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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209E0551999-07-0606 July 1999
1999 Business Plan
ML20206F2231999-04-27027 April 1999
NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station
ML20199H2771999-01-20020 January 1999
Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d
ML20206E6281998-12-31031 December 1998
Rev 17 to ODCM for Clinton Power Station
ML20196A0941998-11-20020 November 1998
Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue
ML20196A1501998-11-20020 November 1998
Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format
ML20155A5631998-10-23023 October 1998
Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys
U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998
Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)
ML20153F4201998-09-23023 September 1998
Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys
ML20237E4191998-08-24024 August 1998
Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG
ML20237C3501998-08-17017 August 1998
Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability
ML20236X0071998-07-31031 July 1998
Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20
ML20236Q4661998-07-17017 July 1998
Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4651998-07-17017 July 1998
Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4571998-07-17017 July 1998
Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test
ML20216B1511998-05-0404 May 1998
Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS
ML20217M3351998-04-27027 April 1998
Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant
ML20203D5651998-02-19019 February 1998
Plan for Excellence
ML20212C6951997-10-23023 October 1997
Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14
ML20149J1701997-07-22022 July 1997
Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition
ML20149H8991997-06-30030 June 1997
CPS Long Term Improvement Plan
U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997
Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation
ML20133F2051997-01-0707 January 1997
Proposed Tech Specs 2.0 Re Safety Limits
ML20133A5951996-12-13013 December 1996
Proposed TSs Re Transfer of Minority Ownership
ML20134M3181996-11-19019 November 1996
Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes
ML20128K0711996-10-0404 October 1996
Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1
ML20134C1631996-09-20020 September 1996
Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months
ML20116N1101996-08-15015 August 1996
Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7
U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996
Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses
U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996
Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling
ML20137A1101996-08-14014 August 1996
Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan
ML20137A1021996-07-10010 July 1996
Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan
ML20113E7261996-06-28028 June 1996
Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable
U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996
Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures
ML20108C9431996-05-0101 May 1996
Proposed Tech Specs,Implementing 10CFR50,App J - Option B
ML20107L0011996-04-19019 April 1996
Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met
ML20100H8411996-02-22022 February 1996
Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months
ML20100H7901996-02-22022 February 1996
Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V
ML20100H8171996-02-22022 February 1996
Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv
ML20100H7741996-02-22022 February 1996
Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier
ML20095G5141995-12-14014 December 1995
Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules
ML20095G6401995-12-14014 December 1995
Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys
ML20095G4791995-12-14014 December 1995
Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement
ML20117E3001995-11-0606 November 1995
Rev 18 to App V Pump & Valve Testing Program Plan
ML20094D2031995-10-27027 October 1995
Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3
ML20094D2141995-10-27027 October 1995
Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions
ML20085N0621995-06-23023 June 1995
Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program
ML20085F5961995-06-0909 June 1995
Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary
ML20087J5691995-05-17017 May 1995
Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual
ML20085J9701995-02-16016 February 1995
Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources
1999-07-06
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20209E0551999-07-0606 July 1999
1999 Business Plan
ML20206F2231999-04-27027 April 1999
NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station
ML20206E6281998-12-31031 December 1998
Rev 17 to ODCM for Clinton Power Station
ML20236Q4661998-07-17017 July 1998
Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4651998-07-17017 July 1998
Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4571998-07-17017 July 1998
Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test
ML20203D5651998-02-19019 February 1998
Plan for Excellence
ML20149H8991997-06-30030 June 1997
CPS Long Term Improvement Plan
ML20137A1101996-08-14014 August 1996
Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan
ML20137A1021996-07-10010 July 1996
Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan
ML20117E3001995-11-0606 November 1995
Rev 18 to App V Pump & Valve Testing Program Plan
ML20087J5691995-05-17017 May 1995
Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual
ML20064K5141993-10-11011 October 1993
Rev 16 to Apps Iii,Iv & V of Clinton Power Station ISI Program Manual
ML20249A6601993-04-14014 April 1993
Revised ESA-102, Electrical Engineering Std for Electrical & Physical Characteristics of Class B Electrical Cables
ML20126E4581992-11-30030 November 1992
Rev 13 to CPS IST Program,App III
ML20096G5031992-04-30030 April 1992
Rev 0 to Clinton Power Station Raw Water Treatment & Enhancement Program
ML20058L3371991-07-10010 July 1991
Rev 2 to Procedure Nragp 101-1, Nuclear Review & Audit Group Charter
ML20082J1991991-02-28028 February 1991
Rev 7 to Odcm
ML20059N2201990-08-31031 August 1990
Rev 8 to, Pump & Valve Testing Program Plan
ML20006C2071989-12-31031 December 1989
Rev 6 to Odcm.
ML20006A8321989-10-20020 October 1989
Rev 3 to Inservice Exam Plan.
ML20236A5281989-02-28028 February 1989
Rev 5 to Odcm
ML20151M7611988-07-29029 July 1988
Rev 2 to Inservice Exam Program Plan
ML20196J5731988-03-0101 March 1988
Pump & Valve Testing Program Plan
U-601006, Rev 3 to Pump & Valve Testing Program Plan & Summary of Changes1987-08-20020 August 1987
Rev 3 to Pump & Valve Testing Program Plan & Summary of Changes
ML20234E0931987-06-30030 June 1987
Rev 2 to Pump & Valve Testing Program Plan
ML20215M3511987-06-22022 June 1987
Revised Inservice Exam Program Plan for First 10-yr Interval
ML20215K5701987-02-23023 February 1987
Rev 0 to Procedure Dcrdr 5.2, Verification of Implemented Human Engineering Discrepancy Corrections
ML20212E9701987-02-0606 February 1987
Rev 8 to Station Operating Manual Maint Procedure 8451.02, Testing of Motor-Operated Valves Using Movats MOV Signature Analysis Sys
ML20212E9611987-02-0606 February 1987
Rev 10 to Station Operating Manual Maint Procedure 8451.01, Preventive Maint for Motor-Operated Valves
ML20213F3631986-10-31031 October 1986
Long-Term Inservice Exam Plan for Class 1,Class 2 & Class 3 Component Supports for Clinton Power Station,Unit 1, First 10-yr Interval Final Plan
ML20213F3861986-09-30030 September 1986
Vols I & II to Long-Term Inservice Exam Plan for Class 1, Class 2 & Class 3 Piping & Components for Clinton Power Station,Unit 1, First 10-yr Interval Final Plan
ML20213F3761986-09-30030 September 1986
Inservice Exam Program Plan
ML20214P1141986-08-15015 August 1986
Rev 7 to Operating Manual Maint Procedure 8451.02, Testing of Motor-Operated Valves Using Movats Motor-Operated Valve Signature Analysis Sys
U-600481, Rev 2 to Administrative Procedure 1888.00, Process Control Program1986-03-21021 March 1986
Rev 2 to Administrative Procedure 1888.00, Process Control Program
U-600487, Rev 1 to Clinton Power Station Inservice Insp - Pump & Valve Testing Program1986-03-18018 March 1986
Rev 1 to Clinton Power Station Inservice Insp - Pump & Valve Testing Program
ML20198S5391986-02-21021 February 1986
Rev 2 to Nuclear Station Engineering Instruction Nsei CS-4, UHS Monitoring. W/860522 Advance Instruction Change 1
ML20138Q0911985-11-30030 November 1985
Rev 1 to Offsite Dose Calculation Manual
ML20138Q9831985-11-30030 November 1985
Inservice Insp Pump & Valve Testing Program
ML20209H1541985-10-29029 October 1985
Rev 2 to Instruction PI-CP-079, Preparation,Review & Approval of Pump & Valve Operability Packages
ML20209H1611985-10-29029 October 1985
Rev 3 to Nuclear Station Engineering Dept Procedure D.22, Engineering Interdisciplinary Review & Impact Assessment for Plant Mode
ML20133N0461985-08-0707 August 1985
Rev 3 to Record Verification Program Plan,Clinton Power Station
ML20134L8921985-07-31031 July 1985
Program for Compliance W/Tmi Action Plan Item I.G.1, `Training During Low Power Testing.'
ML20134P8821985-07-0808 July 1985
Rev 1 to Procedure 1888.00, Process Control Sys. Addl Info Re ATI-VR-001-P-A, Associated Technologies,Inc Vol Reduction & Bitument Solidification Sys, Encl
ML20133N7171985-06-28028 June 1985
Revised Emergency Plan Implementing Procedures,Including Rev 1 to AP-01, Organization & Preparation of Controlled Documents & Rev 1 to Document Control
ML20128M0021985-06-14014 June 1985
Rev 0 to Procedure SPDS-DST-001, SPDS Dynamic Simulation Test Plan
ML20126C5081985-04-30030 April 1985
Offsite Dose Calculation Manual
ML20126B6741985-04-20020 April 1985
Emergency Plan Implementing Procedure EC-13, Reactor Core Damage Estimation
ML20108B4601985-02-28028 February 1985
Preservice Insp Program
ML20116M7781985-02-27027 February 1985
Rev 8 to Radiation Safety Program Augmentation CPS-1, Instructions for Augmenting United States Testing Co Radiation Safety Program at Clinton Power Station
1999-07-06
[Table view] |
Text
) SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-900-4 Revision 23 NUCLEAR PROJECTS February 198_, .
IJ OPERATING PROCEDURE Page 1 of 5 Title Visual Examination of Support I! embers and Structures for Piping, Valves, and Pumps by Direct or Remote Viewing EFFECTIVITY AND APPROVAL Revision of this crocedure became effective on 3 /2 / S2 Cther revisions of the base document may be effective concurrentfy.
SA Acprovals '
'Nritten By , Cate Tec.inical Review Date hk, tLWLLL '
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cd /r M SD /$.f 2' Manager of C.A. Date CogrJunt *irectc Date
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The following information may be used for conven/ience. CcrW t:cn of this certicn is not mandatory.
Ceviation No.
Cate Effecnve Procecure Secnon(s)
Affected l
Notes:
l 06210506 820611
'R ADOCK 05000461 PDR
SOUTHWEST RESEARCH INSTITUTE swar-Nor-9oo-'
Revision 23 February 1982 NUCLEAR PROJECTS OPERATING PROCEDURE
.H; Page 2 of 5 VISUAL EXAMINATION OF SUPPORT ME}GERS AND STRUCTURES FOR PIPING, VALVES, AND PUMPS BY DIRECT OR REMOTE VIEWING SwRI-NDT-900-4
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a complete and accurate visual examination of support mem-bers and structures for piping, valves, and pumps by direct or remote viewing in accordance with the applicable ASME Boiler and Pressure Vessel Code.
- 2. SCOPE AND APPLICATION (1) Direct and remote visual techniques for the examination of support members and structures for piping, valves, and pumps are described in this procedure.
(2) Components, parts and areas to be examined shall be as specified in the applicable SwRI Exauination Plan.
- 3. APPLICABLE DOCUMENTS The following documents, as applicable, form a part of this procedure:
(1) ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition with Addenda through Summer 1975, " Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASSE Boiler and Pressure Vessel Code,Section V, 1974 Edition with Addenda through Summer 1975, "Nondgstructive Examination" (3) swr 1 Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Examination Record SwRI-NDTR Form No.17-28, Revision 7-31-75 f 4. RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for l the preparation, review, approval, and control of this procedure.
I O
l l
swr) Form CA 3-2
SOUTHWEST RESEARCH INSTITUTE R"'7,' E -'
q February 1982 W T y
j 3 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 5 t{R .:,j' (2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan.
(3) The examiner shall be responsible for implementing the requirements of this procedure.
(4) The Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EOUIPMENT Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-2, " Procedure for Certifying Visual Examination Personnel."
The Visual Examination Acceptability Test Card shall be made from Kodak Neutral Test Card No. R-27 or an equivalent, with an 18% neutral grey side g having a 1/32-inch wide black line across its center.
Commercially available equipment shall be used as required for the per-formance of examinations by the techniques described in Paragraphs 6.2 and 6.3.
- 6. EXAMINATION METHOD 6.1 Surface Cleaning Visual examinations which require clean surfaces or decontamina-tion for valid interpretation of results shall be preceded by appropriate cleaning processes.
Examinations may be required where the surface is painted or has other types of coatings. This shall be permitted if it is determined that such coatings do not interfere with valid interpretation of results.
6.2 Direct Visual Technicue Direct visual examination shall be performed by placing the eye within 24 inches of the surface to be examined and at an angle no less than 30 degrees with the surface to be examined. Mirrors may be used to improve the angle of vision, and aids such as magnifying lenses may be used.
6.2.1 Lichting In addition to the general lighting, illum1.ation of the area to l be examined shall be provided at right angles and oblique angles to expose cracks or evidence of corrosion or erosion.
I
$wRI Form CA 30
1 SOUTHWEST RESEARCH INSTITUTE swal-Nor-900-4 O
Revision 23 February 1982
}g}q,A NUCLEAR PROJECTS OPERATING PROCEDURE
/R pg f#' f;;3) Page 4 of 5 6.2.2 Resolution Resolution shall be considered adequate when the combination of access, lighting, and angles of vision, either unaided or corrected, can resolve a black line, 1/32-inch wide, on an 18% neutral grey card placed on the surface to be examined.
6.3 Remote Visual Technique Remote visual examination may be used where conditions exist that do not permit direct visual examination. Remote visual examination may include visual aids such as telescopes, periscopes, borescopes, fiber optics, or video cameras and monitoring systems, with or without attachments for permanent recording. Remote techniques shall demonstrate the ability to provide a surface resolution at least equivalent to that obtainable by direct visual examination. Mirrors, movable lights, or rotating optics, or any combination thereof, may be employed to display cracks, surface scratches, or evidence of corrosion, erosion, misalignment, or movement.
Scanning parameters, if required for the remote visual exami-nations, shall be included in the applicable SwRI Scan Plan.
6.3.1 Resolution Resolution shall be considered adequate when the combination of access, lighting, and angles of vision, either unaided or corrected, can resolve a black line, 1/32-inch wide, on an 18% neutral grey card placed on the surface to be examined or in a situation similar to the area to be visually l examined.
6.4 Reolication i
Surface replication techniques.shall be considered acceptable provided the surface resolution is at least equivalent to that obtainable by direct visual technique.
- 7. EXAMINATION AREAS Section XI of the ASME Boiler and Pressure Vessel Code requices visual examination to provide a report of the general condition of the part, compo-nent, or surface to be examined, including such conditions as surface scre tches, wear, cracks, corrosion or erosion on the surf aces, misalignment or movement of the part or ceaponent, or evidence of leaking.
Components, parts and areas to be examiaed shall be as specified in the applicable SwRI Examination Plan.
Weld areas to be examined shall include the weld and adjacent base material for at least one wall thickness beyond the edge of the weld.
S* AI Form 0A 3-2
f i
SOUTHWEST RESEARCH INSTITUTE Swal-nnT-9oo-'
Revision 23 7C( February 1982 q NUCLEAR PROJECTS OPERATING PROCEDURE
"]:3f Page 5 of 5 The support settings of constant and variable spring-type hangers, snub-bers, and shock absorbers shall be recorded in the " Remarks" section of the SwRI Visual Examination Record.
Hangers having calibrated load indicators shall have the scale reading recorded in the " Remarks" section of the SwRI Visual Examination Record.
Hydraulic snubbers shall be examined for signs of fluid leakage at shaft seals, joints, and couplings. Shaft extensions shall be examined for scratches, cuts, or gouges.
Hanger springs shall be examined for integrity to ensure that springs have not sheared.
Pipe clamps and U-bolts shall be examined to ensure that they are securely attached to the pipe.
- 8. RECORDING CRITERIA Visual abnormalities shall be recorded on the SwRI Visual Examination Record and reported to the customer.
Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-ll6.
Visual indications detected during remote examinations shall be recorded in accordance with the customer specifications, remote equipment manufacturer's specifications, or the SuRI scan plan, if applicable.
- 9. EVALUATION Evaluation of reportable indications shall be the responsibility of the customer, or the customer's representative,-in accordance with Article IWA 3000 of Section XI of the ASME Boiler and Pressure Vessel Code. The applicable year and Addenda of the Code shall be as specified in Paragraph 3.(1) of this procedure.
- 10. RECORDS The customer shall receive copies of documents generated in accordance with this procedure in the examination report.
Documents generated in accordance with this procedure shall be stored and l
retairad as a portion of the examination report. The examination report shall be stored by the Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, in the SwRI Data Storage Facility
, for the period specified by the contractual agreement with the customer.
SwRI Form QA 3 2
