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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K0641999-09-0101 September 1999
Proposed Tech Specs,Changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2,correcting Dc Voltage & Degraded Voltage Settings in SR 3.3.6.2 & Correcting Typo in TS 5.6
ML20211G7681999-08-27027 August 1999
Proposed Tech Specs,Allowing Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities While Irradiated Fuel Assembly Movement Continues in SFP
ML20207F0261999-06-0101 June 1999
Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2
ML20195B2751999-03-31031 March 1999
Rev 0 to Rept 98-FSW-021, Corrosion Test of SG Tubes with Alloy 800 Mechanical Sleeves
ML20204H6011999-01-29029 January 1999
Age Related Degradation Insp (Ardi) Program Technical Requirements Document for Mechanical Systems
ML20196E2191998-11-30030 November 1998
Proposed Tech Specs,Allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 Repair Sleeves
ML20195K3831998-11-20020 November 1998
Proposed Tech Specs Removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section XI, Subsections IWE & Iwl,Per 10CFR50.55a
ML20195J7181998-11-19019 November 1998
Proposed Tech Specs 3.7.6, SWS, Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6
ML20155F7001998-10-30030 October 1998
Proposed Tech Specs Bases,Revs 1,2 & 3 Re List of Effective Pages for Plant
ML20154N1961998-10-16016 October 1998
Proposed Tech Specs Pages,Revising TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR
ML20198A2981998-09-15015 September 1998
Technical Procedure CP-217,rev 7,PCR 98-034, Specifications & Surveillance,Secondary Chemistry
ML20198A3131998-09-15015 September 1998
Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated
ML20236S5621998-07-20020 July 1998
Proposed Tech Specs Providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage
ML20195B2861998-06-0505 June 1998
Rev 0 to Rept 98-TR-FSW-005, Test Rept on Alloy 800 Mechanical Sleeve-Addl Qualification Testing Using Low Yield Strength Tubing
ML20217D2691998-04-21021 April 1998
Proposed Tech Specs Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging
ML20216H0831998-03-16016 March 1998
Rev 13 to Proposed TS Re Conversion to Improved TSs
ML20198A2911998-02-23023 February 1998
Technical Procedure CP-206,rev 4,PCR 98-034, Specifications & Surveillance Component Cooling/Service Waster System
ML20199J5281998-01-28028 January 1998
Proposed Tech Specs,Converting to Improved TSs
ML20198K9851998-01-12012 January 1998
Rev 11 to Proposed Tech Specs,Reflecting Conversion to Improved Sts,Per NUREG-1432
ML20198R7331997-11-0505 November 1997
Proposed Tech Specs Pages Re Rev 10 to Convert to Improved TS
ML20217K6161997-10-23023 October 1997
Proposed Tech Specs Section 3.8 Re Change Request to Convert to Improved Std TSs
ML20217K6671997-10-22022 October 1997
Proposed Tech Specs Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint
ML20198K3321997-10-20020 October 1997
Proposed Tech Specs Section 3.3 Re Change Request to Convert to Improved Std TSs
ML20217G3571997-10-0606 October 1997
Proposed Tech Specs Section 3.6 to Reflect Conversion to Improved STS
ML20217G3781997-10-0606 October 1997
Proposed Tech Specs Section 3.7 Re Change Request to Convert to Improved STS
ML20211J2751997-10-0202 October 1997
Proposed Tech Specs,Reflecting New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated
ML20217C7361997-09-29029 September 1997
Proposed Tech Specs Page Omitted from 970609 License Amend Request Re Conversion to Improved TSs
ML20211J2981997-09-18018 September 1997
Pump & Valve IST Program Third Ten-Yr Interval for Calvert Cliffs Nuclear Power Plant,Units 1 & 2
ML20210T8701997-09-10010 September 1997
Proposed Tech Specs Rev 5 to Section 3.4 of Original License Amend Application & Other Changes Identified by Personnel
ML20210K9711997-08-14014 August 1997
Proposed Tech Specs,Reflecting Removal of TSTF-115,as Well as Other Changes Identified by Plant Personnel
ML20149H5821997-07-21021 July 1997
Rev 2 to TS Sections 4.0 & 5.0,converting to Improved Std Tss,Per NUREG-1432
ML20148P7171997-06-27027 June 1997
Proposed Tech Specs Revising Wording to Support Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes
ML20141G4471997-06-16016 June 1997
Ccnpp Unit 2 Cycle 12 Startup Testing Rept
ML20141D9341997-05-0909 May 1997
Radiation Safety Procedure 1-104, Area Posting & Barricading & High Radiation Area Pre-Entry Checklist
ML20135F0441997-03-0606 March 1997
Proposed Tech Specs,Superceding Previously Submitted Marked Up Pp for ABB-CE Sleeves.New Info to Be Incorporated in Updated Licensing rept,CEN-630-P,Rev 01, Repair of 3/4 OD SG Tubes Using Leak Tight Sleeves
ML20134E3221997-02-0303 February 1997
Proposed Tech Specs for Vol 16,Unit 1 Current Markup Improved Conversion License Amend Request
ML20134E3361997-02-0303 February 1997
Proposed Tech Specs Vol 17,Unit 2 Current Markup Improved Conversion License Amend Request
ML20134D3041997-01-31031 January 1997
Proposed Tech Specs Re Requirements to Allow Increased SG Tube Plugging
ML20210P3971996-12-0404 December 1996
Rev 2 to RP-2-101, Administrative Procedure Radwaste Mgt
ML20135A5231996-11-26026 November 1996
Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule
ML20134N1831996-11-20020 November 1996
Proposed Tech Specs 6.0 Re Administrative Controls
ML20210P3871996-10-17017 October 1996
Rev 2,Change 0 to Offsite Dose Calculation Manual
ML20128Q8041996-10-14014 October 1996
Cycle 13 Summary of Startup Testing
ML20128H6031996-10-0303 October 1996
Proposed Tech Specs,Changing Provisions for Receiving, Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant
ML20117L7991996-09-10010 September 1996
Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys
ML20117L3441996-09-0404 September 1996
Proposed Tech Specs Clarifying License Amend Request Re Implementation of Changes to Radiological Effluent TSs as Proposed by GL 89-01
ML20116F8281996-08-0101 August 1996
Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation
ML20116E3771996-07-26026 July 1996
Proposed Tech Specs Allowing Repair of Defective SG Tubes by Electrosleeving
ML20117F6431996-05-15015 May 1996
Proposed Tech Specs Section 6.0, Administrative Controls
ML20101K6011996-03-28028 March 1996
Proposed TS Figure 3.1.1-1 Re Change to Moderator Temp Coefficient
1999-09-01
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20207F0261999-06-0101 June 1999
Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2
ML20204H6011999-01-29029 January 1999
Age Related Degradation Insp (Ardi) Program Technical Requirements Document for Mechanical Systems
ML20198A2981998-09-15015 September 1998
Technical Procedure CP-217,rev 7,PCR 98-034, Specifications & Surveillance,Secondary Chemistry
ML20198A3131998-09-15015 September 1998
Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated
ML20198A2911998-02-23023 February 1998
Technical Procedure CP-206,rev 4,PCR 98-034, Specifications & Surveillance Component Cooling/Service Waster System
ML20211J2981997-09-18018 September 1997
Pump & Valve IST Program Third Ten-Yr Interval for Calvert Cliffs Nuclear Power Plant,Units 1 & 2
ML20141D9341997-05-0909 May 1997
Radiation Safety Procedure 1-104, Area Posting & Barricading & High Radiation Area Pre-Entry Checklist
ML20210P3971996-12-0404 December 1996
Rev 2 to RP-2-101, Administrative Procedure Radwaste Mgt
ML20210P3871996-10-17017 October 1996
Rev 2,Change 0 to Offsite Dose Calculation Manual
ML20095G7841995-10-12012 October 1995
Change 95-086 to Rev 4 to Technical Procedure CP-217, Specs & Surveillance:Secondary Chemistry
ML20095G7621995-09-27027 September 1995
Rev 2 to Administrative Procedure NO-1-106, Functional Evaluation/Operability Determination
ML20095G7771995-05-23023 May 1995
Rev 0 to Administrative Procedure RM-1-103, Commitment Mgt
ML20095G7661995-02-27027 February 1995
Rev 3 to Administrative Procedure QL-2-100, Issue Reporting & Assessment
ML20078A3611995-01-18018 January 1995
Change 5 to Rev 0,to Program Plan for Second Insp Interval for Plant,Units 1 & 2
ML20072T4141994-08-29029 August 1994
Rev 0,Change 1 to Emergency Response Plan Implementation Procedure,Erpip 203.Change Replaces Entire Procedure
ML20072T3741994-08-29029 August 1994
Rev 1,Change 3 to Emergency Response Plan Implementation Procedures,Erpip 201.Rev Replaces Pages 3 & 4 & Review/ Approval Page
ML20095G7781994-08-19019 August 1994
Rev 0 to Administrative Procedure MN-3-111, Erosion/ Corrosion Monitoring of Secondary Piping
ML20064F2221993-09-0101 September 1993
Rev B/Change 1 to Calvert Cliffs Instruction CCI-803, Radioactive Matls Mgt
ML20064F2011993-08-26026 August 1993
Rev 1,Change 0 to Odcm
ML20095G7551993-08-11011 August 1993
Rev 0 to Administrative Procedure NS-1-300, Industry Operating Experience Info Processing
ML17179A8601993-03-12012 March 1993
Rev 1/Change 0 to LCM-11S, Component Level Itlr Screening Procedure for Structures.
ML20044C5291993-03-0101 March 1993
Rev 4/Change 0 to LCM-11, Life Cycle Mgt Component Level Itlr Screening Procedure for Sys.
ML20056F5701993-02-18018 February 1993
Rev 0 to Change 1 to Odcm
ML20118A8241992-09-18018 September 1992
Technical Criteria & Procedures Used for Generation of In- Structure Response Spectra
ML20091N3031992-01-0606 January 1992
Rev 10 to Support Procedures - Media Response Procedure ERPIP-B.2, Off-Site Survey Points. Rev Deletes Photographs of off-site Points
ML20077R2701991-08-31031 August 1991
Rev 2 to Calvert Cliffs Nuclear Power Plant Fitness-for-Duty Manual
ML20058E5571990-10-29029 October 1990
Rev 5 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program
ML20059H2871990-09-0707 September 1990
Rev 4 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program
ML20044B0421990-07-13013 July 1990
Rev 3 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program.
ML20042E8291990-04-30030 April 1990
Rev 2 to Calvert Cliffs Performance Improvement Plan Implementation Program.
ML20042G3771990-04-16016 April 1990
Changes 1-3 to Rev 0 to Program Plan for Second Insp Interval for Calvert Cliffs Nuclear Plant,Units 1 & 2.
ML19332F3041989-12-0808 December 1989
Rev 3 to Surveillance Test Procedure STP-M-662-2, Integrated Leak Rate Test,Unit 2 Containment.
ML20246L7641989-08-14014 August 1989
Corrected Pages for Substitution Into Performance Improvement Plan (PIP) Implementation Program & Table 1.4 Which Sorts PIP Action Plans by Root Cause & Updated Schedule & Resource Summaries
ML20247M5741989-07-31031 July 1989
Performance Improvement Plan Implementation Program
ML20248H8121989-04-30030 April 1989
Performance Improvement Plan
ML20204G5821988-09-26026 September 1988
Rev 1 to ASME Section XI Pump & Valve Test Programs-Units 1 & 2 Second 10-Yr Interval
ML20029A7671988-07-27027 July 1988
Rev 1 to Chemistry Procedure CP 607, Offsite Dose Calculation Manual.
ML20154J0991988-02-10010 February 1988
Operating Manual;Emergency Operating Procedures
ML20148L6431987-11-30030 November 1987
Program Plan for Second Insp Interval for Calvert Cliffs Nuclear Power Plant,Units 1 & 2
ML20239A0561987-02-28028 February 1987
Operating Procedure OP-17-60-016-0, Ultrasonic Thickness Measurement Piping Using Swri Thickness Data Acquisition Sys
ML20205P4611986-12-31031 December 1986
Rev 0 to ASME Section XI Pump & Valve Test Programs - Units 1 & 2,Second 10-Yr Interval
ML20198H4271986-03-26026 March 1986
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 9 to Erpip 4.1.3, Technical Support Ctr Roster, Rev 9 to Erpip 4.1.4, OSC Roster & Rev 10 to Erpip 4.1.17, Security. W/860522 Release Memo
ML20198C5061985-11-0101 November 1985
Supplemental Program Plan for Dcrdr
ML20138A3931985-09-20020 September 1985
Rev 9 to Emergency Response Plan Implementation Procedure Erpip 5.0, Preparation & Control of Emergency Response Plan & Implementation Procedures
ML20236U2791985-08-0505 August 1985
Rev 3 to Operating Procedure X-FE-101-3, Onsite NDE Records Control
ML20090B5881984-05-0202 May 1984
Public Version of Revised Emergency Response Plan Implementation Procedures,Including Rev 10 to Erpip 4.1.17, Rev 9 to Erpip 5.4 & Rev 2 to Erpip A.2
ML20090B6891984-04-18018 April 1984
Public Version of Rev 15 to Emergency Response Plan Implementing Procedure Erpip A.1, Emergency Organization Telephone Numbers
ML20087F2591984-03-14014 March 1984
Instruction CCI-310, Emergency Operating Procedure Writers Guide. Emergency Operating Plan Validation/Verification Plan & Training Plan Encl
ML20155H2161984-02-20020 February 1984
Remote I/O Equipment Hardware Acceptance Test Procedure for NUS Corp/Bg&E Calvert Cliffs Data Acquisition Sys
ML20106H1901984-02-0202 February 1984
Remote I/O Hardware Acceptance Test Procedure for NUS Corp/Bg&E Calvert Cliffs Data Acquisition Sys at Computer Products,Inc
1999-06-01
[Table view] |
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Change 1 APPENDIX C SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURES Procedure No./Rev. Title IX-FE-101-4 Deviations to Nuclear Projects _ Operating Procedures t
IX-FE-103-2 Weld Joint Identification Marking on Nuclear Power Plant Piping IX-FE-116-1 Recording Data from Direct Visual, Liquid Penetrant, and Magnetic Particle Examinations IX-FE-117-4 Recording Indications During Ultrasonic Examination of Pressure-Retaining Components IX-FE-119-0 Measuring and Recording Search Unit Data During Ultra-sonic Examinations of Pressure Vessel Welds IX-FE-125-0 Recording Indications in Accordance with NRC Regulatory Guide 1.150 IX-FE-131-0 Comparison of Inservice Examination Data IX-F E-132-0 Ultrasonic Indication Resolution Procedure X-FE-101-3 Onsite NDE Records Control I XII-ME-105-0 Operation of the Model ISI-2 Inservice Inspection Posi-tioning System and Attachments (par Device)
XII-ME-106-0 Procedure for Disassembly of the Model ISI-2 Inservice Inspection Positioning System (par Device)
XII-ME-107-0 Procedure for Assembly of the Model ISI-2 Inservice Inspection Positioning System (par Device)
XII-ME-108-0 Calibration of Model ISI-2 Inservice Inspection Posi-Change 1 tion System and Attachments (par Device)
XIII-AG-101-2 Control of Nuclear Inspection Equipment and Materf.als XVII-AG-101-1 Data Storage and Retrieval Change 2 O
8712O20404 871123: C-1 PDR ADOCK 05000310 G PDR
SOUTHWEST RESEARCH INSTITUTE .b FE-101-3 2
NUCLEAR PROJECTS August 1985
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M OPERATING PROCEDURE Page 1 of 6 Titie ONSITE NDE RECORDS CONTROL AFFECTIVITY AND APPROVAL Revision 3 of this procedure became effective on 8/5/85 This procedure censists of the pages and changes listed below.
Page No Change Date Effective 1-6 August 5, 1985 O
Superseces Procecure N o.
gg X-FE-101-2 Aporovals FO Written By Date Technical Review Date 3
& A- ' ? U g @p ) W Ave 1993_
Manager of C.A. Data Cognizant Director Date w>A '"% azAWK %lc 5 al Form GAdo81 '
/ #
SOUTHWEST RESEARCH INSTITUTE
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August 1985 g
ha \ NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 6 3v ONSITE NDE RECORDS CONTROL
- 1. PLTPOSE This procedure describes the onsite control processes for nondestructive !
examination records (data) generated in the field during preservice (PSI) j and inservice (ISI) examinations. )
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- 2. SCOPE AND APPLICATION 2.1 This procedure describes the flow of data records used to document ;
the results of nondestructive examinations performed. Data records ;
include original data sheets, summary sheets, resolution sheets, strip charts, magnetic tapes, video tapes, and other information as defined by the Inspection Engineer or Team Supervisor.
1' 2.2 This procedure provides guidance to personnel of the NDE Field Services Section who are assigned the responsibility of preparing, !
reviewing, or otherwise using data records while in the f.ield per- '
forming a preservice or inservice examination. ,
2.3 Functional steps are provided in this procedure to explain the flow of the records. ,
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- 3. RESPONSIBILITY 1
(1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan.
(3) The Inspection Engineer shall be responsible for i=plementing the l requirements of and ensuring compliance with this procedure.
1 (4) The Manager of the Support and Administration Section, Quality l Assurance Systems and Engineering Division, shall be responsible f or storage of records generated in accordance with this procedure.
O
$*RI Form CA 3-2
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SOUTHWEST RESEARCH INSTITUTE August 1985 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 6 ')
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- 4. PROCEDURE 4.1 Original Data Sheets jl (1) Original data sheets, are to be serialized either at SwRI or at the site.
(2) Original data sheets shall be filled out at the examination location and during the examination time.
(3) The filled-out original data sheets shall be returned to the team staging area (office, trailer, etc.) on a periodic basis {
(at meal time, at the end of the day, upon leaving controlled areas) during an ISI or a PSI, and an entry shall be made into a daily log indicating that the examinations have been performed.
(4) The original data sheets shall then be placed into the To-Be- ,
Reviewed File.
(5) The review process is performed as follows:
(a) The original data sheets shall be checked for complete-ness, accuracy, and consistency of the data. j (b) If clarification or correction of any entry on the orig- )
inal data sheets is required, the original data sheets j shall be returned to the examiner.
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(c) After clarifications or corrections, if any, have been i made and initialed by the examiner, the reviewer shall sign each original data sheet which does not contain indications requiring evaluation / resolution.. ,
i (6) The original data sheets which have been reviewed and signed !
shall be moved to the To-Be-Summarized File. See Paragraph ,
J 4.1(9). j (7) Original data sheets which contain indications requiring evalu- ;
ation/ resolution shall he placed in the To-Be-Resolved File. <
l (a) Original data sheets in the To-Be-Resolved File which i document visual or surface examinations shall be handled i as follows:
O SwRI Form QA 12
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"'" ~3 SOUTHWEST RESEARCH INSTITUTE August 1985 g1 g g NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 6 f i I g[
i s
(1) The Original data sheers shall be reviewed, signed by the reviewer, and used to generate a Customer i Notification Form (CNF). (The CNF shall be com- l plated according to NQAP 13-1.)
l (2) Copies of original data sheets shall be made and l attached to the CNF. I 1
(3) A log shall be maintained of CNFs issued and their l status. {
J (4) The original data sheets are then placed in the l To-Be-Summarized File. See Paragraph 4.1(9). 1 (b) Original data sheets in the To-Be-Resolved File which document ultrasonic examinations shall be used to resolve the indications according to Paragraph 4.3 and shall then be processed as specified in Paragraphs 4.l(5) and 4.1(6).
(8) When a computer, is used to record results and generata sumary l sheets, data shall be fed into the computer. The computer will l generate the sumary sheets at the completion of all required !
examinations of an examination area.
(9) If the computer is not used to generate summary sheets, ' data placed in the To-Be-Sumarized File shall be sumarized accord-ing to Paragraph 4.2 and filed with the summary sheet in the i criginal data volumes. l 4.2 Summary Sheets l
(1) Sumary sheets, are to be serialized either at SwRI or at the site.
(2) Sumary sheets shall be completed for each examination area.
l In certain cases (studs, nuts, etc.), one sumary sheet may be used for more than one examination area.
(3) Sumary sheets shall be completed prior to the conclusion of site activities for each examination area for which examination requirements have been completed.
(4) Sumary sheets shall be file , with the data in the original data volumes.
O SwRI Form QA 3 2
l-X-FE-101-3 SOUTHWEST.RESEARC'HilNSTITUTE Ag ;. .
August 1985 IYq- .
NUCLEAR PROJECTS OPERATING PROCEDURE
.Page 5 of 6-l 4.3 Resolution Sheets (1) Resolution sheets, are to be serialized' eithe'r at. SwRI or at the site.
(2)- The ' Level II. or Level III examiner shall take the steps. neces-aary to resolve the ultrasonic indications and complete a resolution sheet describing the' results of his analysis. . Any-additional documentation required to support the resolution shall be attached. -
(3) Original data sheets and resolution records with . indications requiring no further action shall be-placed in the To-Be-Reviewed File and processed as specified in Paragraphs 4.1(5) .
and 4.l(6).
(4) Data with indications requiring further action shall*be handled in.a manner established by the Director of' the Department of
' Engineering Services.
O (5) Indications which have been deemed reportable and: require cus-tomer disposition shall be reported on a CNF form. The CNF shall be completed in accordance with SwRI NQAP 13-1.
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4.4 Strip Charts, Magnetic Tapes, Video Tapes
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(1) Strip charts, magnetic tapes,'and video tapes being generated !
during mechanized ultrasonic examinations shall be identified with a sequence number and with the examination areas for which 1 they contain data.
(2) During the resolution of any indications, the strip charts and tapes may be used by the Level II or Level III examiner, as needed.
(3) The strip charts and tapes are then prepared for transmittal to SwRI.
4.5 Customer' Data Review I The customer, at his option, may. elect to review and approve the original NDE data prior to its shipment to SwRI.
SwRI Form CA 34
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SOUTHWEST RESEARCH INSTITUTE
!w ust 1985 g
w=x s
/R'gj NUCLEAR PROJECTS OPER ATING PROCEDURE . Page 6 of 6 l.h s ~'-
- 5. R" CORDS 5.1 Price to departing the site at the completion of a preservice or inservice examination, the original data package with the exception of strip charts, magnetic tapes, and videotapes shall be reproduced and a copy (ies) shall be transmitted to the appropriate site person-nel. At no time vill data be reproduced for this transmittal before the required examinations for a particular area are complete, the data have been reviewed, and the summary sheets have been completed.
5,2 After complettion of site activities (or at other timea deemed appro-priate by the Inspection Engineer or Team Supervisor), the original data package shall be transmitted to swr 1 in accordance with the latest revision of SwRI Nuclear Frojects Operating Procedure XVII-AC-101.
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