Fuel Storage Drainage, to Identify Sf Pool Level Sufficient to Ensure SRP Acceptance Criteria ML20154S5011998-10-18018 October 1998 Proposed Rev N to Improved TS Section 3.7 ML20154M5281998-10-15015 October 1998 Revisions K,O & P of 961213 ITS Submittal ML20154A8881998-10-0202 October 1998 Proposed Rev L to Improved Tech Specs Section 3.8 Closeout ML20153G4331998-09-25025 September 1998 Revs J & M to Tech Specs Sections 3.6 & 5.0,converting to Improved Tech Specs (Its),Final Closeout Package ML20236W5851998-07-31031 July 1998 Proposed Rev G to Sections 3.1 & 3.2 of Improved Tech Specs ML20237B6391998-07-30030 July 1998 Proposed Rev H to Section 3.5 of Improved Tech Specs ML20237E9971998-07-21021 July 1998 Rev I to Proposed Improved Tss,Section 3.9 Re Final Closeout ML20237B7021998-07-0909 July 1998 Proposed Improved TS (ITS) Section 3.3 Issued as Result of Removing Generic Change Traveler TSTF-135,Rev E from ITS Submittal ML20236H6531998-07-0202 July 1998 Rev F to 961213 Improved TS Submittal,Containing Final Package Closeout for Improved TS Sections 1.0,2.0 & 3.0 ML20248M1491998-06-0101 June 1998 Proposed Tech Specs Bases Page B 3.8-58b,converting to Improved Tech Specs ML20248K7361998-05-31031 May 1998 Commonwealth Edison Bnps Unit 1 Cycle 9 Startup Rept ML20248C5511998-05-29029 May 1998 Proposed Tech Specs Bases Section 3/4.4.4, Relief Valves, Specifically Crediting Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS at Power Accident ML20217Q8521998-05-0101 May 1998 Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments ML20216D9431998-04-0909 April 1998 Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66 ML20217E1891998-03-24024 March 1998 Proposed Tech Specs Surveillance Sections & Bases Allowing Util to Defer 10CFR50,App J,Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20217B2681998-02-14014 February 1998 Proposed Rev D to ITS ML20199J7581997-12-31031 December 1997 Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 ML20198C3181997-12-30030 December 1997 Proposed Tech Specs 3.7.1.3 Re Condensate Storage Tank ML20203M5921997-12-17017 December 1997 Proposed Tech Specs,Rev C Changes Improved TSs 3.0,3.3,3.7, 3.8 & 5.0 as Result of Removing Generic Change Traveler TSTF-115 from Improved TS Submittal ML20203D0361997-12-0909 December 1997 Proposed Tech Specs Pages Correcting Errors Discovered in Current TS W/Regards to Total RCS Volume & Correction to Increase in RCS Volume Associated W/Unit 1 Replacement SGs Accounting for Hot Conditions ML20199A4751997-11-0707 November 1997 Proposed Tech Specs Pages Revising TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.c & Bases to Allow Performance of 10CFR50 App J,Type a Testing 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 ML20198M2621997-10-31031 October 1997 Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12 ML20217K4461997-10-21021 October 1997 Proposed Tech Specs Re Boron Credit in SFP ML20202F4561997-10-10010 October 1997 Proposed Tech Specs,Deleting Lower Flow Rate Requirement Associated W/Nonaccessible Area Exhaust Filter Plenum & Fuel Handling Bldg Ventilation Sys ML20211D9421997-09-24024 September 1997 Proposed Tech Specs Revising Allowable Time Interval for Performing Turbine Throttle Valve & Turbine Valve SRs Requirements from Monthly to Quarterly ML20216G8541997-09-0808 September 1997 Proposed Tech Specs Change to TS 4.5.2.b & Associated Bases Bringing Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20217H6071997-08-0707 August 1997 Proposed Tech Specs Pages,Revising Bases for Proposed Improved TS SR 3.8.6.1 & 3.8.6.3,to Indicate That Correction for Level Is Not Required When Battery Charging Current Is Less than 2 Amps for Gould & Less than 3 Amps for C&D ML20148P7721997-06-30030 June 1997 Proposed Tech Specs,Revising TS 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Permanently Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3081997-06-24024 June 1997 Proposed Tech Specs,Changing TS for ECCS Venting ML20141B7781997-06-17017 June 1997 Proposed Tech Specs Revising TS Sections 3/4.6.1.6,4.6.1.2, 6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a, Which Requires Utils to Update Existing Containment Vessel Structural Integrity Programs ML20148J3231997-06-0909 June 1997 Proposed TS Reflecting Latest Rev of Waste Gas Decay Tank Rupture Accident Dose Calculation ML20140D0081997-05-31031 May 1997 Proposed Tech Specs,Revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8991997-05-24024 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K3381997-05-23023 May 1997 Proposed Tech Specs Requesting Enforcement Discretion from Compliance W/Ts 4.5.2.b.1 Requirements of Venting of Emergency Core Cooling Sys Pump Casings & Discharge Piping High Points Outside of Containment ML20141K0011997-05-21021 May 1997 Proposed Tech Specs Relocating Reactor Vessel Surveillance Program Capsule Withdrawal Schedules IAW GL 91-01 ML20148B6151997-05-0606 May 1997 Proposed Tech Specs,Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0501997-04-25025 April 1997 Proposed Tech Specs Revising Primary Containment & Reactor Coolant Sys Volume Associated W/Unit 1 Steam Generator Replacement ML20137S5341997-04-0707 April 1997 Proposed Tech Specs 3/4.8.2 Re D.C. Sources 1999-06-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20202G9361999-01-30030 January 1999 Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex ML20217Q8521998-05-0101 May 1998 Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments ML20199J7581997-12-31031 December 1997 Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 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 ML20198M2621997-10-31031 October 1997 Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12 ML20137B9221997-02-28028 February 1997 Revs 1.3 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.4 to Chapter 11, Radiological Environ Monitoring Program & 1.4 to Chapter 12, Radioactive Effluent Technical Standards, Odcm,Byron Annex ML20116L4691996-08-12012 August 1996 Rev 1 to 1595-00305.30000, Byron Station Units 1 & 2 Second Interval Inservice Insp Program Plan-NRC Submittal ML20100Q1761996-03-31031 March 1996 Rev 1.3 to Odcm ML20134N3051996-03-25025 March 1996 Rev 1 to 10CFR50.59 Se ML20095J6131995-12-31031 December 1995 Rev 0 of IST Plan Pumps & Valves Byron Nuclear Generating Station Units 1 & 2 ML20129B7051995-09-22022 September 1995 Rev 0 to Byron/Braidwood Units 1 & 2 SG Eddy Current Analysis Guidelines ML20092B1051995-09-0202 September 1995 Rev 0 to SG Structural Insp Plan in Support of Braidwood 1 & Byron 1 3.0 Volt Ipc ML20091M8641995-08-25025 August 1995 Verification Analysis for Computer Program ML20072R4111994-09-0909 September 1994 Rev 13 to IST Program Plan for Pumps & Valves ML20076L7461994-08-31031 August 1994 Rev 1.2 to Odcm,Chapters 10,11,12 & App F ML20072Q1971994-08-29029 August 1994 Proposed Rev 0a to Section 7 of ISI Program Plan for Pressure Testing ML20083N8701994-07-31031 July 1994 Rev 7 to Byron & Braidwood Stations Units 1 & 2 Eddy Current Analyis Guidelines ML20064H9101994-03-11011 March 1994 Rev 12 to Section 4.0 of IST Program Plan for Valves ML20064H9011994-03-11011 March 1994 Rev 10 to Section 3.0 of IST Program Plan for Pumps ML20063F8721994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Byron Station ML20064N3281993-12-20020 December 1993 Rev 0 to Operating Parameter Uncertainties for Byron/ Braidwood Revised Thermal Design Procedure 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 ML20101B0301992-04-21021 April 1992 Corrected Rev 0.F to Page 11-19 of Chapter 11 of ODCM ML20090A8541992-02-27027 February 1992 Rev 11 to Section 4.0 of Inservice Testing Program Plan for Valves ML20090H7651992-02-27027 February 1992 Rev 0.D to Odcm ML20024H4041991-05-23023 May 1991 Rev 9 to Inservice Testing Program Plan for Valves. ML20024H4031991-05-23023 May 1991 Rev 8 to Inservice Testing Program Plan for Pumps. ML20065Q1601990-12-0707 December 1990 Rev 9 to Inservice Testing Program Plan for Valves ML20065Q1581990-12-0707 December 1990 Rev 8 to Inservice Testing Program Plan for Pumps ML20073C1381990-12-0404 December 1990 Inservice Insp Program Plan for Pressure Testing, Section 7 ML20059J0171990-08-31031 August 1990 Errata to Rev 0.A to ODCM Figure 11-4, Ingestion & Waterborne Exposure Pathway Sample Locations ML20058E8601990-04-30030 April 1990 Rev 55 to AOP 1BOA PRI-10, Loss of Rh Cooling Unit 1 ML19354D4391989-10-25025 October 1989 Revised Procedures,Including Rev 11 to Bzp 200-A1, Pwr... Action Levels (Eals) & Rev 2 to Bzp 210-A1, PWR Emergency Action Level (EAL) Philosophy. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing ML20247M7801989-04-0404 April 1989 Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985 ML20247M8201989-02-0101 February 1989 Rev 1 to 2BWEP-0, Reactor Trip or Safety Injection Unit 2 ML20247M8011989-02-0101 February 1989 Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8661989-02-0101 February 1989 Rev to 1BEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8741989-02-0101 February 1989 Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2 ML20247M7661988-10-0101 October 1988 Rev 01 to RT-1 PWR Simulator Real Time Test ML20248B1211988-03-11011 March 1988 Rev 3 to 2BOA ENV-1, Operation During Tornado or Sustained Wind Conditions-Unit 2 ML20235T6421987-12-31031 December 1987 Rev 11A to Offsite Dose Calculation Manual. Rev 11B to Table of Contents Also Encl ML20236B7981987-12-31031 December 1987 Rev 11B to ODCM Table of Contents for Section 8.0 1999-04-30
[Table view] |
Text
W 1
1
- M nudeor power servkas.kx,
- M WORK PROCEDURE NO. DATE REVISION
3.0.9 PROJECT
SYRON STATION 11/19/86 G l
EXHIBITS 1
I TITLE: AS-BUILT PIPING SUBSYSTEM PREPARATION Exhibit 3.37 (Prior to Final Reconcilia' ion of N#"I** **Y **'
*" #"" I Exhibit 3.39 Subsystem Punch List SCOPE OF REVISIONr Revised Exhibit 3.54 E hibit 3.40 Package Review Checklist Exhibit 3.54 NPS H-1000 Drawings, Sheets 1, 2&3
$k21S$o$k$IOS$4 APPROVAL SIGNATURES REVISION a 81
\}3 & l ' ~ l 4 ~ 8 f*
APPROVED , //' /f 4 _
MANAGER Q. A. // oZo - sio
(
kY)
'. - C' D vg nUCfec.t pcWer services,Inc.
nos ,
MEYIS!CN ?!71.E: W3BC PROCEDURE 8
AS-BUILT PIPING SUBSYSTEM PREPARATION CATES 11/19/96 MAWL __
3.0 REFERENCES
3.1 Sargent & Lundy Project Instruction P[-88-26; 3.2 Sargent & Lundy Component Support installation Guidelines and Tolerances (M-919 Series Drawings);
3.3 United States Nuclear Regulatory Commission IE Bulletin No. 79-14, Rev.1 with Supplements 1 & 2; 3.4 NPS Procedure 6.0.1 4.0 RESPONSIBILITIE5 4.1 The Project Manager is responsible for the implementation of this
4.2 The Project Engineer is responsible for the day-to day administra-tion of this procedure.
4.3 The Assistant Project Engineer is responsible for the day-to-day implementation of this procedure and the accuracy and adequacy of the data assembled.
5.0 GENERAL 5.1 NPS shall be responsible for preparing and reviewing AS-Built Sub-system data prepared in accordance with the NPS-H-1000 series draw-ings (Exhibit 3.54) and for transmitting the data to CECO (for record) in accordance with NPS Procedure 6.0.1.
5.2 As-Built packages are normally processed and transmitted in two phases: (1) - 707. (when at least 70'" of the pipe hangers in the subsystem are installed), and (2) - 100', (when all pipe hangers, piping and related piping components are installed). Some as-built packages are transmitted only at the 100". chase.
5.3 Drawings and documents used by NPS personnel under the scope of this procedure will be provided and controlled by Hunter Corp., unless otherwise noted.
S.4 The NPS. Subsystem Punchlist Summary will indicate which supports are required to bring tne subsystem to a 70* or 100% installed support condition. The punchlist summary will also indicate pending Engi-neering Change Notices. Field Problems and/or Material Procurement Problems, and will identify the grouc or discipline responsible for resolution.
C1 D W
aps nUCICct ;3CWCr SCrYICOS, Inc.
MD ISIOi TITL.Kr -
Mlsut Mets 1JM
- O .0.9 AS-BUILT PIPING SUBSYSTEti PREPARATION QATIJ 11/19/86 PME L W L 5.5 SUBMAN (Subsystem Management Report) is the method used to monitor progress of the "79-14 As-Built Program". This report lists all subsystems required for As-Built and indicates the phase of completion for each.
6.0 PR0CEDURE 6.1 Subsystem Package Assembly 6.1.1 The subsystem package may include the following applicable documents:
(a) Piping As-Built Isometric Drawings (two bluelines each);
(b) Pipe Support Orawings and all related Field Change Requests (FCP's); Engineering Change Notices (ECN's),
and Hanger Field Problems (HFP's);
(c) Containment Penetration Details (one blueline, if the detail is already as-built; two bluelines, if not);
(d) Anchor Sleeve Detail, with Cover Plate Drawings (two Bluelines each);
(e) Embedded Pipe Sleeve Details; (f) Welded Attachment Details (provided for unused Class "A" attachments only);
(g) Hanger As-Built Sumary Sheet (Exhibit 3.37);
(h) Package Review Checklist (Exhibit 3.40).
6.2 Subsystem Boundaries 6.2.1 The subsystem boundaries will be marked on the Isometric by the Package Preparation Group (PPG). The package reviewer will verify that the location of the boundaries are correct.
The A/E's analytical model must be reviewed to determine subsystem boundaries.
w, - - - ---- -----m,a- - , - - -- - - - , , , -- --mw, -
---v -,--
M cx o w
nps nucicer power sGrY" CSS, Inc.
unsun mu, == nam:same '
- 8 AS-8UILT PIPING SUBSYSTEM PREPARATION 3.0.9 11/19/86 Y 6.3 Sumary Sheets 6.3.1 Sumary Sheets (see Exnibit 3.37) are prepared by the PPG in accordance with the following guideline:
6.3.1.1 A Sumary Sheet is given in the package showing all information relevant to the subsystem, i.e.
list of all hangers; all HFP's, ECN's and FCR's for those hangers; isometric drawings; penetra-tion / sleeve drawings and cover plate detail draw-ings. All supports which are part of the sub-systems' boundary, including void or deleted supports, shall be noted.
6.3.2 The following Support Status Codes shall be used for each support:
Supp. Stat. Description
! =
Installed
=
NI Not Installed V = Void 6.3.3 The following Walkdown Codes shall be used for each support.
Code Description
- 1. Support installed per Design
- 2. Deleted support is removed
- 3. Deleted support is installed 4 Minor Redesign is required
- 5. fiajor Redesign is required
- 6. Not installed
'7. Installed but not QC accepted 6.4 Package Review Check Lists 6.4.1 Every Isometric (blueline) used for as-built walkdown and review purposes will have an As-Built Package Review
cx a
. . t)g nUC OC,t pCWCr SCfYICCS, IOC.
nps I
REY! alt 34 71%Es MORK M OCEDUAE AS-BUILT PIPING SUBSYSTEM PREPARATION l Mus 5 6 .
~~~
11/19/86 Checklist (Exhibit 3.40) attached. Personnel in the PPG will be responsible for completing the Package Preparation portion of the checklist and to sign-off and date in the applicable spaces. The same responsibilities apply to walk-down personnel performing the as-built walkdown, the reviewer and the final reviewer.
6.5 As-Built Walkdown 6.5.1 As-Built dimensions and rattle points not oreviously documented by Hunter 0.C. during installation, or a previuus S.A.T. letter will be obtained by actual field measurement for all dimensions shown on the NPS-H-1000 series drawings.
The NPS-H-1000 series drawings shall contain a list of acceptable measuring devices.
- 6.5.2 All piping supports which are not completely installed, not 100% QC accepted to the current design documents or installed supports requiring rework, should be shown on the Subsystem Punch List (Exhibit 3.39) with the appropriate information shown indicating work to be done. If a non-installed support cannot be installed within tolerance (S&L N-919 series drawings) at the location shown on the isometric, the support will be marked as " Redesign" on the Subsystem Punch List. The Sub-system Punch List will indicate the required number of supports
- needed to bring the Subsystem to a 70% minimum installed sup-port condition. The Subsystem Punch List will be forwarded to the Piping Contractor for resolution.
6.5.3 Rattle Points will be reported in the manner described on NPS-H-1000 drawing, sheets 1 and 2 (Exhibit 3.54). Rattle point infomation noted during the 70% and 100% walkdown will include: the distance, location, orientation, type of interaction item, and whether or not the pipe is insulated.
Note: these values can be considered precise only at the time of walkdown.
6.5.4 All measurements are to be taken by NPS engineering and Hunter QC qualified personnel.
6.5.5 All measurement tolerances will be consistant with those specified in the S&L Project Instruction PI-BB-26.
r - -- . , . _ -
M CX X ')
vy nucioar pswcr scrylecs,Inc.
aps MYISION TITLE: lett MIOCENE NO.s a NO.s 3.0.9 AS-BUILT PIPING SUBSYSTEM PREPARATION '
QRTEs -
11/19/86 Mg 6 yL l 6.6 Review 6.6.1 The reviewer will review the work performed by the package preparer and the walkdown personnel, making sure that the information provided is complete and concise.
6.6.2 The reviewer will also insure that the as-built informa-tion is properly transferred to the original piping iso-metric by comparing the revised blueline cooy with the field walkdown copy.
6.7 Final Review 6.7.1 The Final Reviewer performs a cursory review of the As- .
Built Package for completeness and accuracy. This review is perfonted by the appropriate Team Leader.
e
TITLE: TABLE OF CONTENTS - PROJECT PROCEDURE MANUAL REVISION: X DATE: 11/19/e6 PAGE: 2 of 3 gEg,Ilgg, M R.,,Ey,, M 3.0.11 Design Control-Field Change A 11/23/82 Requests 3.0.12 As-Su11t Pipe Support Reactions A 06/13/85 Unit 3.1.1 Requests for Information B 07/20/81 3.1. 2 Action Ites Ccntrol 8 03/04/82 3.1.5 Computer Program & Verification 3 04/04/82 S. 0 PROCEDURES.IMSTRUCTIONS AND DRAWINGS
- 5. 0.1 Work Procedure Preparation. Review and Approval C 10/01/84
- 5.0.2 Control & Distribution of Byron Pro]ect Projects Procedures Manual & A 10/01/84 Procedure Revistons
- 6. 0 00Cunggt_ CONTROL 6.0.1 Document Control H 08/30/85 6.0.3 Document Control-Chicago E 10/30/86 15.0 HQHCQHEQRHARCE QQMTROL 15.0.1 Identification & Control of Monconformances E 04/24/85 15.0.2 Contrel of Issued Nonconformances C 04/26/85 15.0.3 Control of Design Errors D 04/18/84 16.0 CORRECTIVE ACTION 16.0.1 Corrective Action Request C 04/26/85 17.0 GuALITY ASSURAMCE RECORDS 17.0.1 NPS Syron Site Quality E 05/15/86 Assurance Records 17.0.2 Microfilming & Document Storage D 08/30/85 ,
i 1
{ MA
< )! -
3 11 11 I g j
e d E ,
. N ii ! ((k i s ej \
s=
- e. i 5'
$ kl V -
2 l igj ij lla{i 9
e
\
m ! $$g$ha5 ,
t i.
i, ap y::,:::.p.
%, 1
$lR
-- i% '
+
k t ill H g
gal x3; ya8
- i, cr
.J . CJ
'\ '\
- 1. , , ,
4 s, a
j q g db 3
.s s x v
\
/m...- .
,, p
'i-g
\
i
- 3l.
'h':, ' O '
/ g il
\ \\
\
4 '
,/
4*11 I gli t hit ui< 48lly 4 *i
,t L m.7ff_p ~
/ 4 it
\
/__ o \
xg%g . > t
- w, 'd kg
,, 4( ;
ik!
1
q $5 m 1, I n
, . l
, s ma,mm, a m m
./ ,,
, . . .e . . . . . . . m. ...idm.
. . . . hmiisa!!,,
. . . . . ....uu y 2, s........e..e............
5555 $ u,5 $ $ u,uidi$ $ $ $ $.......... 4i ssid ui444 s u s44 u
.e s. a. E $ $ .$. , , , , j , , , , , , , , ,
t d 6t Q
. [' E
>. st!h!!sh!!$!!!!!!ht!$th!!!h!)h))dhth
. .......... m = ....... ... ......
35 ]95 u.. u u u. u. . u. . u.. u. u. u.. u. . u. . u u a.. u.. u. . u.. u. ..u.a.s
..... . . .... . u. . u. .s, 6 3 /
< ?.hwtHYdinhi)MW6MnntwiWMniM) 2
=
- e. .
me .I
[ >. . . . . . . . . . s . 5 m . . . .*. . a.
x:
sv .
.. =. .. . a u..... a u. u. . u. ...u. . u. . u u. . u. . u. . u. . u. . u. . u. u. . u. . u. . w. . i.
g
'g .
f 3 INUND hN3N3 3NNNNNkNNk3 SUN N
k ,Nh kh lg ( (
\+ g h l
- t. = - r-- .~, e,u.r
- u. . u. . u. .._u. . .. u._
u= .n r ==(,d?m==== ,
. m..1.. . . u. . . . u. . u. . . . u. . u. . u. . u. . m. . u. . u. . u. .
$ e % % %5 W W W W' % % %h%*an H W N Whu w w N
> ge 4 4
.Q I p Q
l v
e j r I IkI b I kk bbb $
!! I-m-- "r = =:= = n= = n '""" of l
'l ,iS (I i
S M " M' M M M Mt M M MtM M M Mt M M M Mit M y g fg g MHWWAHHiWGihiihiMMMihhihihi 1
l l 1; : 1.
thm d!!hs Bhd!kt hdhht!!,,lddh
, I.;a. r ntr== n=== . m mi
- u. u uu. . u.. u...u. u.... u. . ...u. - . u..
u.uu- . u. n n =
u u u........
3 J l . .... . u.. u u.. . %
t l, 8 #
g NUYONihhiNNNINbNbbbbibb b '
I. '} -
_g9 P
=
i h t ul ?
,Ib, i.,..u.....ld..kly
- .. ..i m m = =
Ohhh!!hm B..ib.b s u. . s. ;. s. u. . u. . n. . s. s. ;. 4. s. s. i. s. s. u. . n. . u. . n. . s. u. . n. .yt o t 3 m.
- n. . u. . n. . u. .
( '3DWaDNSUN3NSDNNNNNMEN8YEND hhhE6Mddhdh!dhhdhh IhN) UN)+Nh Du..
. . .S. .=u.=. u. =u .=uu.=u. =. .nu. n. . =u..u..,.,.
. u. . . . . =u.. u.. u.. =u.. : 4 u. =u
.u l 3- gc
.wwwwswwwwNwwwhuwwunn%%%
j , .;
+
t
, ,. g C k 3 5 f
..a -
e j
c I , / m g g, g.g 7< c- 9
- j' 52 i
. I
.'/
- l't]gi =
l l i.
l' i
l (- !
8 It 8 i
fl 1,j1$j i ! - l l h 39 I .
, (
O I
.c s 4
!< l l ! E b ! ! 1 1 l $
}i i l-d a l' I i >
i !
F 1 s a a al a s [ i,,
Ii l l !s !
f l !,-
di l l!l h ll!M i !l'lllllIllIfI l' lb l $ ! !! L[ I L II l
11
! ! !ll i i Pi i! ! ! !
pgj . ;; jlj t ld
!. ig . . . . . . . . . . . . llhli a 11 !hl l lu 2
i -
_ _ _ _ _ _