|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program ML20138F2531996-02-23023 February 1996 Rev 38 to Sequoyah Nuclear Plant Odcm ML20108B4121995-11-0303 November 1995 Rev 37 to Sequoyah Nuclear Plant Odcm ML20094Q2301995-10-30030 October 1995 ASME ISI Valve Testing Program Basis Document, Rev 0 ML20094Q1931995-10-30030 October 1995 Rev 1 to ASME Sys Pressure Testing Program Basis Document ML20094Q1971995-10-30030 October 1995 Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2 ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump Testing Program Basis Document ML20094Q1761995-10-13013 October 1995 ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2 ML20094Q1841995-10-13013 October 1995 ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2 ML20149L6811994-09-30030 September 1994 Concerns Resolution Program - Sequoyah Nuclear Plant ML20063D6691994-01-24024 January 1994 Rev 4 to Sequoyah Nuclear Plant Restart Plan ML20065Q6251993-10-13013 October 1993 Rev 31 to Sequoyah Nuclear Plant Odcm ML20056F3181993-08-20020 August 1993 Rev 0 of Post-Restart Plan ML20056G1841993-08-10010 August 1993 Rev 2 to Sequoyah Nuclear Plant Restart Plan ML20044F3081993-05-20020 May 1993 Rev 0 to Sequoyah Nuclear Plant Restart Plan. ML18036B1961993-01-27027 January 1993 Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training. ML20127P5461992-12-16016 December 1992 Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1 ML20127P6361992-12-16016 December 1992 Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2 ML20114C8131992-04-17017 April 1992 Rev 27 to Odcm ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 ML19332D2241989-09-22022 September 1989 Rev 23 to Odcm. ML20245H1421989-08-15015 August 1989 Rev 22 to Offsite Dose Calculation Manual Changes ML20246H4861989-05-16016 May 1989 Rev 1 to Technical Instruction TI-115, Instructions for Sewage Mgt ML20244E2521989-04-28028 April 1989 Rev 14 to Surveillance Instruction SI-114.2, ASME Section XI Inservice Insp Program ML20246E7771989-04-25025 April 1989 Rev 14 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program ML20206D3421988-10-15015 October 1988 Rev 13 to Surveillance Instruction SI-114.2, Inservice Insp Program ML20154J3221988-09-0909 September 1988 Procedure EA-OR-003-S, Sequoyah Nuclear Plant - Unit 1 Design Baseline & Verification Program,Supplemental Engineering Assurance Oversight Review Rept ML20150F9291988-06-17017 June 1988 Diesel Generator Voltage Response Improvement Plan ML20154L1421988-05-0909 May 1988 Rev 3 to Revised Sequoyah Nuclear Performance Plan ML20153H3891988-03-30030 March 1988 Rev 19 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20196G3301988-02-24024 February 1988 Limited Test Program for Determining Axial Load Capacity of Cast One-Hole Conduit Clamps ML20147E9511988-01-21021 January 1988 Revised, Procedures Generation Package ML20153H3851988-01-0505 January 1988 Rev 18 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20147E5691987-12-17017 December 1987 Rev 4 to Special Maint Instruction SMI-0-317-61, Instrumentation Features Walkdown,Rework & Insp Instructions for CAR 87-014 ML20237C5451987-10-28028 October 1987 Rev 17 to Offsite Dose Calculation Manual ML20236E6931987-10-17017 October 1987 Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program ML20235X0551987-10-10010 October 1987 Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2 ML20235X0651987-10-10010 October 1987 Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2 ML20237H2051987-08-28028 August 1987 Rev 0 to Civil Engineering Branch Instruction CEB-CI 21.89, Mod Priorities for Pipe Supports on Rigorously Analyzed Category I Piping - Sequoyah Unit 2 ML20207G5821987-08-24024 August 1987 Rev 14, Balance of Plant Temp Monitoring Sys ML20237L3651987-08-21021 August 1987 Unit 2,Regeneration of Support Design Calculations on Rigorously Analyzed Piping,Program Plan ML20236Q1771987-08-0707 August 1987 Rev 9 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program. Rev Corrects Deficiencies Shown in Caqr CH5870006 & CH5870010,adds Punchlist & Incorporates Icf 87-708 ML20236N7601987-08-0606 August 1987 Revised Radiological Emergency Plan Implementing Procedures, Including Rev 13 to IP-8, Personnel Accountability & Evaluation & Rev 6 to IP-15, Emergency Exposure Guidelines ML20236M7181987-07-28028 July 1987 Rev 1 to WP-17-SQN, Vendor Weld Quality, Welding Project, TVA Employee Concerns Special Program ML20236M7351987-07-24024 July 1987 Rev 5 to 80503-SQN, Document Distribution Control, Element Rept,Tva Employee Concerns Special Program 1999-06-22
[Table view] |
Text
l
', ' a _- N, r
~
F .
q ,,
DING PRCLECT PRcIcT PRnrmsE N O. W-03 i .:. ,s. c. r
===m TITLE: EVALUATION ?. ANALYSIS OF E:@LOYEE CONCERNS ag, i
9 REVISION RO R1 R2 R3 R4 R5 DATE 2/3/86 -
PREPARED (
JQ JQ Jg APPROVED g Q g APPROVED yhg y g U-8609050150 860903 PDR ADOCK 05000327
. ,l
~'; -
6 OFFICE OF ENGINEERING' .
WELDING PROJECT C PROJECT MANUAL _ .
REVISION 2 PROJECT PROCEDURES WP-03 EVALUATION & ANALYSIS OF EMPLOYEE CONCERNS
- 1. - PURPOSE This procedure establishes the method for evaluating, condensing, and determining the relevancy of welding-related Employee Concerns.
This procedure also describes the evaluation methods for addressing
- Employee Concerns. , , _
- 2. SCOPE ,
All Employee Concerns furnished to the Welding Project (WP) are included in the scope of this document. Activities addressed: -- ,
2.1 Review and grouping to determine specific problems and issues in an effort i C to condense these concerns.
i 2.2 Development of trends for the overall TVA welding pro' gram. '
2.3 Engineering evaluation of each concett to determine relevancy to program,
! procedures, or hardware.
4 2.4 Those Employee Concerns determined to be applicable to Sequoyah Nuclear Plant (SQN) shall have Evaluttion Reports initiated as described in this procedure. -
- 3. DISCUSSION The Evaluation Report results represent engineering evaluations of potential generic problem issues. The evaluation of these issues are to be accomplished by review and analysis of:
- 1. Programs, procedures, and polices.
2
- 2. The review of applicable Unplementation audit elenents.
- 3. The review of applicable independent reinspection results.
- 4. kEFERENCES ,
Employee Concerns Task Group (ECTG) Program Manual
(
- 5. DEFINITIONS i
None a
> e OFFICE OF ENGINEERING WELDING PROJECT C PROJECT MANUAL _.
REVISION 2
- 6. RESPONSIBILITIES OC Project Engineer is responsible for all activities within the scope of this procedure.
- 7. PROCEDURE 7.1 Review and categorize each Employee Concern "K-Form" into specific problen and disposition categories assuming each concern is a statement of f act.
7.2 Assimilate these categorizations into the WP data base for overall ;
analysis and evaluation of the welding program.
7.3 Evaluate each Employee Concern to determine if it is relevant to program, _ _
procedures, or hardware. _.
7.3.1 Employee Concerns which are not found relevant to program, procedures, or hardware will not require further reviews or action by WP.- A statement of justification will be prepared for each Employee Concern determined to be in this category. ,
7.3.2 Employee Concerns found to be relevant to program, procedures, or hardware vill be assimilated and filed as follevs for further action by WP: .
7.3.2.1 Program 7.3.2.1.1 Welding 7.3.2.1.2 Overall QA 7.3.2.2 Procedures 7.3.2.2.1 Electrode Control 7.3.2.2.2 Inspection 7.3.2.2.3 Welder Training 7.3.2.2.4 Inspector Training 7.3.2.2.5 Process Control 7.3.2.2.6 Reinspection Criterion 7.3.2.2.7 Others as Necessary WP3.0 Page 2 of 4
a: .
0FYICE OF ENGINEERING WELDING PROJECT .
PROJECT MANUAL REVISION 2 i
i 7.3.2.3 Hardware systems, and components which are identified.
7.3.2.3.1 Specific equipment, -
and components which are not specifically 7.3.2.3.2 Equipment, systems, identified.
7.3.3 Employee Concerns will also be grouped by specific problem areas to condense them into specific families of problems. o4 h an ? 1 Evaluation Reports for Employees Concerns which apply to SQN shall be i' 7.4 prepared as follows:
7.4.1 Each Employee Concern (EC) or group of ECs will be evaluated by WP is l~~ .
personnel individually assuming each statement made by the concern valid observation.
7.4.2 These statements will be assimilated or grouped, if possible l . into specific issues and analyzed both individually and collective y.co .
develop issues.
Each issue will be analyzed against the requirements of the applicableT C 7.4.3 QA program which could affect the issue.
in relation to policies, reinspections, audits, NSRS/QTC impact of the issue on the quality of the plant.
to the issue will be used to 7.4.4 The results of the information revelant develop a report which is to include the following: ,
Statement of scope at evaluation report (list all Emhloyee Concerns 7.4.4.1 applicable).
Statement of issue (s) addressed by the concern (s).
7.4.4.2 7.4.4.3 Statement of substantiation or nonsubstantiation.
7.4.4.4 Statement of compliance to program.
7.4.4.5 Statement of suitability for service.
7.4.4.6 Indication of need for reinspection.
7.4.4.7 Justification for substantiation or nonsubstantiation.
7.4.4.8 Justification for suitability for service evaluation.
- - 7.4.4.9 Recommendation for closure or corrective action.
Page 3 of 4 WP3.0
. ,. , . N' OFFICE OF ENGINEERING -
WELDING PROJECT C PROJECT MANUAL REVISION 2 7.4.4.10 closure statement.
7.5 The report will be initiated and checked by WP personnel and will receive a QA review by the WP DQA representative.
7.6 Completed reports will be forwarded from the Welding Project Manager to the Welding Task Group Manager for review and processing in accordance with the Employee Concerns Task Group Program Manual.
- 8. DOCUMENTATION Employee Concerns Evaluation Reports shall be maintained in acecrdance with the Employee Concerns Task Group Program Manual
- 9. ATTACHMENTS Attachment A - Cover Sheet for fer' Employee Concern Report ._
4 f
s-L.
L WP3.0 Page 4 of 4
7-s l ,. ~
3;-
~
) 0FFICE OF ENGINEERING '
WELDING PROJECT PROJECT MANUAL REVISION 2 Attachment A l EMPLOYEE CONCERN REPORT Page 1 of 1 I. Concern Number (s) considered _
II. Issue involved
~
III. Substantiated or nonsubstantiated . . . .
IV.
Eff ect on hardware / program Y. Justify iY above _
VI. Reconsmendations/ corrective action _ .
Y__ N__
Reinspection neededt VII.
VIII. Closure Report Analysis L
WP3.0
s.
Attachment 2' Page 1 of 3 SEQUOYAH (GENERIC)
WEI.D PROJECT EMPLOYEE ECTG REPORT NUMBER CONCERN NUMBER ISSUE ACTION WP-04-SQN IN-85-406-003 Availability of Wald Not substantiated. No
. IN-85-134-002 Inspection Tools action required.
IM-85-007-001 ,
CLOSED *
- WP-05-SQN IN-85-339-005 Ouct Installation and Substantiated as it re-PH-85-012-XO3 Documentation lates to the duct being too close to walls to
( ,
weld and as to welding l and attendant inspection from the in-side of the duct (IN-85-339-005).
, not having a program
( P H -8 5-012-X O 3 ) . No .
hardward deficiencies exist.' CLOSE0 -
WP-06-SQN IN-85-476-004 Training and Certification Not substantiated by WP.
IN-85-981-001 of Construction Wolding These concerns closed WI-85-081-007 Inspectors based on the existing WI-85-041-002 program and Bechtel SQN Implementation Audi,ts, Key Elements 6.0, 7.0, 8.0, 11.0, and 17.0.
CLOSE0 WP-07-SQN IN-85-706-001 Walder Training Program For Not substantiated. -
XX-85-045-001 Construction and Nuclear These concerns closed .
Operations based on the Welder Qualification Program, Welder Training Program, and Bochtel SQN Implementation Audit, Ney Elements 3.0, 4.0,
, and 5.0. CLOSED
e Att:chment 2 Page 2 of 3 SEQUOYAH (GENERIC)
WELD PROJECT EMPLOYEE ECTG REPORT NUMBER CONCERN NUMBER ISSUE ACTION 4
WP-09-SQN IM-8k-406-002 Weld Inspection Criteria Used Not substantiated.
, For SQN Construction Closed based on the
~
, .Bechtel SQN Implementation Audit.
. Key Element 10.0. CLOSED WP-10-SQN WI-8G-030-010 SQN Implementation of Weld Substantiated. This Program Study QAE-80-2 study was not applicable to SQN. CLOSED WP-11-SQN IN-85-282-002 Surface Grinding of Wolds Not substantiated.
IN-85-271-001 Grinding is an
, acceptable practice.
CLOSED WP-13-SQN IN-85-247-002 Suitability of Welding Equip- Not substantiated.
IN-85-303-001 ment For Construction and Review indicates equip-4 Modification Welding ment is suitable. The Activities Reinspection did not identify problems due to welding equipment.
,, CLOSED
. ~ _ _
WP-16-SQN .SQM-5-001-001 Performance of Preweld Substantiated non-
,$QM-5-001-002 . Inspections compliance by Nuclear W8M-5-001-001 ', . Operations.with ANSI
~~
BEM-5-001-001 Note'that concern N45.2.5 Surveillance BEM-5-001-002 SQM-5-001-002 is a SQN* Program for Structural 0FM-5-001-002 specific concern. Wolding. Interim cor-WI-85-080-007 rective actions have IN-85-212-001 been formulated. To be closed upon
. completion of correction actions. CLOSED upon
- completion of corrective actions.
o Attachment 2*
Page 3 of 3 SEQUOYAH (GENERIC)
, WELD PROJECT EMPLOYEE ECTG REPORT NUMBER CONCERN NUMBER ISSUE ACTION l
WP-17-SQN IN-85-127-001 . Vendor Weld Quality The issue vendor welds IN-85-007-003 not the same quality
- IN-85-657-001 as TVA field we'ds was substantiated by NSRS I-85-753-W8N. The issue that vendor welds are not inspected in field i was not substantiated.
Report close concerns.
No corrective action identified. CLOSED 6
y 1
]
h l
4
\
j i
i l
I f
4 i