ML20078Q799
| ML20078Q799 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 02/27/1993 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML18065B259 | List: |
| References | |
| NUDOCS 9502220075 | |
| Download: ML20078Q799 (130) | |
Text
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HOUSTON LIGHTING AND POWER COMPANY SOUTH TEXA8 PROJECT 8
ELECTRIC GENERATING ETATION FLANT PROCEDURES MANUAL DEPARTMENT PROCEDURE SAFETY-RELATED (Q)
Neintenance Work Practices MPHP01-EA-0040 and Requirements Rev. 2 Page 1 of 46 APPROVED:
D 1h b
DEPARTMENT MANAGER-DATE APPROVED DATE EFFECTIVE PROCEDURE USE CONTROL: AVAILABLE Table of Contents
- Page,
1.0 Purpose and Scope
4 2.0 Definitions 4
3.0 Responsibilities 6
l 4.0 Work Practices and Controls 8
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4.1 Procedural Adherence and Verification 8
4.2 Work Coordination 9
4.3 Maintensnee Shift Conduct and Communications 9
4.4 Equipment Clearance and Caution Tagging Programs 10 4.5 Deficiency Control Programs 10 4.6 Configuration Control Programs 10 4.7 Material Control Program 11 4.8 Expendable Materials 12 4.9 Procurement of Haterials 12 4.10 Hazardous Heterials 12.
RECEIVEQ
.11 onsite Certification of items 12 QS l 619$J 4.12 Control of Stainless Steel.
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Maintenance Work Practices OPMP01-EA-0040 and Requirements Rev. 2 Page 2 of 46 Table of Contents Page 4.13 Quality Arsurance and Quality Control Programa 13 4.14 Housekeeping and System Cleanness Program 13 4.15 Radiation Protection Programs 14 l
4.16 Control of Special Processes 14 4.17 Tool and Measuring 6. Test Equipment Program 15 4.18 Pastener Torquing and Dateneloning 15 I
4.19 ASME Section XI Program 16 4.20 Industrial Safety Programs 16 4.21' Fire Protection Pcograms 13 4.22 Securi'ty Programa 20 4.23 Supporting Programs 21 4.24' Equipment Qualification Program 22 4.25 conduct of Testing 22 5.0 Conduct of Maintenance 23 5.1 Training / Qualification 23 5.2 Control of Maintenance Activities 24 5.3 Plant Material Condition 28 5.4 Maintenance Procedures 29 5.5 Safety 31 5.6 Maintenance Facilities and Equipment 33 5.7 Work Schedules 34 5.8 Management Inspections 35 5.9 Management Involvement 35 5.10 Repeat Maintenance 36
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Maintenance Work Fractices 0FNF01-EA-0040 and Requirements Rev. 2 Fage 3 of 46 Table of Contents Fm 6.0 Electrical Work Fractices 36 6.1 Wire and Cable Terminations 36 6.2 Raychem Insulation Application 37 6.3 Design Configuration Control of Electrical Circuit 37 Breakers 6.4 Adjustments to Motor Oil Level, 500 HP and Above 38 7.0 Hechanical Work Fractices 34 7.1 Alternative Valve Packing and Live-Load Facking 38 8.0 References 39 9.0 Support Document 45 9.1 Addenduss 1 1 Repeat Maintenance Identification Sheet 46 i
Maintenance Work Fractices 0FHF01-EA-0040 sad Requirements Rev. 2 Fage 4 of 46
1.0 Purpose and Scope
1.1 Purpose 1.1.1 The purpose of this procedure is to provide guidelines fors 1.1.1.1 Conduct of Corrective and Freventive.
Maintenance activities in~accordance with applicable site procedures and policies.
1.1.1.2 Conduct of post' implementation testing activities for verification of function and operability.
1.1.1. 3 '
Forforming Ninor Naintenance work activities.
1.2 Scope 1.2.1 This procedure shall apply to all work activities (without regard'to implementing organization) on plant systems, structures and components, non-plant facilities, and requests for general manpower support ' services.
1.2.2 This procedure does not apply to periodic or conditional testing activities performed in accordance with
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0FGF03-ZE-0004 (Plant Surveillance Program).-
2.0 Definitions :
Terms and acronyms used in-this procedure are the same as those defined in OPGF03-EA-0090 (Work Frocess Program)'and.
will not be repeated in this procedure. Additional' definitions are as follows:
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2.1 CONTRACTOR
Any organization under contract for furnishing equipment, material, or services.
It includes the terms vendor, supplier, subcontractor, fabricator, and subtier levels of these, where appropriate.
Prime contractor is used to indicate either the architect engineer, NSSS supplier, constructor, or nuclear fuel supplier.
2.2 INDEFENDENT YERITICATION: The a:t of checking a condition, such.
as a component position, completely separate from activities related to establishing the condition of component's position.
Independent Verification shall apply to valves, breakers, switches, jumpers, lifted wires, blind flanges, plugs, electrical equipment links, control cards, field instruments and transmitters, or any other component that could if improperly installed or mispositioned, degrade a safety function.
4 Maintenance Work Fractices 0FMF01-EA-0040 and Reautrements Rev. 2 -
Fase 5 of 46 l
2.2.1 The Independent Yorification shall be performed by one or-more individual (s) not involved in and separate from the establishment of the condition or component position.
2.3 KEY MAINTINANCE FIRSONNEL:.Forsonnel in key staff positions who perform safety-related functions, and who must have the Plant Manager's approval of overtime in excess of regulatory guidelines.
(Reference OFGF02-EA-0060 Overtime Approval Program.) This policy applice to both ML&F employses and contract employees in these positions. The following are considered key maintenance personnel
- 1) Electricians and their crevleader
- 2) Hochanics and their crevleader i
3)
IEC Technicians and their crawleader
- 4) Other Craftsmen and their crawleader
2.4 VERIFICATION
The act of checking a condition or activity by an individual other than the person parlorming the activity.
The individual performing. the verification may do so in the company of the person performing the activity.
2.4.1 When installing / removing electrical / mechanical jumpers, verification shall consist of positively identifying connection point prior to the installation / removal of the jumper as well as the proper placement and removal of the j umper (SFR-880088).
I 2.4.2 When removing / installing fuses, verification shall consist of positively identifying the fuse.and its required location prior to the removal / installation of i
the fuse as well'as the removel/ installation of the fuse (SPR-880088).
2.4.3 When installing / removing test equipment, verification shall consist of positively identifying the test point prior to the fastallation/ removal of the test lead / device as vall as the proper placement of the test lead / device (SPR-880088).
2.4.4 When manipulating switches, verification shall consist of positively identifying the switch prior to its manipulation as well as the proper positioning of the switch (SPR-880088).
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l Maintenance Work Fractices OPNF01-EA-0040 and Requirements Rev. 1-Fage 6 of 46 3.0 Responsibilities 3.1 The Maintenance Department Manager is responsible'for implementing this procedure.
3.2 The Responsible Maintenance Authority (RNA) is responsible for:
1 3.2.1 Reviewing and approving Vork Fackages..Freventive Maintenance Fackages and Test Packages prior to issuance and adding Maintenance Yorification Points (NYFa) to packages, se required and assigning Minor Maintenance i
Vork activities.
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3.3 The Work Supervisors are responsible fori 3.3.1 Reviewing Work Fackages, Freventive Maintenance Packages, Test Packages and verifying prerequisite actions have -
been performed prior to work start including the i
followings j
3.3.1.1 Fre-staging of parts, tools and equipment.
3.3.1.2 Ensuring assigned craftenen are certified to perform the work activity, or have adequate Work Direction.
i 3.3.1.3 Ensure all documentation (prints, procedures, forms and documents) are the current revision, i
3.3.1.4 Forforming a pre-jpb briefing with the assigned craftsmen.
3.3.2 Returning Work Fackages-and Preventive Maintenance Packages to the Owner /PIsaner whenever any revisions 2re required.
Specific actions / suggestions necessary to aid the Owner /Flanner-in package revision development should be provided by the Work Supervisor /Craf t to expedite turn around tim 4.
3.3.3 Signing Maintenance Verification Points (NYF) after personally performing the required inspection or after personally contacting another group required by the NYF and ensuring the required inspection has been completed.
3.3.4 Obtaining approval from the Responsible Maintenance Authority to separate Test Package (s) from a Work Fackage to schedule required Fost-Maintenance Tests or Fost-Modification Tests as plant conditions warrant.
l Maintenance k'ork'Fractices 0FMF01-EA-0040 and Requirements Rev. 2 Page 7 of 46 3.3.5 Insuring work areas are maintained and left in an improved condition following completion of all work activities.
3.3.6 Identifying Repeat Maintenance resulting from the reperformance of an entire nalatennoce activity or steps in a Maintenance Work Fackage before returning the component to service. These occurrences should be documented on a Repeat Maintenance Identification Sheet (Addendum 1) and forwarded to Maintenance Planning.
3.3.7 Reviewing completed Work Packages Preventive Maintenance i
Packages and Test Packages for completeness, accuracy and legibility, and ensuring all actione required subsequent to completion of the work activity are performed.
3.4 The Craftenen are responsible fore 3.4.1 Forforming and documenting work activities in accordance with approved Work Fackages, Preventive Maintenance Packages and Test Packages.
3.4.2 Insuring work areas are maintained and left in an improved condition following completion of all work activities.
3.4.3 Identifying Repeat Maintenance resulting from the reperformance of an entire maintenance activity or steps in a Maintenance Work Fackage before returning the component to service to the Work Supervisor.
3.5 The General Maintenance Supervisor JGHS) is responsible fore 3.5.1 Performing the duties of the Responsible Maintenance Authority or the Owner when they are not available.
3.5.2 Performing the duties of the PM Planner / Scheduler, as required to issue off-shift FMe.
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j Maintenance Work Practices 0PHF01-EA-0040-and Requirements Rev. 2 Fage 8 of 46 4.0 Work Practices and-Controls NOTE The Work Fractices and Controla Section provides the information necessary to comply with the procedures which impact the performance of all work activities covered by Sections 4.0 through 7.0 of this procedure.
Specific references are made to the appropriate procedures which further detail the acceptable work practices and controle necessary to perform work activities safely and in accordance with commitments made to regulatory agencies and internally as a result of operating experience. Work Supervisors and Craf tsmen shall consult the referenced procedures whenever necessary to ensure adherence with all work practices and controle.
4.1 Frocedural Adherence and Verification NOTE All Heintenance Personnel, who are performers in en evolution requiring the use of a procedure, shall have in their possession a working copy of the procedure except where specified by OPCP03-ZA-0010 (Plant Procedure Adherence and Implementation and Independent Verification).
(SPR 920098).
4.1.1 The requirements for complying with written procedures are detailed.in OPGP03-EA-0010 (Flant Procedure Adherence and Implementation and Independent Yorification). This procedure includes instructions fors i
4.1.1.1 Verifying correct revisions of procedures prior to use.
4.1.1.2 Control of working copies.
4.1.1.3 Forformance of procedural steps in sequence.
4.1.1.4 Independent Yerification requirements and me t hod e ~.
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i Maintenance Work Fractices 0FNF01-EA-0040 and Reautrements Rev. 2 i
Page 9 of 46 1
4.2 Work Coordination 4.2.1 The requirements for coordinating work activities between all departments are detailed in 0FGF03-EA-0080 (Work Coordination Program).
4.3 Maintenance Shift Conduct and Communications i
4.3.1 Proper verbal and written communication techniques are necessary for effective. and efficient interf ace between organizations, groups, and personnel during pe.rformance of maintenance activities.
4.3.1.1 The use of two-way FM radios may create interference or generate errant signals in electronic control systems.
Personnel should heed posted areas where radios are prohibited.
1 4.3.1.2 Ensure that actions of a temporary or permanent nature that may affect the integrity of the physical barriers used to control access to Protected or Vital Area, Material Accese Area or other portions of the overall security program, are coordinated with the-Security Department prior to being implemented (IEN 85-079).
4.3.2 shif t Turnover, when applicable, shall be conducted in a
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manner to ensure all pertinent information to reviewed and understood by the on-coming shift (IEN 06-007).
4.3.3 A shif t turnover log shall be kept by each Maintenance Discipline. The log should be a narrative summary of l
significant shift maintenance activities, problema encountered, precautions, pertinent itema of interest i
that may assist others, status of equipment," etc..
The shift Work Supervisor (s) are responsible for maintaining the log current.
l 4.3.4 Supervisory personnel shall frequently observe maintenance activities under their direct responsibility to ensure plant maintenance is being condutted in a safe and efficient manner, consistent with good maintenance practices and in compliance with the operating license and approved procedures 4 l
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4 Maintenance Work Fracticos OFMF01-EA-0040 and Recutrements Rev. 2 Fase 10 of 46 4.4 Equipment Clearance and Caution Tagging Frograms 4.4.1 The requirements for removing equipment from service and placing the equipment in a condition that is safe to perform maintenance. activities are detailed in Section 9.0 of 0FGF03-EO-0039 (Operati~ons Co' figuration a
Management).
4.4.2 The requirements for p1geing restrictions or precautions on the operation of components are detailed in Section 4.0 of 0FGF03-ZO-0039 (Operations Cohtiguration Management), and include instructions for personnel to comply with all restrictions or precautions specified on the applied Caution Tags.
4.5 Deficiency control Programs 4.5.1 The requirements for identifying squipment. failures or deficiencies, including those which are a result of a i
nonconformance, are detailed in 0FGF03-EA-0090 (Vork Process Program).
4.5.2 The requirements for identifying significant equipment failures and programmatic concerns which significantly impact performance of a work activity or Operability of equipment important to safety are detailed in OFGF03-ZX-0002-(Corrective Action Program).
4.6 Configuration Control Programa 4.6.1 Dverall Configuration Management - The requirements for configuration management are detailed in 0FGF03-EA-0109 (Configuration Management Program).
4.6.2 Flant Hodificati,on - The requiremente for the implementation of Plant Hodifications are detailed in'.
IF-3.01Q (Plant Modifications).
l 4.6.3 Engineering Change Motice Packages - The requirements for the design, approval, lesuance and implementation of Engineering Change Motice Packages are detailed in IF-3.24Q (Engineering Change Notice Package) and 0FGF03-EE-0031 (Design Change Implementation).
4.6.4 Temporary Modifications - The requirements for the implementation and restoration of Temporary Modifications are detailed in 0F0F03-EO-0003 (Temporary Modifications).
4.6.5 Temporary Configuration Changes During Maintenance - The requirements for control of temporary configuration changes during maintenance activities are detailed in 0FGF03-EM-0021 (Control of Configuration Changes).
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Maintenance Work Fractices 0FMF01-EA-0040 and Requirements Rev. 2 Page 11 of 46 4.6.6 Instrumentation Installation - 0FGF03-EE-0056 (Instrumentation Installation) shall be used when major Tubing Support / Rework requires new layout or Tubing / Supports are installed under the Plant Modification Program.
4.6.7 Temporary Mose Control - The requirements for Tontrolling the installation, use and removal of temporary hoses.
i connected to permanent plant system drains, wents or other connections are detailed in 0FGF03-EO-0031 (Temporary Mose Control).
This procedure also provides exceptions of temporary hose installations not covered.
4.7 Material Control Frogram 4.7.1 During the performance of maintenance activities, spare parts, material and equipment are to be controlled in accordance with 0FGF03-EG-0001 (Material control), and include the following requirements:
4.7.1.1 When permanent plant material is not installed in a plant system and it is not marked or tagged with a Requisition Document, UTRCF, Impound Storage Tag or other source document,-
a Maintenance Hold Tag shall be attached to i
the material during times that maintenance is not balng performed on the material.
The i
" Maintenance Hold Tag" shall be completed i
identifying the work control document number, the storage location, the TAG /TFNs number, part number, and the name of the individual applying the tag.
4.7.1.2 Itema that are to be impounded shall be appropriately identified, conta1ued, and protected to prevent loss or damage.
All items shall be tagged with an Impound Storage Tag identifying the Impound Storage number,-
item description, HL&P part number (if applicable), Work Document number, name of individual placing in impound storage, date and other pertinent information.
j 4.7.1.3 The. quality class of replacement parts shall be the same quality class as the parent component unless properly ident'.fied through approved specification, technical evaluation or other design document.
(DR 91-027)
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Maintes& ace Work Freettees CPMf01-EA-0040 and Requirements Rev. 2-Page 12 of 46 4.7.1.4 Items to be reworked shalt 2: Identified by initiating a new Service Request, and shall be properly labeled at all times.
The new Service Request number shall be referenced in the existing Work Fackage.
4.7.1.5 Itema to be held for root cause analysis shall be properly tagged and placed in impound storage and documented in Work Fackage.
4.8 Expendable Materials - The requirements for the handling.and use of expendable materials are detailed in OPGP03-II-0008 (Control ofl Expendable Materials).
These procedures include instructions for ok,sining expendable materials, precautions'in the use of specific expendable materials, and obtaining approval to use newly identified or alternative expsadable materials during maintenance
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activities.
(ONR 82-093) 4.9 Procurement of Haterials - The requirements for procuring materialsaredetailedinOPGF03-ZP-0011(ProcurementofHaterial)l and associated Nuclear Purchasing and Materials Management procedures.
4.10 Hazardous Materials - The requirements for proper packaging of hazardous and non-hazardous waste materials and the cleanup and reporting of spills involving hazardous and non-hazardous materials are detailed in OPGP03-ZH-0003 (Packaging of Hazardous /Non-hazardous vaste Materials for Disposal) and 0FGP03-EH-0006 (Hazardous and Non-hazardous Materials Spill Cleanup and Reporting).
This procedure does not address radioactive material spills.
4.11 Onsite Certification of Items - The requirements for requesting and receiving approval to use alternative materials which are not certified in accordance with originst requirements are detitled in IP-3.11Q (Onsite certification of Items).
In order'for onsite certification to occur the originator must supply as much detailed information as possible about the item to be certified as well as specific detail about the end use of the proposed upgrade.-
4.12 Control of Stainless Steel - The requirements for the handling and use of stainless steel ~during maintenance activities are detailed in 0FGF03-EM-0013 (Control of Stainless Steel).
Maintenance Work Fractices OFMF01-1A-0040 sad Requirements Rev. 2 Page 13 of 46 4.13 Quality Assurance s.nd Quality Control Programs 4.13.1 Quality Assurance Frogram - The requirements for meeting the minimum acceptable standards for an effective Quality Assurance Program in the areas of interest to Maintenance Department Work Supervisors and Craf tenen are detailed in Operations Quality Assurance Flan (OQAF), Section 5.0 (Maintenance, Installation of Modifications, and Related Activities).
4.13.1.1 It is the responsibility of all workers, EgI Nuclear Quality Control personnel, to ensure quality in the performance of their work" activities, and to understand this responsibility and fully implement this responsibility in a competent manner.
4.13.2 Quality Assurance Program for Non Safety-Related Activities - In addition to the Quality Assurance Program, additional Quality Assurance requirements for activities involving Non Safety-Related equipment are detailed in IF-2.10 (Quality Program for Non Safety-Related Equipment and Activities).
4.13.3 Quality Control Inspections - The requirements for inspections of activities covered by the Quality Assurance Program and Quality. Assurance Program for Non Safety-Related Activities performed by Quality Control personnel are detailed in QCP-2.0 (Quality Control Procedure Inspection Activity).
4.13.4 Regulatory Guide 1.75 Quality Control Inspections 4.13.4.1 Whenever a work activity (both Quality and Non-Quality Related) involving Non-Class 1E items that are related to Regulatory Guide 1.75 (Physical Independence of Electrical Systems) is performed which may affect electrical circuit independence or physic'al 1
separation, Quality Control must'be notified to perlera an inspection (ST-HL-HS-2111).
4.14 Housekeeping and System Cleanness Program i
4.14.1 Housekeeping Program - The requirements for maintaining acceptable levels of housekeeping during maintenance activities are detailed in 0FGF03-EA-0098 (Station Housekeeping).
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Maintenance Work Fractices OFNF01-EA-0040 and Requirements Rev. 1 Fage 14 of 46 4.14.2 System Cleanness Program - The requirements for controlling system cleanness during maintenance activities are detailed in OPGF03-EN-0006 (Control of System Cleanness During Maintenance).
4.15 Radiation Protection Programs i
4.15.1 overall Radiation Protection Program - The requirements for implementing the Radiation Frotection Programe are detailed in OFGF03-ER-0001 (Radiation Frotection Program).
4.15.2 ALAR 4 Frogram - The requirements for implementing the 'As Low As Reasonably Achievable" (ALARA) program are detailed in IF-2.03Q (Radiation Protection and ALARA Programs) and 0FGF03-ER-0008 (ALARA Frogram).
4.15.3 Radiation Work Fermit Program - The requirements for requesting and using Radiation Work Fenmits (RWF) are detailed in 0FGF03-ZR-0002 (Request and Ues of Radiation Work Fermits',.
4.15.4 Radioactive Material and Waste Control Program - The requirements for controlling radioactive material and waste are detailed in OPGP03-ZR-0012 (Radioactive Material and Weste Control Program).
4.15.5 Contamination Control Program - The requirements for controlling and minimialns radioactive contamination are detailed in 0FGF03-ER-0044 (Contamination Control Program).
4.15.6 Radiological Controle for Diving Operations - The requirements for controlling exposure to radiation and contamination during diving operations are detailed in 0FRF07-EA-0001 (Performance of High Raposure Work).
4.16 Control of Special Processen t
4.16.1 Overall Control of Special Frocesses. The requirements for controlling performance of special processes are detailed in IF-3.15Q (Control of Special Processes), and include instructions in procedural requirements for special processes, personnel qualifications and certification to perform special processes, implementation of special processes, tests and inspections required during and following completion of special processes.
Maintenance Work Fractices OPMF01-EA-0040 and Requirements Rev. 2' Fate 15 of 46 4.16.2 Welding and Heat Treatment'-~The overall requirements for performing welding and heat treatment operations are detailed in 1F-3.10Q (ETFEGS Welding Frogram).
4.16.2.1 The requirements for controlling welding, brasing and soldering activities are detailed in OFNF02-ZW-0001 (General Welding Requirements).
4.16.2.2 The requirements for controlling weld filler materials are detailed in 0FNF02-ZW-0004 i
(Control of Filler Materials).
4.16.2.3 The requirements for controlling post veld heat treetment are detsited in CPNF02-ZW-0005 (Control of Fostweld Heat Treatment),
j 4.17 Tool and Measuring &" Test Equipment Program 4.17.1 The requirements for controlling the issuance and use of tools, control'of hoses issued from RCA Tool room issue l
area and Measuring and Test Equipment (N&TE) are detailed-In DFGF03-ZH-0007 (Tool and Measuring & Test Equipment control) and IF-1.54Q (Hesouring & Test Equipment Control.
Frogram).
j 4.18 Fastener Torquing and Detensioning.- The requirements for controlling fastener torquing and detensioning activities are detailed in OPMP02-ZG-0004 (Fastener Torquing and-Detensioning).
4.18.1 Torquing of fasteners on Safety-Related equipment or systems shall be performed using torque values and sequences specified in accordance with approved procedures, ins t ruct ions, drawings, vendor manuals, vendor specifications, or the alternate specifications contained in OPMP02-ZG-0004 (Fastener Torquing and Detensioning).
4.18.2 The Torquing Worksheet (OFKP02-ZG-0004-1) is an optional means for documenting the determination of torque values, increments and sequences as well as the actual results of torquing operations and inspection to be used when documentation requirements are not already included in an approved procedure or specific work instructions.
4.18.3 The Torquing value Verification Worksheet (OPMP02-ZG-0004-2) provides optional means for the craf tsman to verify and document torque values prior to and after torquing operations, using the Torque Sensor System.
Maintenance Work Fracticos OFNF01-ZA-0040 and Requirements Rev. 2 Fage 16 of 46 4.19 ASME Section 11 Progrca 4.19.1 ASME Section XI Repairs and Replacements - The requirements for controlling ASME Section II Repairs and Replacements are detailed in IF-3.07Q (ASME Section XI Repair / Replacement Program).
4.19.2 ASME Section XI Fost-Maintenance Pressure Testa - The requirements for controlling the performance of ASME Section XI Fost-Maintenance Pressure Tests are detailed in OPGP03-ZE-0027 (%SHI Section XI Repair, Replacement j
and Fost-Maintenance Pressure Testing).
i 4.20 Industrial Safety Programe 4.20.1 Overall Industrial Safety Frogram - The requirements for the Industrial Safety Program are detailed in IF-1.40 (Industrial Safety Program) and 0FGP03-ZI-0001 l
(Industrial Safety Program).
4.20.2 Temporary Scaffolding and Ladders Frogram 4.20.2.1 The requirements for ensuring that temporary scaffolding is erected and maintained in a safe condition are detailed in OPGP03-ZI-0002 (Industrial Safety Criteria For Temporary Scaffolding) and 0FGP03-ZH-0028 (Erection and Use of Temporary Scaffolding).
4.20.2.2 The requirements for ensuring that ladders are used correctly and are maintained in a safe condition are detailed in 0FGF03-ZI-0017 (Use of Fortable Ladders).
4.20.3 Personal Protective Equipment Program - The requirements for selecting and using appropriate personal protective equipment ara detailed in OPGP03-ZI-0003 (Personal Protective Equipment).
4.20.4 Hearing Conservation Program - The requirements for protection and conservation of hearing of site personnel are detailed in CPGP03-ZI-0013 (Hearing Conservation Eregram).
4.20.5 Heat Stress Frr 23 - The requirements for protection of site personnel.- ct heat stress are detailed in 0FGF03-ZI-0005 ~. dent Stress Program).'
Maintenance Work'Fracticos 0FNF01-EA-00t0 sad Reevirements Rev. 2 Page 17 of 46 4.20.6 Asbestos Abatement Program - The requirements for protection of site personnel from inadvertent enposure to asbestos are detailed in OFGP03-ZI-0006 (Asbestos Abatement Program).
4.20.7 Confined Space Entry Program - The requirements for control of entry into confined spaces are detailed in' 0FGF03-EI-0007 (Confined Space Entry Frogram).'
4.20.8 Warning Signs and Barriers - The requirements for the erection and use of warning signs and barriers are detailed in 0FGF03-EI-0011 (Warning Signs and Barriers).-
4.20.9 Hazard Communication Program - The requirements for reporting of physical-hazards'onsite to the Industrial Safety Department for corrective action are detailed in OPGF03-11-0012 (Hazard Communication Program).
l 4.20.10 First Report of Injury - The requirements for reporting injury to personnel onsite are detailed in 0FGF03-EI-0010 i
(Industrial Safety Accident /I'cident Investigation).
n 4.20.11 Reporting Industrial Safety Concerns - The requirements for reporting concerns related to the implementation of the Industrial Safety Frogram onsite, including procedure problems or program compliance, are detailed in OFGF03-ZI-0019 (Reporting Industrial Safety Cohcarne).
4.20.12 Industrial Compressed Air and Gases - The requirements i
for the use of industrial compressed air and gases are detailed in OPGP03-ZI-0015 (Industrial Compressed Air and Oases).
4.20.13 Hand and Power Tool Safety - The requirements for the use of hand and power tools are detailed in 0FGF03-EI-0016 (Hand and Power Tool Safety)..
4.20.14 Transportation of Personnel On Site - The requirements for transporting personnel onsite in any of the allowed vehicle types are detailed in OPGF03-ZI-001g (Transportation of Forsonnel On Site).
4.20.15 Electrical Safety - The requiremente for performing work activities involving electrical components are detailed in OPGP03-ZI-0021 (Electrical Safety).
l Maintenanea Work Practices OPHF01-ZA-0040 and Requirements Rev. 2 Page 18 of 46 4.20.16 Chemical Safety - The requiremente for performing work activities involving the use of chemicals or exposure to
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chemicals are detailed in OPGP03-ZI-0023 (Chemical Safety), and include instructions for understanding the I
precautions for the use of hazardous chemicals as described by the Material Safety Data Sheets (KSDS) available from the Industrial Safety Department and using personal protective equipment appropriate for the type of chemical exposure anticipated.
4.20.17 General Rigging - The requirements for using rigging during maintenance activities are detailed in OPGP03-ZI-0026 (General Rigging).
4.21 Fire Protection Program 4.21.1 Overall Fire Protection Programs - The requirements of the Fire Protection Program are detailed in OPCP03-ZF-0001 (Fire Protection). All personnel are required to comply with the requirements of the Fire Protection Program and the requirements of the procedures controlling activities which may impact fire detection of fire protection systems and equipment.
4.21.2 Breaching of Fire Barriers - The requirements of performing work activities which result in breaching a fire barrier are detailed in OPGP03-ZF-0003 (Breaching of' Fire Barriers), and include instructions for initiating a Permit to Breach Fire Barrier Form and ensuring appropriate actions are taken when a fire barrier is breached.
4.21.3 Breaching of NVAC Boundarise - The requirements of performing work activittee which result in breaching a i
KVAC boundary are detailed in OPGP03-HZ-0001-(Breaching of HVAC Boundaries), and include instructions for initiating a permit to breach a HVAC boundary form and ensuring appropriate actions are taken when a HVAC boundary is breached.
4.21.4 Control of Transient Fire Loads 4.21.4.1 The requirement's for minimizing or eliminating the introduction and accumulation of transient combustible material onsite and in the power plant structures are detailed in OPGP03-ZF-0004 (Control of Transient Fire Leeds).
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Malatenance Work Fractices 0FMF01-EA-0040 and Requirements Rev. 2 Page 19 of 46 4.21.4.2 The Combustible Material Storage Authorisation Form is required for storing combustible materials unattended in.s power plant i
structure for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
It shall i
be forwarded by the Owner or Work supervisor to the Fire Protection Coordinator for approval, and a copy of the approved form shall be posted in the area where the combustible material is to be stored, until renewal of permit is required or area is no longer needed as a storage area.
4.21.5 Use of Flammable Liquids and Gases - The requirements for using and handling combustible and flammable liquids and 1
gases are detailed in 0FGF03-ZF-0005 (Use of Flammable Liquids and Games), and include instructions for initiating a Storage of Liquids and Gases Form, limiting the quantity of flammable or combustible liquids which personnel performing work activities shall possess, storing flammable or combustible liquide in appropriate containers, and using flammable gas cylinders.
4.21.6 Control of Ignition Sources - The requirements for ensuring fire prevention during work activities involving ignition sources are detailed in 0FGF03-ZF-0006 (Control of Ignition Sources), and include instructions for initiating a Hot Work Fermit Form, initiating an Open Burn Permit Form, and establishing fire prevention methods when using ignition sources.
4.21.7 Control of Solvents, Painte, and Painting Frocesses - The requirements for ensuring fire prevention, protection of j
smoke detectors, protection of HVAC filters, and protection of the Toxic Gas Analyzer System during work activities involving painting or solvents are detailed in.
0FGF03-ZF-0007 (Control of Solvents, Paints, and Painting Frocesses), and include instructions for initiating a Fainting Fermit Form, establishing fire prevention methods when using paints or solvents, and ensuring" precautions are taken and approvals obtained to use paints or solvents in an area affecting smoke detectors.
HVAC filters, or the Toxie Gas Analyser system.
4.21.8 Use of Fire Frotection Equipment - The requirements for obtaining and using fire protection equipment are detailed in 0FGF03-Er-0006 (Use of Fire Protection g uipment), and include instructions for using automatic q
suppression systems, hydrants and home stations, portable extinguishers, and Fire frigade equipment.
Maintenance Work Fractices OPMP01-EA-0040 and Requirements Rev. 2 Page 20 of 46 4.21.9 Fire Watch Frogram - The requirements for establishing a l
fire watch are detailed in 0FGF03-EF-0013 (Fire Watch i
Program), and include instructions for establishing and completing a Fire Watch Log, establishing the minimum training requirements for the fire watches. The duties and responsibilities of. a fire watch are also described.
4.21.10 Fire Protection Unanticipated Impairment - The requirements for responding to' unanticipated impairments of a fire protection. system or component are detailed in 0FGF03-EF-0017 (Fire Protection Unanticipated Impairment), and include instructions for immediately notifying the Shif t Supervisor upon discovery of the impairment.
4.22 Security Programs 4.22.1 Overall Security Frogram - It is the responsibility of all personnel to IMKIDIATELY notify Security if a violation or suspected violation of any security procedure, security barrier, or security feature is discovered.
(DR 90-030) (ST-ML-AE-2593) t 4.22.2 Vehicle and Material Access to the Protected Area - The requirements for transporting vehicles and materials into the Protected Area of the site are detailed in 0FGF03-ES-0002 (Yehicle and Material Access to the Protected Area).
4.22.3 Control of Security Related Keys,. Locks, Cores and Key i
Cards - The requirements for accountability and control of keys, locks, cores and key cards are detailed in IF-7.10 (Site Administrative Lock and Key control) and 0FGF03-ZS-0005 (Control of Security Related Keys, Locks,
)
Cores and Key Cards).
4.22.4 Breaching of Security Barriers - A breach of a security barrier is defined as any. work activity which results in degradation of a security. barrier to a point where the barrier loses all or part of its ability to preclude unauthorized access to the area it protects.-
4.22.4.1 A security barrier includes those components of construction (walls, roofs, floors, ce111 ass, penetration seals or closures and security doors and hatches) or equipment (such as pumps drawing water from outside the Protected Area (FA)) which have as a primary or iceidental purpose the preclusion of unauthorized access to the area protected by the barrier.
(SPR 870374)
Maintenance Work Fractices OFNF01-EA-0040 and Requirements Rev. 2 Page 21 of 46 4.22.4.2 A breach is any penetration in a security barrier in excess of ninety-six (96) square or more inches with at least one dimension in excess of six (6) inches.
Additionally. any activity, work; equipment, location, structure (e.g. scaf folding) or modification whleh -
permits access by bypassing a security barrier is considered a breach 4.22.5. Property Fermits and Property Removal Control - The requirements for removing company or personal property from the Protected Area are detailed fu 0FCF03-1A-0107 (Security of South Texas Froject Electric Generating station).
4.22.6 Material Access to the Reactor Containment Building -
Certain materiale are controlled by Becurity upon entry into the Reactor Containment Building for Security reasons, and include the followings (WAR 90-252) a.
Timanable gases and flammable liquide, as defined in 0FGF03-EF-0005 (Use of Flammable Liquids and Games).
b.
Cadweld exothermic powder c.
Oxygen acetylene torches d.
Caustic chemicals such as sedium hydroxide (caustic soda), acids, acetones, and alcohols or other caustic, corrosive or volatile compounds listed in the Expendable Materials Manual.
4.22.6.1 These materials shall be logged into and out-of the Reactor Containment Building by Security personnel, and should be minimized to the lowest amounts necessary for the work activity.
4.23 Supporting Programa.
4.23.1 Equipment Labeling Program - The requirements for permanent labeling of plant equipment and components are detailed in IF-1.65Q (System and Component Labeling) and i
OPGP03-ZO-0020 (Equipment Labeling).
I 4.23.2 Site Environmental Compliance Frogram - The requirements for complying with commitments and regulatory requirements for the protection of the environment are detailed in 0FGF03-ZO-0025 (Site Environmental Compliance).
j Maintenance _Vork Fractices 0FNF01-EA-0040 i
and Reevirements Rev. 2 Fage 22 of 46-
]
4.23.3 Lubrication Program - The requirements for controlling the selection and use of lubricants in plant equipment and components are detailed in OPGP03-EN-0004 (Luhrication Program).
4.23.4 Control of Heavy Loads Program - The requiremente for the lifting and movement of heavy loads over equipment important to safety are detailed in OPGP03-EA-0069 (Control of Heavy Loads).
Controls to ensure compliance with the requirement for control of heavy loade include OFGF03-EO-0002 (Qualifications and Condt:t ?f Operators for Cranes, Holets, and Monorail Systems).
4.23.5 Bulk Drum and Gas cylinder control Frogram - The requirements for control of' bulk drums and gas cy11adere are detailed in OPGP03-EO-0034 (Bulk Drum and Gas Cylinder Control).
4.23.6 Safety / Relief Yalve Frogram - The requirements for maintenance activities involving safety / relief valves are detailed in 0FGF03-EM-0018 (Safety / Relief Valve Frogram).
4.23.7 Diving Control Program - The requirements for control of diving activities are detailed in OPGP03-EN-0027 (Acquisition and Control of Diving Activities).
4.24 Equipment Qualification Program - The requiremente for maintaining the qualification of equipment important to safety are detailed in IF-1.12Q (Equipment Qualification Program), and include instructions for determining initial qualification requiremente for equipment dependent on the expected environment the equipment will experience and determining requirements for performing maintenance on qualified equipment to maintain the appropriate level of. readiness for the affected equipment.'
4.24.1 To prevent moisture intrusion into safety-related electrical equipment either restore all gaskets, vapor barriers and. seals to original condition or replace any gasket, vapor barrier or seal if the integrity of the item is in doubt.
Special cara must always be.taken when performing maintenance activities on qualified equipment to ensure that all equipment qualification requirements are maintained.
4.25 Conduct of Testing 4.25.1 Control of Testing - The requirements for control of testing performed by Maintenance Department personnel'are detailed in OPGF03-EM-0025 (Maintenance Testing Frogram).
i
Maintenance Work Fracticos OFKF01-EA-0040 and Requirements Rev. 2 Fase 23 of 46 4.25.2 Fost-Maintenanse Teeting - The requirements for post-maintecance testing are detailed in 0FCF03-EE-0020 (Fost-Mair.cenance Testing Frogram), and include instructions for determining the appropriate testing to be performed and controlling the Fost-Maintenance Testing Reference Manual.
5.0 Conduct of Maintenance 1
5.1 Training / Qualification - Qualification of Flant Staff Forsonnel (OFGF03-EA-0065) establishes the requirements for qualification of' Nc: lear Plant Operations Department (NPOD) personnel. This procedure applies to HL&F and contract personnel performing quality-related' activities as dese:1 bed in Classification of' Frocedures (0FGF03-IA-0007) that are within the scope of NFOD.
Maintenance activities shall be performed by, or under the direct supervision of qualified personnel (ONR-85-251).
Personnel gus11fied to perform maintenance activities are determined by the Responsible Maintenance Authority.
5.1.1 The Qualification and Certification of Maintenance Personnel (0PMF01-EA-0035) procedure delineates the guidelines, methods, and responsibilities for qualification and certification of Maintenance and Contract personnel within the Maintenance Department performing maintenance activities and/or testing (other than non-destructive examination) in accordance with ANSI N45.2.6-1978 and ANSI N18.1-1971.
5.1.2 The Maintenance Department Training Frograms (1F-8.15Q establishes the training requirements required by Maintenance Department Forsonnel, along with INFO accreditable IEC, Electrical and Mechanical Maintenance initial training activities conducted for apprentices in the Maintenance Department).
5.1.3 OJT/ Qualification Program (IF-8.18) establiahse management policies and requirements for developing,_
spproving, and implementing on-the-job training and task qualification programs. This procedure also establishes the method for providing documented evidence that an individual is eartified to independently, perform a task.
5.1.4 Welding Procedure Specification Preparation and Qualification (OFMF02-ZW-0002) establishes the responsibilitiae and provides the guidelines by which l
welding and brazing procedures are prepared and/or qualified for use.
Maintenance Work Freetices 0FNr01-EA-0040 and Requiremente Rev. 2 Fage 24 of 46 5.1.5 Maintenance Training Bulletins (NTBs) are leeued as necessary by Maintenance Management to bring to the attention of Maintenance Department personnel a problem or concern that has been identified.
The Bulletins usually identify the problem and present a solution or plan of action to deal with the identified item. All maintenance personnel should review NTB's periodically to maintain familiarisation with existing Bu11etime.
5.2 Control of Maintenance Activities 5.2.1 The " Work Frocess Program" (OFGF03-EA-0090) procedure provides instructions for the following:
5.2.1.1 Originating Service Requests for requesting Maintenance Department, Facilities Management, Communications or contractor work activities, including general manpower support services.
5.2.1.2 Reviewing, evaluating and approving Service Requests, including verifying validity and establishing Friority.
5.2.1.3 Forforming and documenting Emergency Maintenance work activities.
5.2.1.4 Determining when a Service Request may be performed as Minor Maintenance or requires a Work Fackage.
5.2.1.5 Performing and documenting Minor Maintenance.
work activities.
5.2.1.6 Performing Engineering evaluation and -
disposition of " Repair", "Use-As-Is" or other nonconforming condition or for providing additional information to the originating department.
5.2.1.7 Forforming and documenting Tiger Team work activies.
5.2.1.8 Developing Work Fackages and Preventive Halstenance Fackages in accordance with approved schedules.
5.2.1.9 Performing and documenting Work Fackage and Preventive Maintenance Package work i
activities.
Maintenance Work Fractices 0FMF01-EA-0040 and Requirements Rev. 2 Page 25 of 46 5.2.1.10 Forforming Fost-Maintenance Tests and Fost-Modification Tests, restoring affected components to service, and reviewing documentation af ter completion of Work Fackage or Preventive Maintenance Package work-activities.
5.2.2 The 'Freventive Maintenance Program * (0F0F03-EM-0002) procedure provides instructions for the implementation of the Preventive Maintenance Program, the process of providing periodic, planned, and predictive maintenance-activities to maintain specifications and operability of permanent equipment.
5.2.3 The " Planner's Guide' provides detailed guidance for the planning, approval and completion review of Work Fackages. The Guide also provides instructions for the i
requesting of various-permits, materials etc., that may be required during performance of maintenance activities.
5.2.4 The " Maintenance Testing Frogram" (0FGF03-EM-0025) procedure provides guidelines for the authorisation and documentation of all tests performed by the Maintenance Department and all Fost-Maintenance Tests subsequent to Service Request or Preventive Maintenance activities.
It.
i also provides guidelines for implementing the requirements of 0FGF03-Eg-0020 (Poet Maintenance Testing i
Frogram).
j 5.2.5 The " Foot-Maintenance Testing Frogram" (OFGF03-Eg-0020) procedure provides instructions to ensure that Fost-Maintenance Tests are performed to verify that maintenance activities are correctly performed, original deficiencies are corrected, and the component, equipment or system affected by the maintenance activity is OPERABLE in accordance with the Technical Specifications, Safety Analysis Report, design requirements, and applicable codes.
5.2.6 The " Control of Configuration Changes" (OFGP03-EM-0021) procedura provides instructions for the control of temporary configuration changes including lifting and landing electrical leads, installation and removal of-electrical / mechanical jumpers, installation and removal of fuses, etc.
Any changes are documented on
' Configuration Change Log" (OFGF03-EN-0021-1).
Lifted leads shall not be used on safety related systems when other practical means are available to perform the function (ST-KL-AE-2265).
Naintenance Work Fractices OPMF01-EA-0040 i
and Requirements Rev. 2
)
Fage 26 of 46 5.2.7 The " Plant Surveillance Frogram" (OFGF03-ZE-0004) describes the administrative structure and division of responsibilities for implementation and control, and is applicable to those tests, inspections and analysis performed to satisfy Technical Specification I
requirements.
5.2.8 The " Temporary Modifications" (OFCP03-20-0003) procedure provides instructions for the installation, documentation and restoration of temporary changes made to plant equipment that do not conform with drawings or other design documents.
5.2.9 The " Maintenance Department Standing Orders and Night Orders" (OFNF01-EA-0033) procedure provides instructions for the preparation, approval, and implementation of Maintenance Department Standing Crders and Maintenance Department / Division Night Orders in accordance with the requirements of the Operations Quality Assurance Flan, Section 3.0.:
5.2.10 Working under Direct Supervision (Work Direction)
(DR 91-059) (SFR 920534) (SFR 920954) l 5.2.10.1 Craftsmen performing general work at STF are required to be " task" certified unless the specific exceptions as outlined in IF-8.18Q -
(OJT/ Qualification Program) are met and are documented. Work Supervisors shall be cognizant of the scope of assigned work, and should assign only certified personnel to jobs requiring task certification.
l 5.2.10.2 If certified personnel are not available, the job must be performed under Work Direction in accordance with OPGF03-EA-0113 (Work Direction).
NOTE What is important to understand is that when a work package is signed off by a supervisor, he is testifying by his signature that he has exercised the necessary degree of supervision to ensure the work was performed (safely and correctly.
i
j Maintenance Work Fractices OPHP01-EA-0040 and Requirements Rev. 2 Fage 27 of 46 5.2.11 Maintenance Yorification Point (NYF) 5.2.11.1 Maintenance Yorification Point (NYF) is a work hold point assigned to a work package by the Responsible Maintenance Authority (RRA) or Work Supervisor that requires the craft performing a work function to stop and notify their Work Supervisor that a verification point in-the work' instructions has been reached and the Work Supervisor is required to witness a specific function or notify "another group" that a support function is required to be performed and verified prior to continuing work activities.
5.2.11.2 When a verification step is signed off, the signature / initials are verifying the step was performed, and the signer is accepting full responsibility for that action step.
NOTE When a Work Supervisor signs an NYF, this means that the Work Supervisor personally made the inspection or personally contacted another group to perform the inspection.
The Work Supervisor cannot designate another individual to perform the task and subsequently sign off the NYF when it is reported back that the task has been completed. The Maintenance Manager is the only person authorized to grant a required / desired exception to this requirement. (Speakout Concern No. 12177) 5.2.11.3 When a Maintenance Yorification Point (NYF) is assigned so that 'another group" is required to perform a support function (another group-refers to another technical group which is required to support the primary araft responsible for the task due to technical expertise or certification) the Work Supervisor SHALL verify that the designated function required from the "other group" has been completed and acceptable before he signs off the verification point and allows work to continue. (speakout Concern No. 12177)
Maintenance Work Fractices CPMF01-EA-0040 and Requirements Rev. 2 Page 28 of 46 5.3 Plant Material Condition 5.3.1 Inspections shall be conducted as specified on the Work Control Document or in other procedures to determine material condition of plant structures, systems, and equipment such that they are maintained to support safe
[
and reliable operation.
Inspectiens shall include, but are not limited to:
a.
Checking that fluid system leaks-are minimised, b.
I&C, electrical, and mechanical systems and equipment are in good working condition.
c.
Established lubrication programa are followed.'
d.
Tasteners, supports and insulation are in place and operable.
e.
Cleanness and preservation of assigned plant areas is maintained.
f.
Electrical leads are not landed under plastic screws.
Service Ruquests shall be submitted for all deficiencies identified on structures, systems..and-components in accordance with 0FGF03-EA-0090 (Vork Frocess Program).
5.3.2 Work Supervisors should periodically observe maintenance activities for adherence to work control programs and to determine the ef f ectiveness of these programs in maintaining plant material conditions.
5.3.3 All personnel involved in the performance of maintenance activities are responsible for reporting any abnormal or unusual conditions found to the cognizant Supervisor for investigation. These include water or steam leaks, conditions indicative of water hammer, erosion or corrosion, pitting, etc.
(SER 84-069).
5.3.4 All personnel involved in the performance of maintenance activities are responalble for ensuring that items restored after maintenance are placed back in their original condition. These will include but not be limited to:
5.3.4.1 Replacement fuses shall be proper size and type.
(80gR 83-05) (SOER 81-015) 5.3.4.2 Replace gaskets, vapor barriers, and seals to original condition.
Do not reuse these itema when integrity is in doubt.
(IEN 84-57)
I Maintenance Work Practices OPMP01-EA-0040 and Requirements Rev. 2 Page 29 of 46 5.3.4.3 Label electrical wires, hoses, and air lines prior to disconnecting to minimize improper j
hookups when reconnecting.
(IEN 85-02) l 5.3.4.4 Any work activities which involve the
' manipulation" of conductors shall adhere to, the bend radius criteria as specified in:
OPNP02-ME-0013 (Cable Terminations);"
5.3.5 Work-Requiring Insulation Removal 5.3.5.1 Removal of insulation shall be by a pennit issued against the Service Request.
5.3.5.2 Upon completion of the work activity, the lead-eraft shall remove the 3R tag, complete and hang a-* Maintenance Work in Process"' tag on the component requiring the insulation.
5.3.5.3 when complete the craft reinstalling the insulation shall remove the " Maintenance Work in Process' tag and notify the lead craft.
5.3.6 Component data fields.used in the generation of work i
packages contain information that is supplied from the Master Equipment Database (NED) maintained by the Design i
Engineering Department (DED).. Maintenance Department i
personnel noting an error or omission in an MED data field should submit a " Master Equipment Database Change t
Form" to the MED Coordinator in Maintenance support for i
disposition.
I 5.4 Maintenance Procedures i
f NOTE When a signature is required on a Maintenance Department document and the designated person is unavailable, his signature may be obtained using the telephone.
Requestor shall enter requestors NAME, TIME, DATE and words sinfiar to 'Per Telecon with NAME".
6 r-
- - - +
e-
I Maintenance Work Fractices OFMF01-EA-0040 and Reeutrements Rev. 2 Fase 30 of 46 5.4.1 Maintenance Procedures shall be developed, reviewed, and~
{
approved in accordance with one or more of the following:
ORGF03-EA-0002 (71 ant Irocedures), OFNF01-EA-0004*
(Maintenance Fr9eedures), or 0FCF03-EA-0039 (Plant Frocedures Writer's Guide).
Surveillance Procedures are prepared !c accordance with 0FGF03-EE-0005 (Plant Surveillance Procedure Freparation).
5.4.1 Written procedures and instructions which goverm maintenance activities shall include sufficient detail to ensure satisfactory completion of the work, but will not necessarily include step by step delineation of' basic skills normally possessed by certified maintenance personnel.
5.4.3 All personnel are er'ouraged to provide recommendations I
for changes to procedures that will aid the user, clarify requirements, or provide information that will enhance.
Job performance.
Refer to 0FGF03-EA-0002 (Flant Frocedures).
5.4.4 In the event of an emergency situation not covered by a procedure, maintenance personnel shall take action to
{
minimize personnel injury, damage to the plant, and protect the health and safety of the public, as directed by the Shift Supervisor.
5.4.5 It is the responsibility of station personnel, prior to l
the use of. documents issued by ODCC, to review all attachments (drawings, FC's, etc.) that give supplementary direction / instructions against the current revision to ensure that there are no changes that may affect the planned outebne of the work setivity to be performed.
An'y discrepancies between documents should be referred to a supervisor for evaluation and resolution.
(ISEG REPORT (9-87) (SPR 870463) (DR 89-107).
l 5.4.6 When a work activity requires personnel in different locations to perform the activity, or when a work activity is to be performed in a contaminated ares, copies of the required work control document and associated documentation stamped " DUPLICATE" may be issued and shall be controlled per the following guidelines:
5.4.6.1 Work Supervisors shall ensure the total number of copies issued are entered in the work instructions of the original work package.
Maintenance Work Fracticoe OFMF01-EA-0040 and Requirement $
Rev. 2 Page 31 of 46 5.4.6.2 Vork~ 8upervisors shall ensure that all changes, initials, signatures, data and information entered ~on ' DUPLICATE" Work Control Documents and "DUFLICATE" working copies of procedures are transferred by the person (s) who performed that task or step to the original Work Control Document and original working copies of procedures upon completion of the work activity.
5.4.6.3 Only WORKING COPIES of procedures or WORKING COFIES of procedures stamped " DUPLICATE" shall be used. The current revision shall be verified prior'to work start and during the Work Supervisor's close out review.
DO NOT USE any other copies of procedures.
5.5 Satety l
5.5.1 Personnel safety is the responsibility of all personnel.
Maintenance personnel shall comply with the requirekants of the STFIGS Industrial Safety Program.
5.5.2 Safety standards and accident prevention techniques should be used on all jobs to help ansure a safe work place.
5.5.3 Supervisors, Crew Leaders, and Leeds shall conduct l
routine inspection of work sites and work practices to i
identify safety hazards, and take timely action to j
resolve safety deficiencies.
5.5.4 Forsonnel should immediately report'any injury, saf6ty hazard, or violation to their Supervisor in accordance with OFGF03-EI-0010 (Industrial Safety Accident / Incident Investigation).
5.5.4.1 Tor emergency medical assistance call the appropriate control room emergency extension number.
For Unit I and all other site areas, call extension 2111. For Unit 2 call extension 2222.
5.5.5 Accidents or near accidents shall be promptly investigated by station Industrial Safety Representative and cognizant supervisory personnel. Appropriate corrective measures shall be implemented, including dissemination of information concerning the incident to other personnel.
l
t Maintenance Work Fractices Drur01-EA-0040 and Requirements Rev. 2 Page 32 of 46 5.5.6 Maint9 nance activities that are to be performed in a Radiological Area impose additional responsibilities on eac'n individual to minimise his own exposure.
Some-techniques effective in reducing -exposure include, but are not limited to, the followings-5.5.6.1 Review and/or walk procedure and permits through prior to entering radiation area.
5.5.6.2 Spend only time required in High Radiatica Areas to accomplish task.
Discussions required for performing or planning the activity should be done prior to entering the i
High Radiation Area when possible.
If it is necessary to observe the area do sa quickly l
and move to a nearby lower radiatios level j
area to conduct discussions.
It job is
~
temporarily halted for lack of tools, parts, hold points, etc., move to a lower or non-radiation area until work can resume.
5.5.6.3 If extensive work la to be performed'on contaminated equipment or areas, they should be decontaminated under the direction of '
Health Physics personnel prior to performing I
maintenance.
5.5.6.4 Store (laydown) highly radioactive components which have been removed out of the immediate work area when disassembling equipment.
5.5.6.5 Nove parts out of high radiation work areas for cleaning, inspection, etc.
5.5.6.6 Be aware and informed of the radiation and contamination levels present in the work areas.
5.5.6.7 Use shielding materials, as appropriate, to shield high radiation areas or equipment.
Obtain verification and approval prior to the installation of shielding to prevent poselble overstressing of piping, supports, equipment, etc. due to weight of shield material.
Contact Health rhysics personnel for assistance, if required.
t 5.5.6.8 Temporarily cover highly contaminated areas to-i reduce airborne contamination.
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i l
1 i
l i
Maintenance Work Practices 0FNF01-EA-0040 and Requirements' Rev. 2 Fase 33 of 46 5.5.6.9 Notify Radiological Protection personnel when conditions change in the work area, i.e.
opening systems, removal of components or equipment that may have provided shielding, etc.
5.5.7 Maintenpace activities that 'avolve welding, burning, open flame, or spark prode: sag grinding shall be conducted under control of procedures and permite designed to minimize fire hasards during performance of these activities. OPGP03-EF-0006 (Control of Ignition Sources).
5.5.7.1 Areas that have been designated and approved for performance of these activities will be granted an indefinite use permit. Personnel performing work in these areas are responsible for maintaining conditions to prevent dsvelopment of fire hazards.
5.5.7.2 Welding cables and brasing/ cutting hoses-should be routed to prevent damage to the cables or hoses and to minimize tripping hazards.
5.5.7.3 Flash screens shall bc used as necessary to provide personnel protection against flash burns and/or hot sparks.
5.5.7.4 Frovide suitable protection for equipment, cable trays, etc. against hot sparks and slag.
5.6 Maintenance Facilities and Equipment 5.6.1 racilities shall be kept in a clean and orderly condition to present a businesslike and professional atmosphere.
5.6.2 Equipment and tools shall be properly stored when not in
- use, i
5.6.3 Only authorized personnel shall use maintenance facilities and equipment.
Permission to use or operate any equipment or facility shall be given by the Work Supervisor.
5.6.4 Access to shop areas should be limited to those persons on " Official Business Only".
Maintenance Work Fractices 0FNF01-EA-0040 and Reautrements Rev. 2 Page 34 of 46 5.6.5 Fotentially distracting activities during working hours in shops, tool rooms, labs, offices and work places are prohibited. This includes but is not limited to TV's, tspo players / recorders, games, hobbies, horseplay, personal business, phone calls (encept for company business and emergencies) and reading.that is not job reisted.
5.6.5 Only documents authorised by the cognisant Supervisor (postdre, notes, etc.) are to be used and/or displayed in maintenance facilities, shops, offices and work' places-for the conduct of maintenance activities.
5.6.6.1 The following documents are authorised for use to provide reference information to assist Heintenance personnel in the conduct of their duties.
a.
Equipment specific vendor manuals b.
Published technical reference books and reports.
c.
Controlled drawings d.
Safety manuals, posters, bulletins, notices.
Company and plant policy, administrative, e.
and regulation notices.
5.7 Work Schedules 5.7.1 Adequate shift coverage shall be maintained without routine heavy use of overtime. Frocedure OFGF02-EA-0060 (Dvertime Approval Frogram) provides guidelines for a nominal 40-hour week and overtime on a temporary basis due to shutdowns for refueling, major maintenance or major plant modifications.
5.7.2 Any deviation from the guidelines in OFGF02-EA-0060 shall be authorised by the Flant Manager. Duty Plant Manager or Vice Fresident Nuclear Generation.
5.7.3 Work breaks and lunch periods shall be taken at-prescribed. times unless specifically authorized by the Cognizant Supervisor.
5.7.4 Fersonnel involved in collateral ~ duties and activities such as recreation committee meetings, safety committee meetings, bargaining unit activities, etc. shall notify and schedule their time for these activities with their Supervisor sufficiently in advance to minimise impact on work schedules.
Maintenance Work Fractices OFMF01-EA-0040 and Requirements Rev. 2 Fase 35 of 46 5.8 Management Inspections - 0FGP03-ZA-0073 (Plant Inspection Program) provides a method to ensure the material condition, cleanliness / housekeeping condition, and industrial / safety standards of the plant are maintained through a program of inspection, reporting, follow-up and correction.
This procedure applies to Responsible Area Managers and areas as assigned by the Flant Manager.
5.9 Management Involvement 5.9.1 The Maintenance Department Manager or his designee shall, on a routine basis, address Maintenance personast on topics related to team involvement, productivity, and motivation.
5.9.2 The Maintenance Department Manager or his designes shall periodically review and assess the maintenance program.
This review should include input from Operations, Technical Services,,and individual Division Managers, as well as personal observation.
5.9.3 Maintenance Tsedback 5.9.3.1 Feedback from field personnel to management is an essential tool that can provide needed input and can help to improve maintenance activities.
The " Maintenance Feedback Request
- is provided for anyone in the Maintenance Department to fill out to identify all types of feedback, such as, but not limited tot a.
standard Forformance Tools:
FMsg work packages procedures, b.
Specific Issues Safety improvement areas (be specific). process bottlenecks (things which prevent performing eight hours of productive work in an eight hour -shif t):
Maintenance Interface Group support 1.e.
conflicting processes and/or procedures or perception of' lack of' support.
m
Maintenance Work Fractices OPMF01-EA-0040 and Requirements Rev. 2 i
Fage 36 of 46 c.
Maintenance Manager Issuess Frocese improvements (to help. solve bottlenecks):
specific modifications which will enhance I
long tena maintenance, e.g., isolation or double isolation valves an a selected i
components specific modification or idea which could reduce outage length by moving scope outside of outage, e.g.,
replacing safety valves with spares during outage, rework removed safety valves af ter outage and return to warehouse stock.
5.10 Repeat Maintenance 5.10.1 Reporting, tracking and evaluating Repeat Maintenance on components is a valuable maintenance tool. Reducing equipment unavailability due to maintenance or failure j
helps increase overall plant reliability and reduces j
operating costs. The data obtained allows management to identify potential design problems, training inadequacies i
and ineffective repair methods.
It is the responelbility of all maintenance personnel to identify Repeat Maintenance (or potential repeat maintenance) either to their supervision or by completing a Repeat Maintenance Identification Sheet (Addendum 1) and forwarding it to Maintenance Planning.
5.10.2 Repeat Maintenance is defined as:
5.10.2.1 Reperformance of an entire maintenance activity or steps in a maintenance work package prior to returning the components to-se rvice.
Causes of this type of repeat maintenance could bei incorrect reassembly, damage -to other componente during maintenance, or failure of a post-maintenance test whereby failure is directly attributed to the maintenance performed.'
5.10.2.2 Any maintenance activity on a component which has had similar maintenance performed on it within a predetermined time (e.g., twelve (12) months).
6.0 Electrical Work Fractices 6.1 Vire and Cable Terminations - The requirements for controlling initial instellation or reinstallation of wire and table terminations are detailed in 0FNF02-NZ-0013 (Cable Terminations).
l
Maintenance Work Fractices OFMF01-EA-0040 sad Requiremente Rev. 2 Fage 37 of 46 6.2 Raychem Insulation Application - The requirements for controlling application of Raychem hint shrinkable insulating materiale are detailed in OPHP02-NE-0053 (Raychem Insulation Application).
6.3 Design Configuration Control of Electrical Circuit Breakers.
6.3.1 Design configuration control of electrical circuit breakers rated 480Y or greater must be maintained during the repair, rework or replacement of electrical circuit breakers to ensure proper operation of these components and design protection / auxiliary functions for system operation.
The " Circuit Breaker Configuration Change Form" will be used to accomplish the above control in accordance with the Planner's Guide.
The form will be included or added to a work package by the planner as.
required.
The F1 saner shall complete and verify Sections One (1) and.Three (3).
The electrical craft shall complete and/or verify Sections Two (2) and Four (4) as applicable. The Work Supervisor shall complete Section Five (5).
(SPR 910162) 6.3.2 Transfer of circuit breakers between-Facilities shall be performed in accordance with IF-6.01Q (Control of Material) and OPGP03-ZG-0001 (Haterial control).
6.3.3 Utilization of circuit breakers under control.of Nuclear Furchasing and Materials Management (NTMM) shall be performed in accordance with IP-6.01Q (Control'of Material), NFHH-7.03Q (Returning Materials) and NFHH-7.07Q (Removal and Replacement of Components Parts and Pieces of Material in NPNH Control).
s Maintenance Work Fractices 0FN201-EA-0040 and Requiremenle Rev. 2 Fase 38 of 46 6.4 Adjustments to Notor Oil Level, $00HF and Above a a aa A eaa a eeaeaaaa a ea eaa e a
a CAUTION a
e If sight glasses indicate that oil is not
- present or the sight glass is completely
- full while the motor is operating, NOTIFY
- THE CONTROL ROOM Il8EDIATELY prior to coatseting the owner or planner.
a e
A A A A A A A A eeA 4 eA eeeA A A & 4 A e NOTE Adding or draining of oil is prohibited when the pump-la running, except when critical to.
proper operation of the motor and then only with the specific approval of the Shif t Supervisor.
The standard practice should be limited to making oil level adjustments when the pump is secured.
6.4.1 If oil level indicati,ns on large motors are found out of tolerance, maintenance personnel shall notify the Cognizant Owner or Flanner.
6.4.2 The cognizant Owner or Flanner shall contact the responsible system engineer for possible root cause analysis and recommendations prior to performance of any corrective actione, in accordance with the Flanner's Guide.
6.4.3 All corrective actions shall be documented on the applicable work document, in accordance with the Planners Guide.
7.0 Hechanical Work Fracticoe 7.1 Alternative Valve Facking and Live-Load Valve Packing.
7.1.1 The requirements for controlling installation of alternative valve packing and live-load valve packing designs are detailed in OFNF02-ZG-0011 (Alternative Yalve Facking and Live-Load valve Facking).
f
Maintenance Work Fractices 0FNF01-EA-0040 and Requirements Rev. 2 Fase 39 of 46 7.1.2 The Valve Packing Data Sheet (Addendum 1 of 0FNF02-ZG-0011) shall be used to document valve packing activities whenever the valve packing design has been modified from the original design as specified by the valve manufacture or vendor under specification SL749TS1018 (Alternative Valve Packing and Live-Load Design) and whenever a valve is to be " live-loaded".in an effort to stop leakage or extend the life of the valve packing.
8.0 References 8.1 ANSI N18.1 - 1971 - Selection and Training of Nuclear Fower Plant Personnel.
8.2 IP-1.12Q (Equipment Qualification Program), Rev. 2.-
8.3 IF-1.40 (Industrial Safety Program), Rev. O.
8.4 IF-1.54Q (Measuring and Test Equipment Control Program), Rev. 3.
8.5 IP-1.65Q (System and Component Labeling), Rev. O.
8.6 IF-2.03Q (Radiation Protection and ALARA Programe), Rev. 2:
8,7 IP-2.10 (Quality Program for Non Safety-Related Equipment and Activities),~Rev. 4.
8.8 IF-3.01Q (Plant Modifications), Rev. 8.
I 8.9 IP-3.07Q (A3HE Section XI Repair / Replacement Program), Rev. 5.
8.10 IF-3.10Q (STFEGS Welding Frogram), Rev. 2.
8.11 IF-3.11Q (Onsite Certification of Items), Rev.
2.-
8.12 tt-3.15Q (Control of Special Frocesses), Rev. 2.
8.13 IP-3.24Q (Engineering Change Notice Esekage), Rev. 5.
8.14 IP-6.01Q (Control of Haterials), Rev. 12.
8.15 IF-8.15Q (Haintenance Craft Training Frogram), Rev. 1.
8.16 IF-8.18 (QJT/ Qualification Program), Rev. 6.
8.17 NFMH-7.03Q (Returning Materials), Rev. 4.
8.18 NFHH-7.07Q (Removal and Replacement of Components Parts and Fleces of Material in NFHH Control), Rev. 1
i Maintenance Work Fractices 0FMF01-EA-0040 t
asd Requirements Rev. 2 Fage 40 of 46 l
8.19 OMR-82-093 (Damaged Seals on Fressure Transmitters) 8.20 OMR-85-251 (Inadvertent Scrans Due to Misoperation of Instrument Yalves) 8.21 OFGF02-ZA-0060 (Overtime Approval Frogram), Rev. 4.
8.22 0FGF03-HZ-0001 (Srsaching of NYAC Boundaries), Rev. 0 8.23 0FGP03-ZA-0002 (Plant Procedures), Rev. 22.
l 8.24 0FGF03-ZA-0007 (Classification of Frocedures), Rev. 5.
8.25 0FGF03-ZA-0010 (Plant Procedure Adherence and Implementation and '
Independent Yet:1ficatien), Rev. 15.
8.26 0FGF03-ZA-0039 (Flant Procedures Writas Guide), Rev. 11.
8.27 0FGF03-ZA-0065 (Qualif1:Ai~on of Flant Staff Personnel), Re7. 4.
8.28 0FGF03-ZA-0069 (Control of Heavy Loads), Rev. 6.
8.29 0FGF03-IA-0073 (Plant Inspection Program), Rev. 2.
I i
8.30 0FGF03-ZA-UO60 (Work Coordination Program), Rev. 4.
8.31 0FGF03-ZA-0090 (Work Frocess Program), Rev. 6.
8.32 0FGF03-ZA-0098 (Station Housekeeping), Rev. O.
I 8.33 0FGF03-ZA-0107 (Security of the South Texas Froject Electric f
Generating Station), Rev. O.
8.34 0FGF03-ZA-0109 (Configuration Management Program), Rev. O.
8.35 0FGF03-ZA-0113 (Vork Direction), Rev. O.
8.36 0FGF03-ZZ-0004 (Plant Surveillance Frogram), Rev. 11.
~
8.37 0FGF03-ZE-0005 (Plant Surveillance Procedure Freparation),
f Rev. 10.
I 8.38 0FJF03-ZE-0020 (Fost-Maintenance Testing Program), Rev. 3.
8.39 0FGF03-ZE-0027 (ASKE Section II Repair, Replacement and
[
Fost-Maint(nance Preseure Tests), Rev. 5.
8.40 0FGF03-ZE-0031 (Design Change Implementation), Rev. 9.
{
8.41 0FGF03-ZE-0056 (Inr^rumentation Installation), Rev. C.
l r
l Maintenance Work Fractices OPHF01-ZA-0040 l
and Requiremente Rev. 2 Page 41 of 46 8.42 OPGF03-ZF-0001 (Fire Protection), Rev. 5.
8.43 0FGF03-ZF-0003 (Breaching of Fire Barriers), Rev. 6.
8.44 0FGF03-ZF-0004 (Control of Transient Fire Loads), Rev. 1.
8.45 0FGF03-ZF-0005 (Use of Flammable Liquids and Gases), Rev. 4.
8.46 0FGF03-ZF-0006 (Control of Ignition Sources), Rev. 4.
8.47 0FGF03-ZF-0007 (Control of Solvents, Paints, and Painting Processes), Rev. 3.
8.48 0FGF03-ZF-0008 (Use of Fire Frotection Equipment), Rev. 1.
8.49 0FGF03-ZF-0013 (Fire Watch Program), Rev. 4.
8.50 0FGP03-ZF-0017 (Fire Protection Unanticipated Impairment), Rev. 3.
8.51 0FGF03-ZG-0001 (Haterial Control), Rev.
7.-
0.52 0FGF03-ZH-0003 (Facking of Hazardous /Noahasardous Vaste Materials for Disposal), Rev. 3.
8.53 0FGF03-ZH-0006 (Hazardous /Noahasardous Materials Spill Cleanup and Reporting), Rev. 1.
8.54 0FGF03-ZI-0001 (Industrial Safety Frogram), Rev. 1.
8.55 0FGF03-ZI-0003 (Forsonal Protective Equipment), Rev. 4.
8.56 0FGF03-ZI-0005 (Heat Stress Program), Rev. 1.
8.57 0FGF03-II-0006 (Asbestos Abatement Program), Rev. 1.
j 8.58 0FGF03-ZI-0007 (Confined Space Entry Frogram), Rev. 5.
8.59 0FGF03-ZI-0008 (Control of Expendable Materials), Rev. 3. -
8.60 0FGF03-ZI-0010 (Industrial Safety Accident / Incident Investigation), Rev. 2.
8.61 0FCF03-EI-0011 (Varning Signs and Barriere), Rev. 2.
l 8.62 0FGP03-ZI-0012 (Hazard Communication Program), Rev. 1.
8.63 0FGF03-ZI-0013 (Hearing Conservation Program), Rev. 3.
8.64 0FGF03-ZI-0015 (Industrial Compressed Air and Gases), Rev. 1.
8.65 0FGF03-ZI-0016 (Hand and Fower Tool Safety), Rev. 1.
8.66 0FGF03-ZI-0017 (Use of Fortable Ladders), Rev. 2.
wit
Maintenance Work Fractices 0FHF01-ZA-0040 and Requirements Rev. 2 Page 42 of 46 I
8.67 0FGF03-ZI-0019 (Reporting Industrial Safety Concerns), Rev. 2.
l 8.68 0FGF03-ZI-0021 (Electrical Safety), Rev. 1.
8.69 0FGF03-ZI-0023 (Chemical Safety), Rev. 1.
8.70 0FCF03-ZI-0026 (General Rigging), Rev. 2.
8.71 0FGF03-ZM-0002 (Freventive Maintenance.Frogram), Rev. 24.
8.72 0FCF03-ZM-0004 (Lubrication Program), Rev. 5.
8.73 OPGF03-ZH-0006 (Control of System Cleanness During Maintenance),
Rev. 5.
l 8.74 0FGF03-ZH-0007 (Tool and Measuring & Test Equipment Control),
Rev. 7.
8.75 0FGF03-ZM-0013 (Control cf Stainless Steel), Rev. 2'.
l 8.76 0FGF03-ZM-0018 (Safety / Relief Valve Frogram), Rev. 5.
8.77 0FGF03-ZM-0021 (Control of Configuration Changes), Rev. 4.
8.78 0FGF03-ZM-0025 (Maintenance Testing Frogram), Rev. 3.
0FGFf3-ZM-0027 (Acquisition and control of Diving Activities),
0.79
/
Rev. 1.
8.80 0FGF03-ZM-0028 (Erection and Use of Temporary Scaffolding),
Rev. 3.
8.81 0FGF03-ZO-0002 (Qualifications and Conduct of Operators for Cranes, Hofsts, and Monorail Systems). Rev. 3.
l 8.82 0FGF03-ZO-0003 (Temporary Modifications), Rev. 11.
8.83 0FCF03-Zo-0020 (Rguipment Labeling), Rev. 4.
8.84 0FGF03-ZO-0025 (Site Environmental Compliance), Rev. 2.
8.85 0FGF03-ZO-0031 (Temporary Hose Control), Rev. 2.
8.86 0FGF03-ZO-0034 (Bulk Drum and Gas Cylinder Control), Rev.
3.-
8.87 0FGF03-ZO-0039 (Operations Configuration Management), Rev. 3.
8.88 0FGF03-ZF-0011 (Frocurement of Material), Rev. O.
8.89 0FGF03-ZR-0001 (Radiation Protection Program), Rev. 4.
8.90 0FCF03-ZR-0002 (Request and Use of Radiation Work Fermits),
Rev. 9.
Maintenance Work Practices OPNF01-ZA-0040 and Requirements Rev. 2 Fase 43 6f 46 8.91 0FGF03-ZR-0008 (Operational ALARA Program), Rev. 5..
8.92 0FGF03-ZR-0012 (Radioactive Material and Waste Control Program),
Rev. 6.'
8.93 0FGP03-ER-0044 (Contamination Control Program), Rev. 2.
8.94 OPGP03-ZS-0002 (Vehicle and Material Access to the Protected Area), Rev. 10.
8.95 OPGl'03-ZS-0005 (Control of Security Related Reys, Locks, Cores, and Rey Cards), Rev. 9.
6.96 OPGP03-ZS-0011 (Site Administrative Lock and Rey Control), Rev. 1.
~
8.97 OPGP03-ZX-0002 (corrective Action Program), Rev. O.
8.98 OPNP01-ZA-0004 (Maintenance Procedures), Rev. 6.
8.99 OPHP01-ZA-0033 (Maintenance Department Standing Orders and Night Orders), Rev. O.
8.100 OPNF01-ZA-0035 (Qualification and Certification of Maintenance Personnel), Rev. O.
8.101 0FMF02-NZ-0013 (Cable Terminations),.Rev. 3.
8.102 0FNF02-NE-0053 (Raychem Insulation Application), Rev. 2.
8.103 0FMF02-ZG-0004 (Tastener Torquing and Detensioning), Rev. 3.
8.104 OPMF02-ZG-0011 (Alternative Valve Packing and Live-Load Valve Facking), Rev. 4.
8.105 0FKF02-ZW-0001 (General Welding Requirements),' Rev. 2.
8.106 0FNF02-ZW-0002 (Welding Frocedure Specification Freparation and Qualification), Rev. 3.
8.107 0FNF02-ZW-0004 (Control of Filter Haterials), Rev. 6.-
8.108 0FMF02-ZW-0005 (Control of Poetveld Heat Treatment), Rev. 2.
8.109 0FRF07-ZA-0001 (Performance of High Rxposure Work), Rev. 4.
8.110 DR 89-107 (Inadvertent Use of Superseded FM Revision) 8.111 DR 90-030 (Accesa a Security Barrier) 8.112 DR 91-027 (Use of Non-Quality Bulk Material in Quality-Related Components Without Engineering Approval) 8.113 DR 91-059 (Work Direction)
Maintenance-Work Fractices OPHF01-EA-0040 s
and Requirements,
Rev. S Fage 44 of 46 -
8.114 IEN 84-57 (Operating Experience Related to Noisture Intrusion in Safety-Related Electrical Equipment at Commercial Power Plants Reconnecting) 8.115 IEN 85-02 (Improper Installation and Testing of Differential Pressure Transmitters) 8.116 IEN 85-079 (Inadequate Communications between Maintenance, Operations, and Security Forsonnel).
8.117 IEN 86-07 (Lack of Detailed Instruction and Inadequate Observation of Frecautions During Maintenance and Testing of Diesel Generator Woodward Governors).
8.118 INFO Good Fractice MA-318 (Maintenance Work Fackages Flanning),
December 1990.
8.119 ISEG Report 9-87,(Valve Packing Observation) 8.120 Operations Quality Assurance Plan.Section 3.0 (Conduct-of Flant Operations), Rev. 5: Section 5.0 (Maintenance Installation of' Modifications, and Related Activities), Lev. 4.
8.121 Flanners Guide, Rev; O 8.122 QCF-2.0 (Quality Control Frocedure Inspection Activity), Rev. 5.
8.123 SER 84-069 (Damage in Main Steam and Feedwater Systems Caused by Water Hammer and Rapid Vater Transients) 8.124 SOER 81-015 (Partial Loss of D.C. Power)-
8.125 SOER 83-05 (Inadvertent Use of Incorrect Replacement Fuses) i 8.126 Speakout Concern No. 12177 (Maintenance Yerification Foints) 8.127 SFR 870374 (Inadvertent Breach of a Security Barrier Due to Removal of a Fenstration Seal) 8.128 SFR 870463 (Injected NADH from spray additive tank into reactor water storage tank) 8.129 SFR 880088 (Independent Yorification) 8.130 SFR 900400 (Configuration Control - Temporary Wire Markers) 8.131 SER 910162 (480Y Spare Load Center Breaker) 8.132 SER 920098 (Reactor: Trip Due to Falso Reactor Coolant Low Flow Trip Signal) 8.133 SFR 920534 (Maintenance Forsonnel Have Not Been Trained to Revision 5 of IP-8.18Q)
\\
- o A
Maintenance work Practices 0FMF01-ZA-0040 and Requirements Rev. 2 Fase 45 of 46 8.134 SFR 920954 (Definition of Work Dirsetion is Inconsistent in IF-8.18A, 0FGF03-ZA-0090 and MTB-92-025) 8.135 Specification 5L749TS1018 (Alternative Valve Packing and Live Load Design ), Rev. 1 8.136 ST-HL-AI-2265 (Use of Jumpers and Lifted Leads During Routine Maintenance and Testing) 8.137 ST-HL-AE-2593 (Access a Security Barrier) 8.138 ST-ML-HS-2111 (Electrical Separation Problems in the Control Room) 8.i39 WAR 90-252 (Haterial Access to the RCB) 9.0 Support Document 9.1 Addendum 1 - Repeat Maintenance Identification Sheet i
Maintenance Work Fractices OPMF01-F.A-0040 and Requirements Rev. 2:
Page 46 of 46 ADDENDUM 1 Repeat Maintenance Identification Sheet - Typical (Fage 1 of 1)
DISC.
1,0G NO.
I.
Identification: Tag /TFNS No.
Unit System New York Doc.
Date Vrltten Old Work Doc.
Date Complete Equipment
Description:
Description of Potential Repeat Maintenance:
A Identified By
\\
Date II.
Evaluation / Root Causes A
a
/&W/
/ AAP/
/NT/
Froposed Disposition:
2\\
N
'/-
N/
Code Class.:
RMS, RNA, RHO, RMN Resp. Organization Evaluator Date III.
Corrective Actions FR/NCR/RTA/ MATS Initiated:
TES/NO DOC. NO.
Diviolon Manager OR Planning Supv.
CONCURRENCE Date
,y'--
- ~ lf,-.,;
\\,
- . ~i.. T.:.. ~
4 STP 3259A (0823)
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATK)N
',, e PLANT CHANGE FORM REV 3 MT-3 OM i4-(Page 1 of 3) 3O8913 -
PCF NUMBER' M[
WORK occ. No g
- v...
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Prob 1emfCondnion:
aikcAed exy hN
- 2. TAG /IPNS: Y \\ Yh"TI\\ll4O 7-System: MD Unh
/
Priorky Componert/Part
Description:
bE C(b d d 848 d 3.
Recommended Action:
SEE Ct//ACMtad
- IM f Est. Insta!. Date inhiated by: M l'Qt A % 4 e.-
i isA Daie: <, /2 le 3 Pnone:
PCF Accepted by TSE Engineer (Name):
IO!t4f93 n
4.
Disposhon/Doscription of Change; 9ee ctOar d pas e3 g
g4-005069 $@
4 ZE-31 EVAL REQUIRED? YES O NOG DISPOSmON: INTERIM
- O FINALE O RELATED: YES O NO G
(*f0R INTERIM, ATTACH PCF INTERIM 50.59 EVALUATION FORM) 50.59 EVAL REQUIRED? YES O OG (if no,idenitfy the reasons)
NO. OF AMENDMENTS O
60.8 9 fuh f4ptM t' M we d dgp O. - Op(,co3 3A.gg3 g &, 3, 2
k t of g+l 4 g A. NON CONFORMANCE:
B. PAPER CHANGE O
USE AS-IS O
C. REPLACE EQUIVALENT U EP fNEER DA REPA1R D
D. BENEFICIAL CHANGE O
/ /m d'
I m a A
/ dD TEebs REVIEWER REWORK g
E. INVAUDATE D
- DAIE ENGINEER SUPV.
l
ORIGINAL
,Ay,g,.
hr e o
t 51P 3226A (OS/92)
SOUTH TEKAS PROJECT ELECTRIC CENERATING STATION se j j
3OMI3' A PLANT CHANGE FORM PCr NUuBER OPGP03-2A-0090 PACE i Or 2 SC. AFTECTED DESIGN OOCUuCNTS DOCUMENT NUMBER REV.
KEY?
DOCUMENT NUMBER REv.
key?
% t)tiFi4-(97
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8
- 1. PROBLEM / CONDITION:
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4 W 30 8 9 l3 UNIT; WK DOC:
- 2. TAG /TPNS:
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b " C-Ik om M S /d O 3 CouPoNENT DESCRIPT10N -
PART DESCRIPTION 3.RECOuMENDED ACTION:
O WIVO a bt*
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U INITIATf D BY; A^
A DATE:
7 3
- 4. PLANT CHANGE TYPE:
NONCONTORMANCE (NCR)
REPAIR EQUIVALENT CHANGE (REO)
BENEFICIAL CHANCE (ATTACH ECONOuiC EV ION)
DEVELOPMENT AUTHORIZATION (FOR BENEFICIAL CHANGES ONLY):
a lA o /A i
MAINTEN ANCE u AN AGER DATE DESIGN ENGINE ANAGER DATE 5 DISPOSiltON/ TECHNICAL JUSTarlCATION:
E8 M&3
- &Y
%V A. O-RELATED?
YES NO B. FOR NONCONTORMANCES, SE ONE:
USE-AS-IS REPAIR REWORK C. IDENTiry ArFECTED
.NCS/DESiCN DOCUMENTS IN BLOCK SC ABOVE.
D. IS 2E-31 R IRED' YES NO
- F YES. INillATE ZE-31 AND ATT ACH COPV. (rORWARD ORIGINAL TO DE SJGN ANGE COORDINATOR) INDiC ATE ON 2C-31 WHETHER ZE-31 RETURN 10 SERVICE IS REOuiRED f
E REQUIRED? WS NO
l M
e n
PCF NO.
308913-A PAGE 3 OF 3 ATTACHMENT TO PCF 308913-A TECHNICAL JUSTIFICATION:
Valve NIMTFV7902 was installed backwards (flow under the seat). Installation of the valve to the required flow directions (flow over the seat) as shown on vendor drawing 4449-00004-Lv restores the valve to the original design configuration.
This valve opens to permit condensate drainage to the main condenser from downstream of the MSR control valve.
This valve is designed to fail open on a loss of air.
This valve does not serve any safety function.
DISPOSITION:
REWORK:
l Install the valve into the system to the flow direction required in accordance with drawing 4449-00004-LV (flow over the seat).
If necessary, the valve can be rotated from vertical in accordance with specification 5A010PS002.
If the flow arrow on the valve is incorrect, based on the new i
installation configuration, buff off the old arrow and restamp or etch the arrow in the correct direction.
l l
l
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WSTRUCTl0NS FOR PART 1 COMPLEft0N CRpDMA104.
SCSOR$C 1r00R CONCERN OMNC AS NUCH N'ORMAh0N AS POS98LE. FEL M ALL APPUCA8LE SCCDONS OR ATTACH 90CutCw1AhCM. DIDeCAlt DNAT. DHCN. WHQ. WiY. WHERC MOW. UST ANY ALTERENCC$.
SCSCRSC ANY MetDAE COWPCNSATORY/RCMEDIAL ACh0N$ 1 AMEN M A00lDON 10 Wm1NC DC SPR.
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F A CO@0NENT. SYSTEW. DUILDHC. CTC 5 Ofv0 LED. DOI COMPLEE INE APPUCABLE PORDON Cr PART L F TOU NAiC (M0hM 9#0RMAh0N Td BDfffT 1HC CAUSC AND REMEDIAL ACDON.1HE SO STA1E.
j CS1AN taKDiATE SUPCRWISOR$ CON 00RACNCC F POS99tt. F NOT POSSOLE OR F WuoNATM DeSACREES W1H I
sa4 DIAR SUPERMSORS POSth0N. DCUWR To SW1 SUPERvtS04 OR CAO AS APPROPRA1E.
l POTENTnAhv RtPORTANA. OR F ANY 90Utf Rata 918 REGARDING REPORTA8UTY. HApe CARRY WOTk IeCNAMV TO TM SHFT SUPERV180R. OTNEREst. DEyvtR TO TE CAS RA OR, y Asrf secTt0N OR SLANx te NOT 00MPLttto, TMres Recono N/A N THE APPRepniATE SECT @et PART 2: REPORTABILITY i
A. PLANT WOOD (ORCLE OC) 1 234 5 8 NO-WCDC m, Po cR naitwP_
as PRCSSURE Rs 1RP 1ES [ ] W [ ]
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- 3. MABUTY
[ ] CPCRA8UTY REMCW RIOutRED WDeN 24 HOURS.
[ ] JC0 REOutRED
[ ]NA l
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- t. RCPORTADUTT DCTERuMADON PCR REPORTNG NANUAL l
[ ] StCPORIASLC PCR wTHN law /PERWIT/DCENSC IWDHOUR$
N0nnc4h0Ns (sS) l 24ffY PLANT WANAGER
[ ] W/A PDtSON CONTACTED DATE/fWE N DALS 95tC RCSCCNT NSP
[ ] N/d PCASON CONTAC1ED Daft /IWC DaTIALS
- SftC CPS CENTER
[ ] N/A PCA$0N CONTACTED DATE/TWC paftALS I
OTHER
[ ] N/A - PCR$0N CONTACTED DAX/tmit ScT4ALS
{ j AD0th0NAL RCPORTASUTY EVALUAMON REQUWLED e
[ ] NOT REPOR1A8LE snrt wecRus0R oAu/TWc
- 3. FNAL RCPORTA9UTY REMCW
! 3 RtPORiarJt PCs unaN law /PERWIT/DCCNSC SMDHOURS
{ )Q NOT REPOR1A8LE
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PART 3:
ACTION ASSIGNMENT ACTION ORCAM2Ah0N($)
AW b
I"TM Q
DCPARTWENT ACMON OUC DCPARfWINT.
Ach0N he N
DUC IICPAR7WINT ACMON DUE
( ) CONTNUATiON $NEti ATTAOCD 1
r m'"
w m
9 3 0 0 6 'l m_ A sr.n a,.
racc./._ ore PART 4:
EVENT DESCRIPTION
( ) coNimunwoN sntti AnacNco l
A. DCsC5hPDON -
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-5 EoC 0
e encatu tvtut coots PART 5:
SPR CAUSES AND GENERIC IMPLICATIONS t I CONTWVATCH $HCCI AUACMCD A. causcs I 3 * " """'" * ** ^" 'C"'
- s. cc tec wucanoNs g
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~
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930064
. ctv _o _.
PACC 2: or_5 PART 6:
REMEDIA1./ COMPENSATORY / CORRECTIVE ACTIONS A. Atucun/couPCNSATORy ACTO 4 COuPLETCO (DCYOND PART l.C) '
Sft-G yf c CA rr) s
{ ] CONTWUATtON SHC(T ATTACHED 3.. CORRICTiW ACTIONS E
c'
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( ) CONTWVATON SHCC t ATTACH (O PART 7:
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Page 3 of D Station Problem Report 930064 Various Drain Valves Installed Backwards PART 4:
EVENT DESCRIPTION ~
A.
Description A Mechanical Maintenance crew was installing a new replacement valve for N2MTFV7987, MSR 21S tube bundle drain, because of seat damage due to continuous leakage.
A question-arose about the proper orientation of the valve because the new valve had the flow arrow pointing in the opposite direction as compared to the cid valve.
A check of the design drawings revealed that the old valve had been installed incorrectly with a flow to open orientation.-
The new valve was installed properly.and passed its post-maintenance test.
A walkdown of like valves, Conval Y-type globe valves, revealed that all Unit 1 and 2 MSR tube bundle drains, Unit 1 and 2 extraction steam to high pressure feedwater heater drains, and Unit 1 only above seat main steam isolation valve drains are also installed backwards.
The valves listed below are known to be installed improperly.
NIMDLV7925 N1MTFV7962 N1MTFV7984 N1MTFV7900 N1MDLV7926 NIMTFV7977 N1MTFV7985 NIMTFV7901 N1MDLV7927 NIMTFV7979 N1MTFV7986 N1MTFV7902 NIMDLV7928 NIMTFV7981 NIMTFV7987 NIMTFV7903 N2MDLV7925 N2MTFV7962 N2MTFV7984 N2MDLV7926 N2MTFV7977 N2MTFV7985 -
N2MDLV7927 N2MTFV7979 N2MTFV7986 -
N2MDLV7928 N2MTFV7981 The affect of flow to open installation is that the pneumatic operators on these valves are not exerting enough closing force to prevent leakage.
Thermal Performance surveys show these valves to be continuous leakers.
The Conval valves take main steam from the HP turbine and could cause as much as 2 MWe loss per unit.
These valves contribute to main steam leakage problems during start up operations.
B.
Problem Event Code EA49 PART 6:
REMEDI AL/ COMPENSATORY / CORRECTIVE ACTIONS A.
Remedial / Compensatory Action Completed 1.
Valve NIMTFV7987 was repaired under SR MT-146929.
9
Page 4 of 5 2.
PED will evaluate the best method to repair the valves.
Possible repairs are 1) cut the valve out and install with i
proper orientation 2) install a larger operator 3) increase 1
the pressure on the actuator.
Repair will include inspection of the seats due to long term leakage.
PED will initiate required documentation to impicment the recommended fix.
Y i
This action will be completed by S/n,/93 g
)
G.
E. Schinzel _M [
gy o
v r
A 2
25/91, g
y'J/
l,
> ' * ~ *3 dv e 2
l'O C-24 A.7
Houston Lighting & Power Company OFFICE MEMOR ANDUM
~
yd AG Administrator Februa y 9, 1993 ST-HS 23385 D. A.
Leazar PFN Z2
- lu from r N'N'"
Reportability Review for SPR 930064 On January 5, 1993:a Thermal Performance Engineer discovered that several air operated Y-type Conval drain valves were installed backwards during construction.
Valve drawings indicate that the valves should be flow to close but were installed in a flow to open orientation.
With system operating pressure underneath the disc the pneumatic operator will not provide sufficient closing force causing the valves to. leak by continually.
There are 8 MSR tube bundle drains and 4 HP turbine extraction steam drains in each unit installed backwards.
The leakage past the seat on these valves is not reportable.
The Unit 1 above seat main steam isolation valve (MSIV) drains are also installed in the flow to open orientation.
.These valves TAGTPNS numbers are N1MTFV7900, 7901, 7902, and
.~
7903.
The Technical Specifications and 10CFR50 Regulations do not require NRC notification for leakage greater than design on theses drain valves.
The justification is that MSIV above seat drain valves are not safety related or containment isolation valves.
Nuclear Licensing 2/p/g -
MS cc:
C. A. Ayala N5010 K. J. Christian N2017 Unit 1 Control Room M1001 Unit 2 Control Room M1001 RMS Correspondence N2002 4
9)(\\
(,/4 1
SPR ACTION COMPLETION VERIFICATION FORM
- 1. SPR/
U C064 Action Item # (If Known): 81 e ad e a t. olkte
- 2. ACTION #(s) STATEMENT (s) a) A 2 - bval, be4 f % M oci Yo
_ P LP ett e Va I4f C ta cd u d ei t A t # t c.No e o b C CA b.
b) 0 N - E e J.
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s A
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p
- 3. TuE AnoVE ACTION MAS BEEN YERIFIED COMPLETE BY:
Attached
- Kee No a) Document (s) # _04 - I " [C.6 [7Y90E-N
[x]
- 4
'2. - Pc f / ? y ? 43 - A gxj g
( )
I1 II L3 11 II b) Describe
%m ma. d et+ k cA c a - PC F s e-uo - c.nd destas ch v C S.
U
- 4. DATE(s) COMPLETE:
N ['2- !9 3
~3 cih n @dkt
- 5. AUTHORI11HC $1CHATURE:
The undersigned have verified that the above action (s) have been coepleted as described. This coceplete form is subject to QA Audit and SH4LL be illed with the SPR file.
h l
DepartmentMpager(Required)
Date t
- VERIFICATION DOCUMENTS St%LL BE PROVIDED FOR NRC RELATED ISSUES
4 k
3/31/93 s
_fwetvf?p ( _ Attrov ts.g Scr.=CE DOC TJ_tt M SCt t et t0w Ett StarvS fut G.E. SCwturEL 03/15/93
- CU10AwCE to CwECT COVET #0e BESPO4SE TO EwSuet Att Att IS
{
- E W D Froe Twt GCvEtwot, f
e" c 03/17/93 9tott3/tte CX 004A) CO*LtitCM FOR TWE FotCEO Att PCRff04 0F 800 90021 TO LC 1 91 l
Estunt fut JC0 VfLL wof BE eEDuitED VwEw fut$ Poef!04 Or ?>E
-Ott
[
m IS uttDED TO EWSueE WrDeAM IC FlutD tufECetft.F,suev)
[
600 01/97/93 930064 C
- 2) EVALUATE twE BEST pef *00 70 ptPAtt fut Vat,vES VwtC4 ;
O CNANCEO Ft0* Vtw 70 f
ItCLLCES INSPECfl04 0F TWE SEAYS DUE TO LONG TEtw LEAEACE.
CES 3/31/93 L
IeIf f ATE WECUt'ED 00CUME4YAT10W TO !PPLEwt4i TME RECCPertwCED Ftz.
DDR 03/17/93 930064 CX EVAttJAtt fut stSt WETuc0 70 #EPAtt TwE VALVES. POSSIBLE O
REPAlt1 ARE 1) CUT TPE VALVE OJT A40 twSTAR VifN PROPER OttENTAf t04 2) tusfALL A LARCEt OPERATOR 3) !wCtEASE f rE PtE55U*E or f>E ACTUATOR. REPAf t VfLL thCLUDE 14SPECTION O'
~
TFE SEAYS DUE TO LONG TERS LEAICACE. PED VILL tufftATE Bt0UIRED DOCUMENTATION 70 twPLEMEuf fpE RECCPo'ENCED PtIS.
03/18/93 92*140 CX istitATE A Pu 70 RECAlletATE TNE MCPrtTOR Aw0 0 70 CAG 3/30/93
- EPLACE/tECAlt8 TATE TME Pt08E CONS!CEttuG TRE RECor*8EMOATIO4 0F THE VEw002 MANUAL.
C3 Obt 03/23/93 930377/LER 2-93-004 CX 006)-COMPLETE Amo ISSUE DEttcu FCm M00tFICAf tos FOR TPE O
STEAM Ot!vt W PUMP SMAFTS TO USE CWomE PLAftwC.
ODP 03/23/93 930377/LER 2-93-004 CX 007) ISSUE SRS FOR M00tFICAf!CM or fpE STEAM OttvEW 0
FEEDVnTER PeseP SMAffs 70 USE CNROME PLAf teC.
,c Mr 03/23/93 930377/tte 2-93-004 Cx 014) CO*PLETE A40 ISSUE DEttCN FOR MCX)tFICAf!C4f CF TNE O
$T4tTUP FEEDVATtt Pupp SEALS 70 tNSTALL A DEIGN fMAf PtECLtOES VATER INTRUtt04 A00ttt04ALLT, TME COALESCtkG FILTRAf t04 DEttC4 VILL SE CnANCED TO PLACE frE FILitATION ELEMEuf tu A PARAREL LOW PATM SUCN TMAT CLOCCEO FILTEtt VILL 407 CAUSE A PtP* TRIP.
w.
%G 03/23/93 930377/LER 2-93-004 CX 0151 ISSUE SRS FOR >00tFICAft04 0F INE STARTUp FEECVATER 0
PUMP SEALS TO INSTALL A DESIC4 TRAT PRECLUDES VATEP I47tUSION. AD0ff!CMAtti, THE COALEstis C FILTER DEstCs VILL 8E CNANCED TO PLACE TME FILitATION ELEwtwit 14 A PARALLEL
- LOW PATM SUC# TNAT CLOGCED FILTEt$ VILL NOT CAUSE A Ptpp falp.
03/30/93 921453 CX 003) As EVALUAft04 08 TME SOC DEstCu v!LL tt PERFotmED TO O 70 CAC 3/30/93 IDENTIFY Of!8Et COMPowtuTS 04 LOCAf!Ot3 wot CtittEsfLT BEttG LUBRICATED V4tCM MAY VAttANT LU9t!CAft04 T
03/31/93 930431/LER 1 93-007 LC 001) TEsttuc UttL BE CON 00CTED PRIOR 70 DECLAttwG 70AFVP 24 0 TO CAc Ext. 70 5/5/93 OPERASLE. TESf!NC WILL INCLUDE: VERIFICAf tce CF f>E CatAls De9e 2
PACT I Oc SOJTH TEXAS PROKCT CLICTAsc CCNERATsNC STAT #ON PLANT CHANGE FORM I74 7 0 2,- A STP 3226A (o5/92) rcr uvu3c SPcsm uzA-OQ90
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SC. ArTIC1ED DC5aCN DOCUuCN DOCUMENT WUvDER RCV.
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RCPAIR [0ViVAL(N1 CHANCC (R(0)
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DCWLOPutNT AUTHOR 12 A1 ON (f 0R D(N(flCIAL CHANCES OrdLV).
/
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. W AIN TEN ANtt M AN AC(R DATE OC$'CN (NC8N(( RING M AN AC(R D A T[
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- E BENEFICIAL CHANGE TO SELECTED DRAIN VALVES
- 1. PROBLEM / CONDITION:
Below listed valves are installed contrary to design.
Data Sheets indicate valves are " flow to close", but they are installed the other way around.
Additionally, the original design data seems to be invalid, so that even if the valves were turned around,the actuators would be improperly sized.
- 2. TAG /TPNS: N1MDLV7925, 7926, '/927, 7928; N1MTFV7962, 7977, 7979, 7981, 7984, 7985, 7986, 7987; N1MTFV7900, 7901, 7902,- 7903
- 3. RECOMMENDED ACTION:
For valves H1HDLV7925-7928 (HP Turbine to l
HPFWH Extraction Line Drains) recommend changing the actuator l
spring from size-1F1771 to 1E8049, and leaving the valves as is.
For valves N1MTFV7962-7987 (HSR Tube Bundle Drains) recommend l
turning valves around and changing spring from size 1E8057 to 1E8051.
Leaving the valves in their current configuration would require changing actuator size.
For valvec N1MTFV7900-7903 (Above Seat Drain Line Level valves), recommend changing spring size from 1F1773 to 1E8266, and l
1eaving the valves as is.
See attached for more information.
Recommend continuing to use conval valves in this application, as the valve performance has been very good, considering the design inadequacies.
Even if the valves were to be "use-as-is", the paperwork associated with these valves must be updated to show the correct information.
W vs.-
A r, c~.a..t.a:.
r.,p, a.s, m
,,iu an be It\\st e c t sA e s ol re g s;t e A as assessary,
f s i.a tv I IsTP J2NA (05/D2)
SOUTH TCKAS PROKCT CU:CIR8C GCNCRAING STA1:0N 3~A PLANT CHANGE FORM OPCPO>-2 A-DO90 PCr NuwotR pget g o,. 3 N-SC. ATTECTED DC580H DOCUuCNTS DOCUWCHT NUMDCR REV.
KEY 7 OOCUu[NT NUMBER REV.
KCT7 1
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.J /4 N
SWJ
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UNil.
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PART DCSCRIP1 TON
- 3. RECOuuCNOCO ACitON.
b C bM tl VAkVCF A. n S ke C $
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- e Mc wWYar a us.e n Hac.J as o u '<f4 met 0
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N twiTIATED BY. -
DATC-
- 4. PLAN 1 CHANCE TWC-l hCNCourCMANCE (NCR)
FLPAIR LOUT #LCN1 CHANCC (RCO) -
DCNCflCLAL CHANCC (ATTACH CCONOuiC [vALUAllOH)
DCKLOPMCNT AUTHORt2 ATION (rOR BENCf8Cl#1 CHANCCS ONLY).
/
/
. MANTEN ANCE W AN ACCR DATE DC58CN [NCIN(( RING W ANAC(R DATC S Dr5PossisON/II,CHNICAL JJ5 fir: CAT:0N.
A Q-nCL A1001 YE5 NO-8 FOR NONcoNrORu ANCCS, S(LCC1 ONC-USC-AS-IS -
RCPAiR RLwok C IDCNiery ArfCCICD DR AWINCS/D(SiCN DOCUM[NIS IN BLOCt. M. ADO 4 0 f5 ZC-38 RCousRCD' YC5 NO er YC5. esillA TC 2C-3i Ar4D At t ACH COm (roawaRo OciCs44. 10 DC9CN CHANCC COO 5 tom A10R) sNDeC All ON 20- 38 NtC1HCR 2C-38 RC1 URN IQ SCRVICC 15 R(OU'RCO C RPL RCOJRCD' YES
- D -
PCF 174763-A BENEFICIAL CHANGE TO SELECTED DRAIN VALVES I
- 1. PROBLEM / CONDITION:
Below listed valves are installed contrary to design.
Data Sheets indicate valves are " flow to close", but they are installed the other way around.
Additionally, the original design data seems. to be invalid, so that even if the valves were turned,around the actuators would be inproperly sized.
- 2. TAC /TPNS: N2MDLV7925, 7926, 7927, 7928; N2MTFV7962, 7977, 7979, 7981, 7984, 7985, 7986, 7987 3.
RECOMMENDED ACTION:
For. valves N2MDLV7925-7928 (HP Turbine to HPFWH. Extraction Line Drains) recommend changing the actuator spring from size 1F1771 to 1E8049, and leaving the valves as is.
For valves N2MTFV7962-7987 (MSR Tube Bundle Drains) recommend turning valves around and changing spring from size 1E8057 to 1E8051.
Leaving the valves in their current configuration would require changing actuator size.
See attached for more information.
Recommend continuing to.
use conval valves in this application, as the valve performance has been very good, considering.the design inadequacies.
Even if the valves were to be "use-as-is, the paperwork associated a
with these valves must be updated to show the correct information.
M Mca 4(e re e.m m ed e /
ac4 tens are i,f mwied,
M.
v.id s.
4s
.,ill le f
kspefed ast reg a;e ed as cecess.r7
PORC Review Evaluation SPR fjpoly Subject _
Does the subject SPR meet any of the following criteria:
XES
.N.LQ 1)
Concerns a REPORTABLE EVENT?
/
2)
Concerns a significant operating abnormatity or sinnificant deviation from normal and expected performance of ptant equipment or systems that
/
_affecLn_uchar safety?.
3)
Concerr's unanticipated deficiencies in the,Gnigg or i
.ppfdation of structures, systems, or components that affect nuclear saferv?
/
4)
Concerns any accidental, unplanned, or uncontrotted
/
radioactive release?
5)
Concerns the violation of:
- Codes
- Regulations
- Orders
- Technical Specifications
- Operating Licensing Requirements having n_uclear safety significance?
6)
Concem the abnormal degradation of systems designed to contein radioactive material?
/
7)
Should be otherwise reviewed by PORC?
[
Explain:
I 1
If any of the above questions are answered YES, THEN the subject SPR SHALL be submitted t P C.
as F 3
.1 rw
/
bate fv'aluator
12/16 '04 '2:44 IDiPJJCLEAR' LICEPSINC
~ FAX:6i2-072-8208
' PACE 3
STPtes#AOMfD3)
EOU1H TEXA8 PROJECT ELECTpWC OtENEMllNG til AllON h
,//
REVS PLANT CHANGE FOlW
/MF/t/b1P/-A (Page s orl) l%93Y~ 0 WOnM DOC. Ps0 POP NthuskM 1.
Pro 6sarnroanennon 1 Al.Ud All ArrCn/1972 /$ Ca$rkuth ho+cdsJNt.bs, SDLJ L$ f rAvi/ZLE) _7D f$L _bt/d TifL t
SrAT.
2.
TAQrrPNS: //2M 177 system:
/>f T Una Priomy_
A 3
ComponenWPwt Description ST"fAc4 TD A5A '24,/ Ih,/_.
3.
Hecomrwndoc Acten:
04)T
- W A+lb __ h T% %C. VM Fat insani. De*e o,f'_ Date: 3-lMV Poone FL C Innleted ty; k Mud.A44 I Pritu
/
M, ~, /-
PCF Aeoepsed ty T4G Engheer Namep w
d.
D:spontinrvneScri, vion of Change:
b C(
W f. $ TTA'L44L.b h t$f)O$lTIO J
- TW5 PcF suptastxs
/ce's /w,934-A ut> 2rzos; A STl-94-007485 2E41 EVAL REO'JiHkD? YES O NOW DISPO8frlON: WTERW D FINAL 3 0 4ELATEO: YES O NO 9 VFOR WTERN, ATTACH PCF NTEAN 00.69 EVAL (AVION FORMJ 5049 kVAL. REQUIRED 7 YES S NO D (If no,ident#y the seesces)
NO. OF AMENDMENTS O
y,[,, _
9[
A NON CONFORMANCE:
D. PA5'dM CNAVJti O
M
~
USfi AS 1.9 O
C REPLACE E0V! VALENT O NC - FR nATE ntPAtti O
n REN(?hCIAL CHANGE D 4I44 M Y
nEwoak in
- t. iNvAvoA1c n
D TC e
3 y
CNGWGER Supt DA10
=.
12 1604'12i44
~ ID NUCLE M LICEN91NC
~
FAX:512-072-8008 PACE 4
ATTACHMENT PCF 146934-B March 16,1994 FAGE 247.3 BLOCK 4 DISPOSITIONI TECFENIC4L RJS11FKA110N REWORK DISPQ$f110N:
This disporldon sh00 sqpersede PCF's 1469344 & 212051-A in their entirety. The scope of this PCFis to cut and rotate wlw N2M1FVM77. Thk subject valw was installed backwards (flow under the seat). Install the subject valve udth theflow over ne seat. Urequired, gind theflow arrow off the valve body usirg cent not to tr\\frirge on the minimum wall Alckness, and reirutall thepow armw in the correct direcdon.
TECHNICALlllS11 FICA 110N:
This dkpotirion will enhance the cperational charnetoriedas of the vahw. The valw is non-quality amt non safety and this disposiden was discussed udth B. Ratte'ofPED. Thh does not lapact or affect the FS4R or ikchnloal Spet41cellora anudated wkh hk system. This door not affect the ability of the corrponent to puform its intende!funcdon, nor does it entall any emeriments or tests not previously reviewed in the FSAR.11dt charge does not toduce the marg!n to safety of this component nor will it require charges to hchnical Specylcadons orthe FSAR.
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12 6 'O 12 5 IhWCLEAR LICEElm Fb512-072-9209 m
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' ecullt ilAA$ MtodOG4 sAACles; 4XpetAAleNC STA1:0N A33AQ@fii-dog.2-l 10CFR50.59 8CREENING FORM y.343 tivPacau e m i or j 4
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PREUMINARY SCREENING vcs no 1.* Does tho' proposed 6honge represent e chenee le the Plant Teahnloat Spectnoolicast O.W t
en a
red er to I.t f.
H *Yes' refer le IP-l.190. f'oriher sorvening is not requifsd.
Does the proposed ehenge represent
,YCEi.
- HO
'3. A chonge to aerrect e typographloot edit di er or desfilag error?
O Y
4, A watch.ar identeeol to end ^^' -" In les ' ntirety by o.
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a0 *pProwd 800ftt5o.69.ScreenId[U3i4ft
- s. gs. emgeh e.e ter..,.r sea.h d m o
av (see N ier bien of egdvoledt) '
+t It all errowers.fe'the obew quesliens ete "No" perform the final screenlag esed mark N/A in the opproret blocks below.
If the easwer to ony question (3)d pages 2(8) le "Vas* e finot moreening l: not.necessory thrwegh approval blocks befow and discor thru 4.
. Sign Prodde en emplenellen/lvdif;oort.n,ad references if ony of items (5) through (6) are onswered 7Yes*.
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4 Propored by:-
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12 16 '04 12:46 ID:NLICLEAR LICENSINC FAX:512-072-8209 r%CE P
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PACC k Of r,te suco (os/n) sovts rcxAs ea0;cCt Ettctmt ccatRAtenc staleoN h gg etv 0 I
d PLANT CHANGE FORM F" "V"dt" OPoe03-2A-0090 PACC 2 or y esotc; Pant e es neof Rrovtato con newong perostis0Hs scon roa s[NfraCtAL HANGkg TW6GH V$( 9800PICATION PACKACES.
6 PCT SC8t[(NtNC OU[5fs0N$ (if ANT ARC *TC *, lHC PCF CANNOT DC AUTHOR 1ZCD FOR IMPLFM[NTATION A$ A NONCONr0RuANCC Dr$PQ$ttlGN QM R(PAIR I VALENT CHANM. UNDLR 7A SLLOW);
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Out$tiONS C, D. E, a r MAY BE ouiTTED sr IP-3 200-2 IS PREPARED MD ATTACHED, OR ar 1HE CHANCC IS 80CNitCAL TD AND ADDRC55CD N ITS ENT;RCTY BY AN CEISTING APPROVCD 10CrR50.59 SCRCENINC/U$0C (PROMDC RCr:_
).
NO p CHANGE INv0LVE A >tANCE TC f Cdl1Y AS OCSCR;DCD IN THE SArCly ANALY5t$ RCPCRT ($M)?
C. Dots THE PROPCs YE $ -
I D DOC 5 f*C PROP 05t0 CHANOC thv0LVE A CHANCC TO THC PROCCDURCS AS DCSCRIEED IN THE $AR7 YLS _ NOI J C DOCS TH: CHANGE PROPO$t THC CONDUC OF TC515 OR [XPCRsuCN1$ NOT DCSCR10E0 IN THC $ arf YC5 NO I f.
Don 1HL PHOP05tD CHANGE AirtCT CO#4D:1#0NS OR BAS [$ A55VutD IN TrtC SAr(TY AN ALYS$ REPORT OR SartTv-RCLATIO FUNC160NS or toJiPMENT/5Y31EuS. [vCN THOUCH THE PROP 0500 CHANCC DOCS NOT ENTAlt ANY P YSICAL CHANCF IN [rlShkG $1RUCIUPES. Sv$ffu$. OR PPOCCfoRC$ AS DESCRiDC0 sN 1HC SAR? vis -
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/.suvLtutNI A sCW APPROVAL; DCstCNATE APPROVAL CL ASSar: CATION (CHECK CNEL
_A TH:5 '5 A N(NCUNf GHM ANCL D5POSill".r4 OR A REPA!R COUVALENT CH ANCE AFPROVED TOR IMPLEM[NTATION AND RETURN TO SCRVICC.
l (PLANNERS - F.[FtR TO ATT ACHED ZE-31 FOR ANY SPCO AL POST-M0011 CAT 40N TEST REQU Rtu[NTS. At D 10
$tt er 2C-31 RETURN 10 SCErVCC 15 R10#CD)
I t TitiS 45 A NONeoNroRu ANCE wHifH RC0 VIRES DETArtto [NCtNCCRfNC (VALUAllON. AND 15 NOT AUTHORIZED FOR suPL(wCNTAT80N I
(T6P055h0N AND A550Ca At[D APPROVALS WLL OC PROVIDC0 VI A PCr. PART lf - CNIER *N/A* AND IN h At/OA1L 1+4L $ LOC.t 7 C.GNATunC CCLov) (PART I: Of PCr 15 IN OPCP03-2A-0603)
C TH:515 A NONCorJORw ANCC Dr$ POSIT 40N OR A RrPAirt r(xnvALCut cesawCc APPn04o roR suPotutN1Afiert AT Ri$st IDLNIP V OPLRABfL11Y RESIRA!NTS l
_ D TH S I$ A BEN [f4CIAL CHANC( 10 9( iuP tu!NTED WTHOUT A u00iF#CAft0N PACKAC[.
L (PCr PART 11 MUST DC CCwP CIED AND ATTACHED ALONC W1H OTH[R ATI ACHuCNTS REOutRCD PIR PCr PAR 1 st.
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t tecS 15 A DCNtr:CiAL CHANCI To O!! suPLtu!NTED MA 9005 C ATION PACK Act.
(u00eriCAll0N PACKACC NO
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I (tuPL(MINTATi0N APPROVALS NLL SE AUTHOR 12E0 V A THC MODirlCAft0N PACKACF AND NDT VA THrt Prf -
tNitR *n/A* AND INihAL/D ATE THL. BLOCK 7 5'CNA DELOW).
TICisN' CAL Lune'04 LNGINEE DATL I '
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12/26 '04 12:47 TMAI#t LICENSINC FA6512-072-8209 TWCE e
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i Per 146934-A, i
Page 3 of /'fp I
of5A YN t
- 5. DISPOSITION /TECHNICA!, JUSTIFICATION i
valve N2MTFV7977 which was removed from the fleid because the seat is le'aking and the replacement valve taken from.
the warehouse l for Instanation in the field, have flow '
directional arrows nisaatched. The removed valve has flow arrow indicating that the flow comes under the valve seat. The ned valve has flow arrow indicating that the flow goes over the valve seat. The vendor drawing, 8449-ooco2-DLV, iridioatos that the flow is over the valve seat. This valve is an air operated globe-wye type valve.
l The valve fun tions to. permit condensate drainage to the j
stain condense from downstream of the MSR control valve.
l It is designe$ to fail open on a loss of air. This valve does not serve safety function.
1 The valve va purchased in accordance with the control valve data sh4et, which indicates that the valve requires the flow to 'close the valve (over the seat). Vendor drawing 4449/8449-00002 LV Rev. D shows that the flow
]
direction arrow.is over the valve seat. Vendor submittal,
)
A " does not! indicate a flow direction. Submittal "B"
indicated a f3ow direction under the seat, but Bechtel '
comment, based on the data sheet, changes the flow to over the seat.
i There are sikteen (16) valves installed in the plant which are identical to N2HTFV7977. All these valves are installed wit'h the flow direction under the valve seat. ;
Tne vendor drawing and the piping isometric drawings do '
not agree with the valves' installation orientation.
l i
Per discussio'n with Paul Moricy of Conval Inc. (203-763-3S51 ext.220)' Mr. Mosley said that in most application,
of this typej,of valve, the pressure is under the seat when the valve is closed and the flow comes under the seat. Ile said that this valve can also be used with flow going ever the seat, but such application requires careful consilderetion. According to Mr. Mosley the change performed on the reverse flow was per Bechtel request during construction time, however he cannot locate such request.
In the present installation orientation the down stream :
pressureiscondenservacuum(3.6psiaperdatasheet).l Tnis orientation mininj zos steam leak problem coming.
through the valve packing howover air may leak to the' main condensar through a weak valvo pack 5ng.
/
1946 '04 12:48 ID: NUCLEAR LICENSINC FAX:512-072-0209 PACE O
I e
PCP 149634-A Pago 4 of t3w39' i
The drawingo show that the down stream pressure is main steam pressuro which has a decign precsure of 1285 psig.
If these valvbo havo to be re-oriented per the drawings, the valve packing will constantly bo subjected to.this high pressure and the air preocure to the actuator has to be re-analyse,1 to account for the pressure drop.
Ray Richkrdson of Hochanical Maintenance, one of Por theco type ofivalve (N2MTrV79s?) has been installed with theflowoverjtheseat.Thisvalvewasreplacedbecause the system prpseure under the seat had caused the valve to open and allow steam to damage the seat.
Valvo N2MTFV7977 wac disassembled and inspected to determino wha't was been causing the valve.to leak. The inopection fobnd that there was no damago to the seat or diso. No othe;r reasons for the leakage were found.
Review of the SR's issued for the Unit P identical valves, indicates that all of the valvam lank by the sent and require repair.
DISPOSITION: USE-AS-IS i
Install the!replaeoreent valve (N2MTTV7977) to the orientation where design flow direction is under the seat. This valve was originally designed to flow under the seat. Tho!roversal of flow diroetion was not properly addressed.
l All the affebted drawings and data sheets have to be revised to erflree with tha an-bttilt configuration.
Theflowdire:ctionnajkingsonall1-1/2"convAlVA1Ven purchased under class bin 501-25075 have to be grounded and remarked to show the flow direction under the seat.
(see Note 1)I Valve N2MTFV7,967 has to be removed and re-oriented. (see Note 2)
DF.n to ravinw tha instrocent and Valve Data Rheats en i
confirm tha spaci find closing air prannura for the valve operators is attained.
Note la Thf scope of thir. package shall be extended to include the two steps abovn.
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12<',6 '04 12:46
!D:NtX1Efdt LICENSItC FAX:512 'R2-8000 m
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12/16 '04 12:40 1Dit#JCLEAR LICENSINC FAX:512-072-8008 PACE 11
,4 2n.f n69sh j EEEP_QNEER_ID_SARGENT AND LUNDY COMMENTS _ h (,/ [,[ g Rh.CdAGE 9.014A l
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D rt 1 of 1 mart i
t PCF 146934A i
This is additional infoxmation that has been requested on '
the final dis' position of this PCr.
j The earlier rpl sponse, PKG 014, Part 1 of 3, had a note in i it stating that the PCF had been revised, yet no. revision,
could be fourid.
i l
i A review of the documentation trail revealed that this PCF had been voided and supet meded by PCF 212051A on 9/9/93.
This concernIls therefore closed.
I I
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Pear >onsen app!
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SOVfH tex AS PROJCC1 ELECTRIC CENER ATING ST AllON hg f/
N NA PLANT CHANGE FORM OPGPO3-2 A- 0090 PACE 1 or 2 PCr NUuBER SC (Jf(CTED D[SICN DOCvvCNTS ECCuvEul NUvDER R E V.
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BENEriCIAL CHANGE (ATTACH ECONOMIC EVALUAflON)
COILE**vCN1 AU1hD4 ? AliDN, OR Btr.Di;i AL CH ANCES ONEy)
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-k D it toiCONTORv4N:ES. SELECT ONE USE-AS-IS REPAtR RE WORK C JENis y Aff LCTED DRu/NCS/DESiCN DOCUMENIS IN BLOCK SC ABOVE IS 2f-31 REOU' RED
- YES NO /
tr yEs, IN;TIATE ZE-31 AND ATTACH CCPy. (rORWARD ORiciN AL TO DES:0N CH A*iCC CDDcD N ATM) IND'C ATE ON 2E-31 WETHER 2E-31 RETURN TO SERVICC 15 REOutRED E Tr'; "E-r7 7_
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SOUTH TEXAS PROJECT ELECTRIC GENER ATING STATION
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PLANT CHANGE FORM WNb OPGP03-2 A-0090 1
PACE 2 Or 2 FCF NUuBER NOTE: PART 4 IS 8801 REOUIRED FOR REWORK DISPOstTIONS stOR FOR BENEFICIAL CHANCES Wr8CH USE MODfflCATION PACKACES f, PCF SCREEN:NG OUESTsONS (or ANY ARE "YES" THE PCF CANNOT BE AUTHORIZED FOR luPLEuENT ATION AS A NONCONTORMANCE DtSPO9 TION OR REPA1R EpVALENT CHANGC UNDER 7A BELOW);
A, DX S THE SCOPE OF TH:S CHANGE EXCEED THE LfupTIONS FOR A REPA!R EOUIVALENT CHANGE AS DEFINED IN OPCP03-2 A-0103. ADDENDUu 5? WS NO B. DOES THE CHANGE REPRESENT OR REQU4RE A CHANGE TO PLANT TECHNICAL SPECsFICATsONS? YES N O _V OVEST ONS C. D. E. & F WAY BE OuiTTED IF IP-3.2OO-2 IS PREPARED AND ATTACHED OR IF THE CHANGE IS IDENTICAL TO AND ADDRESSED N ITS ENTIRETY BY AN ExlSTING APPROVED 10CFR50.59 SCREENING /USOC (PROVIDE REF:
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C. DOES THE PROPOpS CHANGE INVOLVE A CHANGC TO FACfLITY AS DESCRIBED IN THE SAFETY ANALYSr5 REPORT (SAR)?
YIS NO l
D DC{S THE PROPOSED CHANGE NVOLVE A CHANGE TO THE PROCEDURES AS DESCRIBED IN THE SAR? YES NO. /
E DOES THE CH ANCE PROPOSE THE CONDUCT Or TESTS OR ExPERiuENTS NOT DESCR18ED IN THE SAR? YES NO V l
F. DOES THE PRocOSED CHANGE ArrECT CONDITIONS OR B ASES ASSUuCO IN THE SAFETY ANALYSTS REPORT OR S RELATED FUNCTIONS Or EQUIPuCNT/SYSTEuS. [WN THOUCH THE PROPOSCO CHANGE DOES NOT ENTAIL ANY PHYSICAL CHAN",E IN [KISTING STRUCTURES. SYSTEuS. OR PROCEDURES AS DESCRtBED IN THE SAR? YES NO f
- 7. ruPLE utNTATION APPROVAL; DESfCNATE APPROVAL CL A59rtC ATION (CHECK ONE):
/ A.
TH:S IS A NONCCMORMANCE DISPO9 TION OR A REPAIR EOU4 VALENT CHANGE AFPROVED FOR suPLEuCNTATION AND PUURN TO SERVCE.
(P ANNERS - REFER TO ATT ACHED ZE-31 FOR ANY SPECIAL POST-MODirlCATION TEST REOUIREuCNTS AND TO L
SEE er 20-31 RETURN TO SERMCE IS RLOUiRED)
B wc5 iS A NONCONrORu ANCE WHICH REOViRES DETAILED ENGINEERING EVALUATION. AND IS NOT AUTHORIZED FOR
- LEWINTATiON.
(th!POSITICN A ND ASSOCI ATED APPROVALS WLL DE PROVDED VI A PCr, PART It - ENTER *N/A* AND I4T4At /DA TE 1HE D;OCK 7 9GN ATURE BELOW) (PART ll OF PCF 15 IN OPOPO3-2A-Ot03)
C TH:S 15 A NorcCMOPur.NCE DISPOSITION OR A REPAIR EOutVALENT CHANGE APPROVED FOR IMPLEutNTAT'ON A T tv EDENTir Y OPER AB'tiTY R[$TR AINTS D TH:S l$ A DENEflCIAL CHANGE TO DE tuPLEuENTED NTHOUT A uCDirlCATION PACKAGE.
(PCF PART 11 MUST BE CCwDLETED AND ATTACHED ALONG w!TH OTHER ATTACHuCNTS REOutRED PER PCF PART II.
PART 5 Dr PCF 15 IN OPGPO3-2 A-0103)
E THIS 15 A DCNErsCIAL CHANGE TO DE suPLEMENTED VIA uODiriCATION PACKAGE.
(uoO4raCATION PACK ACE NO
)
(wPLEu NTATION APPROVALS WLL BE AUTHORIZED M A THE WODiriCAT40N PACK AGE AND NOT VIA THIS PCr -
thTT,R *N/A* A.ND INITIAL /D ATE THE BLOCK 7 SIGNA BELOW)
TECHNICAL SUPPORT ENOINEE b Id DATE T'
ie
\\
(FEA APPROVAL CL ASSir CATIONS A & C. FORbARD COPY Or PCF AND SR TO ENGINEERnNC; ORICINAL TO REuA!N WTH wpRK PACAACE: FOR APPROVAL CL AS$ar#C ATIONS D. E. & T. FORWARD ORIGtNAL PCF TO ENGINEERING WIIM SR COPT)
EDIE: THE FOL10WNC ST[p CHALt. t'E COMPLffED AT THE DIRECTION OF THE WORK SUPERVISOR AFTER WORK
%4PLEMENTATION PRIOR TO RETURN OF WORK PACKAGE TO WORK START AUTHORITY.
8 fr DRAWNCS/DCS GM DOCUu!NTS ARE ArFECTED (SEE BLOCK SC) FORWARD COPY TO THE TSE FOR FORWARDING 10 DCOUuENT CONTROL UPON CCuPLETiON Or THE WORK FOR ISSUANCE AS A DE9CN CHANCE DOCUMENT. ALSO, PL ACE i
A CCoy fN PCr DON IN THE CO%TRO; ROOV Cr Tt+C prrECYtD UN!T(S) m.
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PCF 146934-j Page 3 of j
6f D 3/.W 5.
DISPOSITION / TECHNICAL JUSTIFICATION valve N2MTFV7977 which was removed from the field because the seat is le'aking, and the replacement valve taken from the warehouse; for installation in the field, have flow directional arrows mismatched. The removed valve has flow arrow indicating that the flow comes under the valve seat. The new valve has flow arrow indicating that the flow goes over the valve seat. The vendor drawing, 8449-00002-DLV, indicates that the flow ic over the valve seat. This valve is an air operated globe-wye type valve.
The valve functions to permit condensate drainage to the main condenser from downstream of the MSR control valve.
It is designed to fail open on a locs of air. This valve does not serve safety function.
The valve was purchased in accordance with the control valve data sheet, which indicates that the valve requires the flow to close the valve (over the seat). Vendor drawing 4449/8449-00002 LV Rev. D shows that the flow direction arrow is over the valve seat. Vendor submittal "A"
does not. indicate a flow direction. Submittal "B"
indicated a flow direction under the seat, but Bechtel comment, based on the data sheet, changes the flow to over the seat.
There are sixteen (16) valves installed in the plant which are identical to N2MTFV7977. All these valves are installed with the flow direction under the valve seat.
The vendor drawing and the piping isometric drawings do r.o t agree wn.h tne valves' installation orientation.
Per discussion with Paul Mosley of Conval Inc. (203-763-3551 ext.220), Mr. Mosley said that in most application of this type'of valve, the pressure is under the seat '
when the valve is closed and the flow comes under the seat. He said that this valve can also be used with flow going over the seat, but such application requires careful consideration. According to Mr. Mosley the change performed onlthe reverse flow was per Bechtel request during construction time, however he cannot locate such
~
request.
1 i
i In the present installation orientation the.down stream !
pressure is condenser vacuum (3.6 psia per data sheet). !
This orientation minimizes steam leak problem coming' through the valve packing however air may leak to the, main condenser through a weak valve packing.
- 1.. :
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IDENTIFICATION OF CONCERN r
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SupC asSTRUCTIONS FOR PART 1 COMPLETION I
DESCRWE TOUR CONCERN C'VNC A5 WUCH NrORWADON A5 POSSIBLE.
r LL W ALL APPLICABLE SECTIONS OR AT"ACH DOCUWENTADON.
NDCATE WHAT. WHEN. WHO. WHY. WHERE, HOW. UST ANY REFDtENCES.
DESOtlBC ALL WWEDtATE GOWPENSATORY/ttEWC0tAL ACTIONS TAKEN WOTE: E POTENTIALLY REPORTAGLE. OR F ANY DOUST EKISTS RECARDING REP 0ftf A31LITY.135 DELfVER mee4EDIATELY TO THE SMFT SUPERet0R. OTHERWISE. DELIVER 70 TME CAS ADessusTRATOEL A
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.[ ] W1HM 24 HOLft$
[ ] OTER (les Comments)
W1HM I
[ ] REPORTABLE PER -
TwE:NOUR5 law IT/utINE tJ
[ ] REPORTABUTY EVIEW REQUIRED [
NOT REPORTABLE
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(
N/A PER$oN CONTACTED _
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ACTlONS TO BE COMPLETED
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SOUTH TEXAS i-ROJECT ELECIRIC CENERATING STATION OPCP03.zx.0002 STATION PROBLEM REPORT ma n
,n
-,,w# Gift 11L_L cAo CAxc0RY Oi On Os OA Os Os sPR uo.
PART 1:
IDENTIFICATION OF CONCERN n AuE - J T9 AT o s B R I oE,E _ ef/2 A. UNIT i Oi 0 C0=uoN
=2A7E02 3:
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DISCOVERY: DATE 2-5I4 nug
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luuEDATE $UPERytSOR:
8 DATE tug
$1CNATURC (NOT RE0'J.RE0) couuCNTs Sei n 7%4ed PiF Pc f Coff A% led PicTu e3 *TRdd G ud Mos/en e den SW a c. 315 40 % Ect>i A1%cf ad B.
PROBLEu DESCRJPT10N OR dt&L ERsdqe w4 e e Is alps os f-R yowiwa.
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A CouPONtNT u0. _TClb2, NCP2clA etoc_RC O R00u _ e C o /
INSTRUCTIONS FCR PART 1 COMPLETION DESCREE YOUR CONCERN QVNC AS MUCH Nr0RMATION AS POS$$LE.
rtLL IN Att APPLICABLE SECTION$ OR ATTACH DOCUMENTADON.
ND4CATE WHAT. VMEN. WHO WHY. WHERE HOW. LIST ANY REFERENCES.
DESCROC ALL IWuEDATE COMPENSATORY / REMEDIAL ACTIONS TAKEN N0ft IE P3TruT1ALtv REPORTAsLE. OR IF ANY DOUtf EXISTS RECARDeNC REPORTA41LtTY. It1EH Otttytt IMMEDIATELY To THE SNWT sVPERvison. cTHERWISE. DCLivtR TO THE CAC ADMINtSTRATOR.
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)
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CAc RECcvCo DATE /1Af Tw:07/b 7
PART 3: ACTION ASSIGNMENT EVENT CODESEN2'F.L OMsW M M*.
DEPARTWENT ACDON OVE o
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DEPARTWENT ACDON DUE t
PART 4: ACTIONS TO BE COMPLETED IReme**VCasea*atwr (R) or
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y PRIOR 11Y DUE DATE APP. AUTHORITY DATE 04 i
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PRiomTY DVE DATE APP. AUTHoltsff DATE.
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i gu CAE 5/6 CLOSURE
( ) CON 1NWAh0N SHEET ATTACHED CAC OATE l
1.
Event
Description:
At 1430 on February 2,1994 while Ebasco was using the Unit 2 Polar Crane to repair nisted welds on the Polar Crane support beams (SR JC-212836), the orbital bridge angle iron which supports the power cables from the busbars contacted a stationary busbar support clip (power rail clip) and broke it. The Orbital Bridge was connected to the Polar Crane when the event occurred. The Polar Crane was at azimuth 185*. Service Request JC-315406 was initiated by Electrical Maintenance on February 3,1994 to replace the broken power rail clip. This Station Problem Report, (SPR) 9G252 was originated by Ebasco on Febniary 2,1994 to document the broken power rail clip and to identify that l
contact may also have occurred at other locations. It was obs:rved that applying the brakes on the Polar Crane caused sudden stops and jarred the Polar Crane and Orbital Bridge.
At 1930 on February 5,1994, while performing Service Request JC-315406, Electrical Maintenance discovered the following as-found conditions between azimuth 170* and 270*:
1.
The orbital wheels were almost running off the rail, the only thing keeping them on track was the safety stops; 2)
The cantilevered tube steel support for the collector arm was rubbing on the end of the flat bar supports, busbar insulators and jumper cables; i
3)
There was a broken power rail clip. Electrical Maintenance personnel successfully j
replaced the broken power rail clip at azimuth 245*. The Polar Crane (and Orbital Bridge) was left in a safe position and danger tagged for safety concems. 'Ihe electricians initiated Plant Change Form (PCF) 315406 to requent Design Engineering to evaluate the as-found conditions. Station Problem Report 940273 was subsequently combined with SPR 940252.
On Febniary 10, 1994, the System Engineer in conjunction with Design Engineering evaluated the operation of the Orbital Bridge and issued a Conditional Release Authorization to use the Polar Cranc and Orbiter with the following restrictions:
Use the polar crane and orbiter is allowed only when the polar crane pulls the orbiter for all major movements. Some allowance is provided for only minor adjustment (say less than 10') in the opposite direction.
II.
Event Significance:
This event had no significant effect on the plant, t
Page 1
j III.
Event Analysis:
(or Apparent Cause for Category 4 SPRs)
The apparent cause of this event was the Polar Crane brakes were not adjusted properly. Reference the disposition to Plant Oiange Form 315406-A.
V.
Generic ImpBeation: (Category 1-3 SPRs Only)
None l
VI.
Cormctive Actions:
RI.
Service Request JC-315706 successfully replace the broken power rail clip.
This action was completed February 5,1994.
R2.
Plant Change Form 315706-a was initiated on February 5,1994, to request Design Engineering to evaluate the abnormal tracking of the wheels of the j
Orbital Bridge and the interference with the Orbital Bridge bus supports.
J R3.
A Conditional Release authorization was issued by the System Engineer and Design Engineering on February 10,1994, to operate the Orbital Bridge when being pulled by the Polar Crane. The restricted operation will continue in effect until final disposition of Plant Change Form 315406 A, subsequent corrective actions and release by Engineering to normal rotation.
R4.
The System Engineer and Design Engineering observed the orbital bridge tracking / interferences on March 21,1994, after the following inspections and adjustments were performed on the Orbital Bridge and Polar Crane:
Inspection of the Orbital Bridge wheel bearings per SR 208942.
Diagnostic evaluation on the operation of the Orbital Bridge brakes per SR 208942, and Adjustment of the Polar Crane brakes per SR 208943.
Completion of the above actions indicated:
j The Orbital Bridge wheel bearings were acceptable, The Orbital Bridge brakes were operating appropriately, and The Polar Crane brakes were operating properly after being adjusted.
Page 2 j
1
VI.
Corrective Acdons:(continued)
C1.
Revise OPMP05-JC-0002, Polar Crane Inspection procedure, to include steps to properly adjust the Polar Crane brakes by May 15,1994.
C2.
Maintenance Support will provide a note in the remarks section of the MED stating that PCF 315406-A has a approved design change to rnodify the supports in the future if rubbing of the supports teoccurs. Ihis will allow the planner to see that this engineering disposition is available if Md This note will be added by June 15.1994 to TPNS# 76102NCP201 A and 7C10lNCP201A.
MfT4-T. E. Underwood %
Date i
M "f 6 M aA C4 ct-, e 6. ush. pH V/tr/W P
i i
Page 3
t
~
SPR ACTION COMPLET10N VERIMCATION FORM 1.
SPR#:
9VO2 f 1 Action hem # (If Known):
oi NRC Related
[ } Yes
[x]No Priority A/A 2.
AC110N #(s) STATEMENT (s) 4 3.
THE ABOVE ACrlON HAS BEEN VERlRED COMPLETE SY:
Attached *.
Yes No a)
Document (s) #
o / et/s t - I c.- o o a 2
{}
D(
Il Il
- Il Il il
[]
[]
b)
Describe A sne eY e(ls3,lN f
4.
DATE(s) COMPLETE:
0
/J[9 Y AUTHORIZING SIONATURE:
_ - = _ - - _
bate' VERIFICATION DOCUME'fts SHALL BE PROVIDED FOR NRC RELATED ISSUES.
RECEIVE 9 W l31994 m m m,c, ~...._,,,,
~ ~
PA".E 2
DATE 05/13/94 TIME 13:14:33 SPR ACTIONS FOR SPR 940252 Denartment; h
Due Date:
MRC Consnitment:
Comnlete Date:
MAINTENANCE SUPPORT 04/02/94 no 04/04/94 SMITH, M.G.
CA Descrintion:
INVESTIGATION 11 Due Datet NRC Commitment:
Comolete Date SUPPORT C1 05/15/94 no KELLY, L.E.
CA Descriction:
REVIEW OPMP05-JC-0002, POLAR CRANE INSPECTION PROCEDURE, TO INCLUDE STEPS TO PROPERLY ADJUST THE POLAR CRANE BRAKES.
Decertment:
11 Due Date:
NRC Consnitment :
Complete Date:
MAINTENANCE SUPPORT C2 06/15/94 no 04/27/94
- KELLY, L.E.
Description:
MAINTENANCE SUPPORT WILL PROVIDE A NOTE IN THE REMARKS SECTION OF THE MED STATING THAT PCF 315406-A HAS A APPROVED DESIGN CHANGE TO MODIFY THE SUPPORTS IN THE FUTURE IF RUBBING OF THE SUPPORTS REOCCURS. THIS WILL ALLOW THE PLANNER TO SEE THAT THIS ENGINEERING DISPOSITION IS AVAILABLE IF NEEDED. THIS NOTE WILL BE ADDED BY 6/15/94 TO TPNS #76102NCP201A AND 7C101NCP201A.
f I
k h
1 o
SPR ACTION COMPIErlON VERIFICATION FORM 1.
SPR#:
94/d3 5"2 Action tiem # (If Known):
01 NRC Related
[ ] Yes
[M No Priority (I4 2.
ACHON #(s) STATEMENT (s) 3.
'nIE ABOVE ACTION HAS BEEN VERIFIED COMPLETE BY:
Attached *,
Yes No a)
Document (s) #
- 76B
/r/a/rour-(l W
[]
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a il
[]
Il
!)
Il b)
Describe 4.
DATE(s) COMP 1ETE:
OV-R7'fI AtTDIORIZING SIGNATURE:
p
/
25il%
v~
~
ii Date' VERIFICATION DOCUMENTS SHALL BE PROVIDED POR NRC RELATED ISSUES.
4 l
Pmos 2
hDATE04/21/94 l TIME 09:35 43 (This report keys of f the Departwent Internal Due Instel l
l OFEM SPR INVESTIGATIONS AND CORRECTIVE ACitONS ASSIOceED TO RELLY. L.E.*
l l
DUE FROM 01/Ot/94 M 01/01/9%
l l SPR 920394 E CA Nueber R 1A E Int Due Date 04/09/94 E NRC Ctensteent s no
!! SrR Descriptiom l
l E Unit Cat 4 5 To CAG E Mode Restraint E0BERABILI*Y Cc4CERN RELATING TO ACUT BEING PERFORM DURING REPUBLING.
l l
~~~
~
I -.
E l
l Ae'. ion
Description:
l WRITE 190CEDt9tE TO VERIPY TS. 4.3-1 fvNCTIONAL t? NIT FOR P-33.
E
,l 3 CAG Due Date: 06/15/94 l
l E Responsible 997r s WADDEla. W.E l
l E
l 1
E l
l Ctmunent s :
l E
l E
l l
l' L
l SPR 940252 E CA Nuieer C 2 E Int Due Date 06/09/94 E NRC Cournitment: no E SPR Deeceiption:
l E Unit Cat 4 E To CAG E Mode Restraint: no EwH112 USING THE POKAR CRANE TO SUPPORT SR JC-212034 (REPAIR RtBTED WWIDS l
__- oW TwE PotAR CRANE scProRT sBmSt Tnt cRetTAs. mRIDos ANOLE tRaN. Nutot l
r l=
ESUPPORTS THE POWER CABLES FROM Tts BUSS SARS. CONTACTED A STATIONARY SUSS l l
Action
Description:
l MAINTENANCE Ii'frPORT WIIL PROVIDE A Nort IN THE REMARRS SECTION OF THE MED E
l l STATING THAT PCF 315406 A NAS A APPROVED DESIGN CRANCE TO NODIFY T1tE E CAO Due Date: c6/15/94 l
l SUPPORTS IN T1tB PLM IF RUBS 1NG OF THE SUPPCRTS RLOCCURS. TMIS WILL E Responsible Degre WADDRIA. N.T.
l l A!4LM *INE PIANW111 TO SEE TMAT THIS ENGINEERING DISPOSITION IS AVAILABLE IP E
l E
l l
Cowenente t E
l l
l E
l l
l SPR 931013 E CA Number C T E Int Due Date 06/21/94 3 NRC Consnit=nents no E Sra Descript.one l
l 3 tpnit Cat 3 E To CN3 5 94cde Restraints no ETME DC INPUT MREARER CIDSED. THRif 1994BDIATELT TRIPPED 0P58. THE SUPPLT l
ta gREARER FOR THIS INVERTF.R PROM 125VDC SWBD 13 A150 TRIPPED OPEN.
l gz l
Action Description E
l l INCORPORATE ANUSTING THE NON-CEABS it INVERTER CUTICT SNUTDOWN SETPOllfTS E
l lPER THE TECHNICAL MANUAI, IN PROCEDURE OPMPD5-VA-0003. INVERTER / RECTIFIER E CAG Due Datee D6/24/94 l
l MAINTENANCE EIDAR MODEL UPS 253-1-112 AlfD E1 CAR MODEL 11tv 253 1-105 E Responsible styr s WADDELL. W.T.
l E
l lwMENEVER CIRCU!T CARDS ARS REPtACED.
l l
Comments: MATS 9302104-943 E
3 i
1 E
I.
1 l'
l SFR 932716 E CA Muster C 1 E Int Due Date 06/24/94 E #fRC Commitments no E SPR Descriptions l
E Unit Cat 4 E To CAG H tiode Restraints no EDISCREPAMCIES FOUND IN PetoCEDURE OPMP05-EE-0044, CALisRATICII OF ITE-59G l
REIAYS.
l
[
l Action
Description:
E l
l REVISE PROCECURE OPMP05-EE-0044 TO UPDATE INSTRtX*r!ONS PCR THE TEST E
l lEoUtseerst CURRErn.T rW uBE. RErERENCE MATS zTEM 9302401-es, AND E CAo Due D.te 05/30/,4 l
E Re,ponsible Myrs wAtetts. w.T.
I l92c2359-e49.
E I
I l
l Cennents: MATS 9302401-843 E
E I
l E
I I.
l
~. -
-, -..,.. ~. - -. -,.. -,-
c.,
--.,.a...
.. - - - ~. ~. - -. - -.
SPR SCREENING CRrrERIA FOR START-UP ISSUES NilHill H _, 7
- l'H t
YES NO CRITERIA
[]
(J Is the problem described in the SPR needed to comply with the STP Technical Specifications or other license commitments?
t (J
Do the consequences of not correcting the l
problem affect the ability of a safety system to satisfy its design function?
[]
p Do the consequences of not correcting the problem create or could create a condition that leopardizes the safe or reliable i
operation of the Units?
[]
fp Do the consequenoes of not correcting the problem create or have the potential to. create a Wition that will or could effect# the
. station's ability to effectively support, unit operation or mitigate emergency situaHan=7 O
f)I Does the problem described ini the SPR impact the r=14=M14ty of.the system to per(azz its i
design function?
O p
Is the problem described in the SPR considered-to be a Inode restraint?
(which mode - 1[], 2[], 3[], 4[], 5[])
If the answer to any of the above criteria is ras, the problem described in the SPR needs to be corrected prior to mode change or unit start-up, unless justification for deferral is provided.
COGNIZANT DEPT.
I d - PERATIONS r
CAG DATABASE UPDATED DATE e
e 9
l l
l STATION PROBIEM REPORT SPS#940252 i
REGARDING catepry a Prionty l
Unit 2 OrbJtal Bridge APPROVALS ORIGINAL REV1 REV 2
(}ignature/Date)
(Signature /Date)
W
,f IkY PREPARER APPROVAL 4l4h AUTHORHY 4
REVIEW / APPROVAL l
PORC ORIGINAL REV1 REV 2 l
l V[YES (
)NO ISignature/Date)
(Signature /Date)
Ellpsttrt/ Die)
CAO (k
MfdQ QA (IP APPLICABLE)
PORC (Mtg No./Date)
PLANT MGR CIDSURE APPROVALS I
ORIGINAL REV1 REV 2 (Signature /Date)
(Signature /Date)
Niakst,Dule) g[j((
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STI_-94,-006874-h P.sge 1 of 5
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$TP 486 (06/92)'
SOUTH TEXAS PROKCI ELECTRtC GENERATING $TATION OPGPO3-ZX-COO 2 STATION PROBLEM REPORT p,cc a o7.,_3.
9DN can cAftcoar Oi 02 03 04 Os Ele sen No.
PART 1:
IDENTIFICATION OF CONCERN NAME - M A I R 6fd &
DEPT
/ # 5 A. UNIT $ 0 i O COWWON NMTED:
W$O 02 Er'iom PO9 DON MOP PHONE NO.
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WY Rgy SPR Na PAGE D OF 7 DISTRUCTloses FOR PART 1 COMPLETION ORIGN ATOR.
DESCR6BE YOUR CONCERN CIVING AS MUCH NFORMATION AS POSSIBLE. FILL IN ALL APPUCABLE SECTIONS OR ATTACH DOCUWEN T ATION.
INDIC ATE WH AT. WHEN. W40. W4Y, WHERE. HOW UST ANY REFERENCES DESCREE ANY fWWEDATE COWPENSATORY/ftEWEDAL ACTIONS TAKEN IN ADDITION TO WRITWG THE SPR.
F A COWPONENT. SYSTEW BUILDHG. ETC.15 mv0 LWD. THEN COWPLETE THE APPUCASLE PORTION OF PART 1.
F YOU HAVE ENOUGH INFORWAff0N 70 IDCNTIFY THE CAVSE AND REWEDIAL ACTION, THEN SO STATE.
OBTAIN IWWEDIATE SUPERV. SORS CONCURRENT IF POSStBLE. F NOT POSSOLE OR IF ORIGNATOR DtSAGRES WTH IMME01 ATE chERMSORS POSITION. DEURR TO SMFT SUPERVISOR OR CAC AS APPROPRIATE.
NOTE: E POTENTIALLY REPORTABLE OR F AlfY DOURT EXISTS REGARDING REPORTABILffY. IHL81 MABS CARRY aheWDIATELY TO THE $NFT SUPERVISOfL OTHEAWISE. DELIVER 70 THE CAG ADMsRSTRATOR.
F ANY SECTION 081 SLANK IS NOT COMPLETED. TMN RE00RO N/A #8 THE APPftOPRfATE SECTtOct PART 2:
REPORTABILITY A. PLANT WODE: (CIRCLE ONE) 1 2 3 4 5 6 NO-WODE Ra POWER R TEMP R PRESSURE R TRIP TES ( ) NO [ ]
ESF ACTUATION NtTIATNG SIGNAL B. OPER ABIUTY
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( )N/A PERSON CONTACTED DATE/T1WE INITIALS scy NRC OPS CENTER
( )N/A PERSON CONTACTED DATC/TlWE INIDALS D"
OTHER
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[ ] REPORTABLE PER W THIN law /PERulTWCENSE TlWE: HOURS
[ ] NOT REPOR1ABLE UCENSWG REPPESENTATWE DATE
[ ] CONTNUATION SHEET ATTACHED E. WRITTEN REPORT
- f. NUCLE AR NETWORK REQUIRED [ ]YES
( ) No PART 3:
ACTION ASSIGNMENT ACTION ORCANIZATiON(S) k DEPARIMENT ACTION DUE U
DEPARIMENT ACTION DUE DEP AR TWENT AC T10N DUE
[ ] CONTINUATION SHEET ATTACHED
PART 6: REMEDIAL / COMPENSATORY / CORRECTIVE ACTIONS A. REMEDIAL / COMPENSATORY AcilON COMPLETED (SEYOND PART 1.C)
/
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B. CORRECTWE ACTIONS Il CON 1 ATION SHEET ATTACHED g
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C OUE DATE RESP. MAN R
DATE A
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OUE DATE RESP. MAN AG ER DATE
/
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DUE DATE _
RESP. MAN AGER DATE I l CONTINUATION SHEET ATTACHED PART 7:
ROVALS/ CONCURRENCE I
A.INVES
'ATOR DATE INVESTIG ATING MGR DATE G
N B.
' (IF REQ'D)
DATE
D. PL ANT MAN AGER (IF REQ'D)
DATE E. Q A (if REO'D)
DATE PART 8: CLOSEOUT A. CLOSEOUT
SUMMARY
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STP 486 (12/91)
SOUTH 1EXAS PROJECT ELECTRIC CENERATING STATION IP-1.450-02(RS)
STATION PROBLEM REPORT p,ct i og g scwRity Lcwt Oi
$2 O s (se) sPR No.
9le 4/4 I54Mf5dM DCPT 'Ib /oMM INITI ATED. NAME
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P6 3A. (OTHER) UNIT:
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TECH. SPEC. ACTIONS 8
@ NOT REQUIRED x0 (iP-iRQ) HmD?
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U NEED FUaTHER INF0/ REVIEW COWWENT3.
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fli DATE: C'/J 1
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- 6. NRC REPORTABLL?
N No O Rai to oTHEas (rwC. ETc.)
ovE:
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% n Inspection and Maintenance for Cranes.
OFMP02-2G-0003 Holets. Honorail Systems Rev. 6 and Liftina Devices fase 3 of 17 j
Record 6.1.2 Daily Inspection 6.1.2.1 Daily inspection is required prior to crana use only if the requirements have not been not within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
6.1.2.2 Daily inspection shall be performed using the Crane / Moist /Nonorail Inspection Checklist Data Sheet Form (-1).
Record 6.1.3 Monthly Inspection 6.1.3.1 The monthly inspection requirements identified in this procedure shall be performed prior to erane operation only if the requirements have not been met within the previous four week period.
6.1.3.2 Monthly inspection, shall be performed using the Crane /Holst/Monorell Inspection Checklist Data Sheet Form (-1) in conjunction with the requirements identified below.
6.1.3.3 As applicable, the following thall be inspected for unsatisfactory conditions and damage, with I
inspection results recorded in the ' Comments' section of Form (-1).
a) Moist chains, if applicable.. including and connections, for wear, twist, distorted links interfering with proper function, or stretch beyond acceptance criteria as specified in subsection 6.5.
b) Lubrication levels c) Rope roerdng for noncompliance with crane manufacturer's recommendations.
Record II.4 Yearly Inspection 6.1.4.1 Yearly inspection and lubrication shall be performed in accordance with the Preventive Maintenance and Lubrication Programs required for the specific crane, boist or lifting device.
6.1.4.2 Yearly inspections shall be performed in accordance with the Preventive Maintenance Frogram, if applicable.
l
ch6
%1 OPHP02-EG-0003 Inspectica and Maintenance for Craneet Rev. 6 Holsts Nonorail Systems Page 5 of 17 and Liftina Devices Worn, cracked or distorted parts, such as 1) plas, bearings, shafts, gears, wheels, rollers, locking, clamping devices, bumpers, switch baffles, interlock bolts and stops, as j
applicable.
a) Brake system parts, linings, pawls and ratchets for wear.
Drive sprockets for wear and stretch of n) chain.
Electrical apparatus such as controllers, o) master switches, contacts, limit switches and pushbutton stations, for signs of say deterioration.
Wire rope (refer to subsection 6;2).
p) 1 Wear of drive tires, for monorails and q) nnderbung cranes.
Wear or deformation of lower load carrying j
r) flange of all track sections in the system, both straight and curved, for monorail.and i
J underhung cranes.
6.1.5 Cranes Not in Regular Use Standby cranes shall be inspected prior to each 6.1.5.1 refueling in accordance with Freventiva Haintenance Program requirements.
(Other than olings) Inspection and Replacement 6.2 Vire Rope 6.2.1 Inspection NOTE i
Sections of rope which are normally not visible 1.e., sections that pass over sheaves should be examined carefully, i
I Any deterioration resulting in appreciable loss 6.2.1.1 of original strength, such as described below, shall be noted and determination made as to whether further use of the rope would constitute a hazard.
f
i}0 50 t
Inspection and Maintenance for Cranes.-
OPMP02-ZG-0003 Hoists. Monorail Systems Rev. 8~
and Liftina Devices Page 6 of 23 p) Vire rope (refer to subsection 6.2).
q) Wear of drive tires, for monorails and Underhung cranes.
r) Wear or deformation of lower load carrying flenge of all track sections in the system, both straight and. curved, for monorail and underhung cranes.
6.1.5 Cranes not in regular use 6.1.5.1 Preventive unintenance requirements shall be determined by the designated inspector.
6.1.5.2 Standby cranes shall be inspected, prior to being placed into service, in accordance with this procedure.
6.1.5.3 RCB located standby cranes preventive maintenance shall be performed prior to entering HODE 4, (plantheatap)atthecompletionofoutage.
6.2 Wire Rope (other than slings) inspection and replacement 6.2.1 Inspection NOTE Sections of rope which are normally not visibic 1.e., sections that pass over sheaves should be examined carefully.
6.2.1.1 All wira rope which has been idle for a month or more due to shutdown or storage of a crane on which it is installed, shall be inspected for proper lubrication and deterioration by a qualified inspector, prior to crane being placed into service.
This inspection shall be performed on all of the wire rope that is vir' tie and accessible to the inspector.
/
Houston Lighting & Power Company OFFICE MEMORANDUM To G.I. Parkey e
Maint. 92-9-0653 From J.D. Sharpe Sub/cct SPR 92-0414 Reassignment for Investigation References (a)
IP-1.45Q (Station Problem Reporting), Sect. 6.
Per reference (a), the subject SPR is forwarded to you for investigative action.
Preliminary review has determined that this is an IPS Department scheduling issue. The procedure identified in this SPR had greviously been revised adding the necessary steps.
If you require additional information regarding this subject, please contact L.B. Taylor at extension 7070.
Concur:
I 8,A. McBurnett JLB/cg Attachments (1)
SPR 92-0414 c:
D.L. Musick L.B. Taylor K.D.
Richards c.A-
%yala P.O.
P.3111ngham SPR *J20414 File i
TECHSUP-JLB/ RESIGN.INV p
m
22"[2 SPR APPROVAL CLO,SURE FORM a
STATION PROBLEM REPORT SPR # 4M (p 2/
REGARDING Category F
Priority t/wir i Srra m Calzenrez
__ 7DAr ZUC tectn e *O OhrA s lofH Ide.oe caren-
- D e m) T e P s c. A r g s e)
APPROVA1S ORIGINAL REV1 REV2 (Signature /Date)
(Signature /Date)
(Signature /Date)
PREPARER S 9 Approval Authority WhO& pg,R b
REVIEW / APPROVAL PORC ORIGINAL REV 1 REV2
[ ] YES
[ ]NO (Signature /Date)
(Signature /Date)
(Signature /Date)
QA (IF APPLICABLE)
PORC (Mig No/Date) 1 Pl>MTMOR S T I - 9 4 -0110 0 2 - D ~J J
CLOSURE APPROVAIE ORIGINAL REV1 REV2 (Signature /pa,te)
(Signature /Date)
(Signature /Date)
MSA.[..
CAO ADMIN.
[
OA (IF APPLICABLE) l
b^
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b I.....'...........
04GPO33-2x -00'02 st? 4t4 (oe/p3)
Sou1H ItxAS PROJECI CLECIRIC C(NE4AllNG SIAllON STATION PROBLEM' REPORT 7 V O 6 ~2. /
cAc cAttcDer Oi Or 03 04 50 s Os seR un.
PART 1:
IDENTIFICATION OF CONCERN A. UNIT g E O couuCN-sufiAft0: uAuc J//r AA/ a/o-oc,7 Exu. Proge,,, s O2 0 80tH POstTION $YAff WNde Pn0Ng un. />$$$
DATT d - f-N
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.R00u INSlRUCTIONS FOR PART 1 COMPLETION OtscRBC YOJR CONCCRN CtVtNC A$ WUCH INFORuATION AS P055'OLC.
(stl N ALL APPLtC ABLE SCCIONS OR At1#CH 00CUu(NTAT)ON.
DOCATE VMA1, WHEN. WHO. M4Y, W4ERE, HOW. LIS1 ANY RCfCRLNCCS.
DESCRGC ALL suut01 ATE CouPENSAtoRY/RCMCDIAL ACis0N$ TAKCN WOT E:
E POTENT 4 ALLY RCPORTABLE. OR 8P ANY DOUST Ex1578 REGamptNG REPORIA$lLITY. If((M D(LfVER twMLD4ATELY 10 THE SM1FT SUPERvtSOR. OTHERWISE OtLavtR TO THE CAC ADMINISTRATOR.
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To:
TA RICHARDS, MANAGER NDE TECHNOIDGY FROMs @ RJ HIMMELSPACH, DATA ANIAYSIS GROUP FIL5s CHRON i
CUBJs STP UH1T 1, 09/93 OUTAGE - TUBE MISENCODES DATE:
03/03/94 Following are details on tubes that had encodes changed in the data base for the STP Unit 1, 09/93 Outage without a message.
These tubes have been verified to be different from the tube number originally cncoded.
l l
G/G "A" - OK - No encode changes without messages.
S/G "B" - Tube 08-94 on Cal 61 was encoded on the cal as11-102, but was changed by Secondary and kept by Resolution.
Primary analysis the tubo number as11-102.
The T-list shows that the kept tubos were acquired in descending-row order, and 08-94 would be the correct next tube, not 11-102.
This tube was changed to 08-94 on the profile data base also.
No message.
0/G "C" - Tube 5-76 was encoded as 999-999 with no message on the Cal On the previous Cal 81 the tubes were run in descending 83.
row order and the last tube was 6-76.
The next entry on Cal 83 after the "999-999" tube is 4-76.
This would make the 999-999 tube encode as 5-76.
No message.
Tube 22-73 on Cal 81 was encoded as 21-73.
The T-list shows that the tubes were acquired in increasing-row order, which would make this tube 22-73.
No message.
Tube 35-78 on Cal 83 was encoded as 36-78.
This cal was run in descending-row order.
Primary and Secondary changed the encode to 35-78 in their reports.
No message.
Tube 46-75 on Cal 67 was encoded as 45-75.
This cal was run in increasing-row order, which would make the tube 46-75.
No messago.
S/G "D" - OK - No encode changes without a message.
l
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TA RICHARDS, MANAGER ;- NDE TECHNOIDGY DRJ HIMMELSPACH - DATA ANALYSIS GROUP FILES CHRON FROM:
CUBJ:
STP UNIT 1 - 09/93 OUTAGE S/G "D" HISSED DATE:
03/03/94 TUBES In S/G "D" there are 14 tubes on Cal 12 that were not examined during the fall 1993 bobbin inspection.
It appears that, at the start of Cal 12, the Roger operator was off by one column of tubes, starting with l
tube 26-17.
Acquisition order was by increasing rows and when they got to 40-17 they started acquiring by decreasing rows in column-18.
They started at 41-18 and continued in decreasing-row order.
The last tube in the cal group was 't3-18.
Tubes 40-17 and 40-18 are the same tube, and 39-17 and 39-18 ar > -1so the same tube, as verified by comparison of the tubeshoot profilet This matching sequence continued through tubes 26-17 and 26-18.
In the previous Cal 10 the last three tubes (23-17, 24-17 and 25-17) did not match the last throo tubes on Cal 12.(23-18, 24-18 and 2 5-18).
This shows that in Cal 10 the tubes were indeed acquired from column 17, and that in Cal 12 tube encoded as column 17 were not actually from that column.
The thirty tubes involved were then tube-searched in the data base to see if any had been examined on another cal group. Comparing the tubesheet profi(40-17 Two tubes le of tube 40-18) had been run in Cal 227.
40-18 on Cals 12 and 227 verified the two tubes are the same tube.
Comparing the tubesheet profile of 40-17 on Cals 12 and 227 verified that these two tubes are not the same tube.
Based on the above comparisons it is concluded that tubes acquired in column 18 on Cal 12 are the correct tubes, and the tubes encoded as column 17 were really column 18 and; therefore, the corresponding tubes in column 17 were not examined.
Those tube are:
26-17.
33-17 27-17 34-17 28-17 35-17 29-17 36-17, 30-17/
37-17 31-17 38-17
'32-17 39-17
SPR SCREENING CRITERIA FOR START-UP ISSUES l
- i'Ji N18f188 8:lt _
f Y E.*;
NO CHITERJA
()
g Is the problem described in the SPn needed to comply with the STP Technical Specifications or other license commitments?
{J
[
Do the consequences of not correcting the problem affect the ability of a safety system to satisfy its design, function?
i f1 (4
Do the consequences of not correcting - the
(
problem create or could crea t.e a condition
- that, jeopardizes the safe or reliable operation of the Units?
[J Do the consequences of not correcting the -
problea create or have the potential to.oreate a condition that will or " oould affect the
. station's ability to effectively support, unit operation or mitighte emergency situations?
[]
Does the probles describ'ed is the SPR inqpact the ra14=hility of.the. system to per(orm its l
design function?
P
[]
]
Is the problem described in the SPR c6nsidered.
I to be a mode restraint?
. (which mode - 1[], 2[],.3[], 4(),, 5[])
If the answer to any of the above criteria is YBs, the problem described in the 6PR meeds to be corrected prior to mode ctsange or unit start-up, unless ustification for deferral is provi ed.
00GNIEANT DEPT. M N
OPERATIONS'
- n-cAo Dmaxss UPoArsahldu kepo oars _&lD 4 i
l
SPR No. 94-0621 PART 1: 2DENTIFICATION OF CONCERN B.
PROBLEM DESCRIPTION (CONT'D)
Between September 14 and October 6, 1993, B&W Nuclear Technologies (BWNT) performed eddy current testing (ET) of STPEGS Unit 1 steam generator tubing.
Between January and March 1994, BWNT reprocessed the previously recorded ET data in order to identify anomalous tube roll expansions in the tubesheet region.
Identification of such anomalies was not within the scope of the surveillance conducted in 1993.
During the reprocessing, BWNT discovered the following problems regarding the condition of the previously recorded data.
Problem 1 An analysts noticed that the tube inner diameter profile that he was reviewing was identical to one he had reviewed shortly before.
However, when he investigated, he discovered that the identification recorded on the data indicated that the tubes were different.
The analyst discovered that tube numbers 26-18 through 40-18 ( along the same column) were tested but identified on the data as 26-17 through 40-17.
Later the correct tube 40-17 was ratested.
Thus, fourteen (14) tubes were planned to be tested but were not tested.
The BWNT procedure which the technician was using, ISI-424 Revision 20, requires position verification periodically.
Position verification is not defined in the procedure.
However, it is typically performed by moving the probe to a i
recognizable tube location and confirming that the correct tube number appears on the probe manipulator (Roger) control console.
These position verifications were performed.
So, the Roger controller was probably displaying the correct i
tube number during the time the incorrect tube numbers were recorded on the data.
The hardware configuration which was used has the Roger controller software on a HP9836 computer and the ET data acquisition software on a different computer.
The two computers may be linked via a cable so that the tube-location as determined by the Roger controller software is automatically transferred to the data acquisition software and entered on the data.
A software timing problem caused the Roger controller / data acquisition system to " lock up" occasionally when using the connecting cable.
So, BWNT decided not to use the cable at STPEGS. Therefore it was necessary for the technician to obtain the tube number from the Roger console ~and type it on the acquisition console.
SPR No. 94-0621 Ideally; this system is operated by two (2) technicians, It-is possible that, at the time of the event, the work station was being operated by one (1) technician.
Based on the facts available.-it appears that the problem was caused by random human error.
It is likely that the human error was caused by or made worse by the repetition of the task.
Verifyino position by movino the manioulator to known locations will detect a malfunction of Rocer.
However, it will not work for detectina whether the tube number is correctiv read and entered into the data acouisition comouter.
On the surface, it would.seem that periodically verifying the location of the actual tube just tested ( as opposed to a remote tube of known location) would be effective.
This concept may discover a string of fourteen (14) tubes with data entry errors.
However, it has the following significant limitations:
(1)
It is common to test a large number of tubes, none of.
which are a readily recognizable landmark.
(2)
Counting the tubes to the nearest landmark is time consuming and also subject to human error.
(3)
Periodic verification will not reliably detect a single event (e.g. making a single error and then performing correctly).
The error could have been detected and prevented simply by careful reference to the list of tubes to be examined or the Roger console.
The risk of this type of mistake can be eliminated by removing the manual data entry step.
Problem 2 While the data was being reprocessed to identify roll profiles, the results for each tube were entered into the BWNT *TUBAN2" data base.
At the conclusion of the ET data reprocessing, the results were reviewed to assure that everything.was in order.
Tuban 2 indicated that profiles had Dol been acquired for a small number of tubes.
On investigation it was found that the ET data for some tubes was encoded with the wrong tube number.
Whenever a technician acquiring data discovers an error of -this type he.
is supposed to generate a message on the data indicating the correct tube number.
Initially all of the STPEGS Unit.1 bobbin coil data from the Summer 1993 inspection was reviewed to. identify tubes examined out of sequence.
Five (5) tubes with incorrect tube numbers and no clarifying i
8
i SPR No. 94-0621 j
message were identified in Unit 1.
Later, the 2RE03 ET data f
was reviewed.
One. (1) similar encoding error was discovered
}
in Unit 2.
The root cause-of the problem is inattention by the operator in encoding the tube numbers.
C.
IMMEDIATE COMPENSATORY OR REMEDIAL ACTIONS TAKEN (CONT'D)
The problems identified in SPR 940621 regard services which were performed under the jurisdiction of the BWNT Quality Assurance program.
Letter No. ST-HS-20-12 entitled
" Response to Site Problem Reports on the Condition of Optical Disks Containing Eddy Current Data" was prepared and
-transmitted to BWNT on March 15, 1994.
This letter transmitted the SPR 940621 to BWNT.
It also requested that actions be taken to address these problems in accordance with their Quality ' Assurance program requirements.
BWNT transmitted with the attached letter entitled " Station Problem Reports 940515 and 940621" on April 27, 1994 three (3) BWNT Non-conformance Reports (NCR's) Nos. 94-00185, 94-00186, and 94-00187.
Each of these NCR's contain BWNT-approved dispositions.
The following additional compensatory or remedial actions were immediately taken:
l Problem 1 The BWNT analyst reported the scope of the problem in the I
attached memorandum entitled "STP Unit 1 - 09/93 Outage S/G "D" Missed Tubes" dated March 3, 1994.
l It was determined that there is a record of: the position f
verification performed immediately prior to testing tube 26-17 (actually tube 26-18).
It was determined that there is also a record of position verification performed seven (7) tubes after testing tube 40-17 (actually tube 40-18).
This indicates that the Roger controller was probably displaying -
i the correct tube number during the time the incorrect tube numbers were recorded on the data.
The scope of bobbin coil ET during the Summer 1993 Unit 1 5
and 2 was intended to include all tubes.
Therefore, the bulk of ET data was recorded sequentially up and down the rows or columns.
Errors in encoding of the tube number in the ET data will be evident sometimes when the sequence of encoded tube numbers is abruptly disrupted.
That is, a tube number is repeated or skipped in the logical progression.
In response to Problem 1 and 2 of this SPR, BWNT reviewed i
the order of all tubes tested by the bobbin coil method in Unit I and 2 to attempt to identify any other encoding errors.
BWNT compared tube profiles of the data discovered out of sequence to data taken in the same tubes on other r
SPR No. 94-0621~
occasions to verify their. identity.
Otherwise there is no way to determine whether this error occurred elsewhere.
HL&P determined that the fourteen (14) tubes which were not tested were not required by the STPEGS Technical Specifications to be tested.
HL&P determined that none of the fourteen (14) tubes which were tested twice contained.a condition which required repair.
So, no plug was installed in an incorrect location.
Problem 2 The BWNT analyst reported the scope of the problem in the attached memorandum entitled "STP Unit 1, 09/93 Outage -
Tubes Misencodes" dated March 3, 1994.
BWNT reviewed the Unit 1 Summer 1993 and 2RE03 bobbin coil data and identified six (6) tubes where the test sequences were disrupted and there were no error messages recorded.
BWNT compared tube profiles of the data in. question to data taken in the same tubes on other occasions to verify their identity.
BWNT concluded that the correct tubes were tested but the data was encoded incorrectly.
The five (5) Unit 1 cases were previously discovered by the data analyst in 1993.
It was verified'that the analysis results stored in the TUBAN2 data base for Unit 1 are correct.
However, the case for 2RE03 Steam Generator A tube 22-86 was apparently not noted previously.
It was determined that the TUBAN2 entry for this tube with index number 66 is incorrect.
HL&P determined that none of the six (6) tubes contained a condition which required repair.
So,.no plug was installed in an incorrect location.
In the process of conducting the review of 2RE03 data the working copy of Steam Generator B Optical Disc 5 Side A and Steam Generator D Optical Disc 7 Side A could not be read by the analysis software.
They were corrected by BWNT by copying the original discs to the working copy.
PART 4: ACTIONS TO BE COMPLETED (CONT'D) i C1.
BWNT committed in the disposition to their NCR No. 94-00187 that the Roger Operating Instruction will be -corrected by July 31, 1994 to require the use of the cable linking the Roger and ET data acquisition computers.
Mr J.
L.
Haning in HL&P Engineering Programs will verify that Aucosf15.n94.y a D the Roger Operating Instruction has been corrected by f fir. dk
'~'
(M. Pacy) j C2.
BWNT committed in the disposition to their NCR Nos. 94-00186 and 94-00187 that Mr.
T. A. Richards, BWNT NDE Technology Manager, will issue a memorandum by May 1, 1994 to all BWNT
. _ ~
._.e SPR No. 94-0621 (and vendors in the future) certified ET personnel emphasizing the importance of encoding correct tube numbers.
Mr. J. L. Haning in'HL&P Engineering Pro, prams wil ify that the memorandum has been issued by MAV10,1994_
~~
'(M. Pacy)
C3.
BWNT will correct the STPEGS files in their "TUBAN2" data base management system for the 15 Unit 1 tubes addressed in Problem 1 and for Steam Generator A' tube 22-86 from the 2RE03 outage addressed.in Problem 2.
They will transmit an update of the TUBAN2 files to STPEGS by June 15, 1994 along with uploading instructions.
Mr.
J.
L.
Haning in HL&P Engineering Programs will load the update (Tuban2 files into the STPEGS Tuban2 data base by ZFuty f.1994 nl, _
(M. Pacy)
After the completion of the Summer 1993 Unit i nspection, BWNT developed a Roger controller and ET data acquisition console design which places both functions on the same computer.
This configuration possesses the automatic encoding feature and requires no connecting cable.
The new system is designed for one person operation.
l l
l
2..
. O %$,.:..V At4T SPIS F-162 1-003 P-011 APR 27 '94 13:3'i
~BW B&WNUCLEAR TECHNOLOGtKS s5S MAR,$pe %
E W A educts & W W Se m oes
((y rekecpysod a2P-ose; April 27, 1994 SGBM-94-3361 Mr. J. Haning Houston Lighting & Power Company South Texas Project P.O. Box 289 Wadsworth, TX 77483
Subject:
Station Problem Reports 940515 and 940621
Reference:
(1)
HLEP Letter No. ST-HS-2U-12 dated March 15, 1994 (2)
BWNT Letter No. SGBM-94-3351'
Dear Jim:
Enclosed for your review and concurrence are three B&W Nuclear Technologies (BWNT) Non-conformance Reporte (NCR) which address the two Houston Lighting & Power. Company Station Problem Reports (SPR) that are identified as the subject of this letter.
The Specifically these NCR's are.
(3)
NCR No. 94-00185 which addresses SPR No. 940515 (2)
NCR No. 94-00186 which addreepes SPR.No. 940621 (3)
NCR No. 94-00187 which addresses SPR No. 940621 These NCR's address the root cause of the non-conformances and corrective actions that will be taken by BWNT to minimize the chance of such problems recurring in the future.
j After you have completed your review of the NCR's please sign and date each NCR as identified in Section of the NCR: and return the i
original to BWNT.
If you have any questions or comments on the attached, please contact me at (804) 832 3464.
)
i very truly yours, h
(d.
Dennis W. Renner.
Manager, Marketing Steam Generator Services i
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Norwanformance Report Non #_.9/-M//f (Typical Pare)-
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- 1. Purchase Order #II-* /MIII contract # /#/M'3 Supplier TWr/ GAS customer _ [/ Y Site 8T8
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Past #
serial #
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Sequence / step #
ksafety-selated Oson-Safety-Related OmgM3 code 2.
Ita= classifications b
/Ab [ d.h E
- 3. Deecription ee Nonconformances A A/ 2 I m ehr/?
1 OrL Lnatoe _/T Ahmehshs/4-ed/
Date A-lT'l4 K tinne
/ P.'W 4.
9 S. cause of NCRs Personnel hooediare f
t ter1=1 peaten other Sec l i 2, and 3 of attached response.
i g,pt, to, _,
D
- s. Di.posittoo or men:
D o.e a rs Omopair/metaspect Oneplace aasis.
See item _4 of attached response, approval seguired OnN2 IEfcusta e
- 7. Prevent 4t.1re Action:
See item 5 of attached response.
- ats:.
- s. Applicable to other contracts Uso' S&res mesolution _ included in item 5 of attached response.
i Distribui19A i
NCR Discosition Acaroval l
ElR Ing Diviolon gn Manager cognisant togineer E. _ _ __ - e I
1 cognisant angineer Purchasing Reviewer X;C //m-+ _
l Project sngineer ovowment control Unit. Manager '#<JS uiz # '
Project Manager pcm originator
- Project Manager.bu h us A" _
punta section Manager YP&GN (Close Out Daly)
- 3f customer appcova.1 is required
- 9. Customer Review (if required)
Date As1 Review (if required)
Date _
V Disposition completeds amps Date Page 9 of
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r-m ;.' i-N P U B MR Fi'tu 15:3 u,r.; <j. s j
RESPONSE TO BwNT NCR #94-00185 i
1.
WHEN DISCCVERED
' This nonconformance was discoverad' in February 1994 dur.ing the South Texas Project MRPC wave analysis of data from the September 1993 outage.
2.
DESCRIPTION OF NONCONFORMANC11 On optical disk #1STP12A, the raw data for 696 tubes is aimaing from side A for Unit #1 MRPC hotleg examinations during the September 1993 outage. This is contrary to the usual data management practice for administering and storing oddy current data during an outage.
The primary, secondary, and resolution results, however, are present on both sides of this optical disk showing that no tubes were missed.
The raw data is present on side B, but is 1
missing only from side A.
The nonconformance is that there are no requirements in IsI=
)
69, Revision 18, for the administration and storing of the eddy current data during an outage.
I The following is a-brief explanation of the data flow between i
data acquisition and data analysis during the South Texas Project work.
Acquisition personnel acquired the data and I
recorded it on an optical disk.
The moquisition software program also copied the raw data from the optical disk to a hard drive on the data analysis server via a fiber optic cable.
After both sides A and B of the acquisition optical disk reached the maximum raw data limit, the disk was hand carried to the data analysts.
The data on the analysis server hard drive was then analyzed and the results temporarily stored to a results directory on the analysis server hard drive.
After the analysis and resolutions were completed, the acquisition optical disk was mounted on the analysis server and checked to see that all of the raw data is intaot. The results were then copied from the analysis hard drive to the acquisition optical disk.
- Finally, the raw data was erased from the analysis server hard drive to make room for more raw data.
The acquisition optical disks then became working copies and are now typically used for changing the resolution results and subsequent analyses, such as the tubasheet profilometry project.
3.
E0XCQNPORMANCR_HOIATgp2 The root cause is an inadvertent erasure of the raw data during the writing or correction of the results on the optical disk.
This violates a requirement of the customer's Purchase
- Order, but not any present requirement of BWNT Administrative Procedures or the QA Program.
' a, 4.x
..,m.j,g n,- a
- e
. D.WW BLen SPIS F-162 T-003 P-004 APR 27 '94 13:34 RESPONSE TO BWNT NCR #94-002JtJ.
(CONTINUED) 4.
CORRECTIVE ACTION:-
The primary, secondary, and resolution results are present on both sides of this optical disk showing that no tubes were missed.
No further correotive action is required.
5.
PREVENTIVE ACTION:
By July -31, 1994, a new BWNT Adminis-trative Procedure will be prepared and approved describing the requirements for administration and storing of data by data management personnel, including making a duplicate of the moquisition optical disk when first received at analysis.
(302-NCR94185)
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(Typical Form)
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Ites Name N fMAn/=df Drawing #
Part #
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2.
stam classificatione ety-Rolsted D5am-Safety-melated Casssa code
- 3. DescriptLoa of monoomtoamaaoes )ne hs/_ f nisat/ M & e-61 Ade s-A
->A A A r h a// A n _ & / / / W 4;Ar4%4-tLee /5:4 r 4.
gtsatar _1'5ilmserirH &
Date
- 5. Cause og scas anel are t
unplain.
See items 1, 2,.and 3 of attached response
- 6. Disposition of DCRs EUse As Is Onepatr/mainspect Omeplace assis See item 4_ of attached response.
Approval Required:
Onsrz E!Teuetoner See item 5 of attached response.
- 1. Pr ventative Actions l
consoeots:
- s. Applicable to oth.r contracts Duo' Mres Resolution: Included in item 5 of i
attached __ response.
Distributien BCR Dianosition Annros man tog Division OA Manager cognizant Epc r
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cognisant EaC.ineer Furchasing Reviewer M
_ /r M Project. segLn,e Docuneet. coat. col onLe Manager N
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- Froject Managerr Rh4 strus sectiac Manager VP&GM (Close Out Only)
- If customer appevy is swguired I
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Date amt moview (ir required)
Date Q
DisposLtion completed: getsg cate Page 9 of '
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F-162 1-083 P-00ts 4 H 7/ osa 13:35 s
RESEQHSE_TO_BWNT NCR #94-00186 1.
)DIEN DISCOVERED:
This nonconformance was discovered in February 1994 during the South Texas Project bobbin tubesheet profile analysis of data from the September 1993 outage.
2.
DESCRIPTION OF NONCONFORMANCE:
Six (6) errors were made in the encoding of tube numbers during data acquisition in Units
- 1 and 2 during the September 1993 outage.
By Unit, Steam Generator, and tubo number, the tubes were:
e steam Correct Encoded Unij; Cenovator Tube No.
Tube No.
1 B
8-94 11-102 1
C 5-76 999-999 1
C 22 21-73 1
C 35-78 36-78 1
C 46-75 45-75 2
A 22-87 22-86 The actual tube numbers have been verified to be different from the encoded tube numbers.
For Unit.#1, this'was done during the outage at the site by the data analysts, based on the order in which the tubes wore run.
During the tubesheet profile analysis in February, 1994, baseline and other pre-1993 data were compared to the 1993 profile data, and i
confirmed the tube identifications assigned to the data by the i
analysts.
For Unit #2, on Cal 84, two tubes were encoded as 22-86.
The first (Index #65) is 22-86; the second (Inder #66) is 22-87.
Tubo 22-87 was verified in February,1994, to have been rerun on Cal 92 during the outage.
This was also verified against baseline data..
The data for tube 22-86, however, is entered in the final report under the wrong Index number.
3.
NoNCONPORMANCE VIOLATES: The root cause is inattention by the operator in encoding the tube number.
In each case, however the acquisition operator did not correct his encoding error, with a message, as required by ISI-424, Revision 20, Paragraph 9.4 --
' Corrections to any tube identity shall be made using the message function following the completion of the tube i
run."
4.
CORRF, m VE_4QTJpH1 During the eddy current data analysis at the site, the reported tube numbers were corrected based on the increasing or decreasing row order in which data was taken.
Subsequent comparison of tubesheet profile data from the 1993 data with baseline or pre-1993 data shows clearly that the tubes as renumbered are correct and were examined.
The Tuban II database must be annotated to show that the correct run of tube 22-86 is Index #65, not #66.
No other corrective action is required.
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BJ4T SPIS F-162 T-083 P-007 APR 27 ' 94 13: 3.
l RESPONSE To BWNT NCR #94-031A4 (CONTINUED) 5.
PREVENTIVE ACTION!
TA Richards, MDE Technology Manager, will issue a memorandum by May 1,1994, to all BWNT (and vendors in the future) certified addy current personnel emphasizing the importance of enooding correct tube numbers and the requirement in Paragraph 9.4 of ISI-424, Revision 20.
(302-NCR94186)
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Onni 66custaaer See item 5 of attached response.
- 7. Preventative Action:
h nte S. Applicable to Other contracts UNo' Eres Resolutions _ Included in iten 5 of attached response.
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Disposition Ocepleteds SWNS Date Pags 9 of
- BMVAY 1AJU SPIS F-162 T-083 P-009 APR 27 '94 13:36 RESPONSE 19 BwNT MCR #94-00187
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i 1.
IfMEN DISCOVERED:
This nonconformance was discovered in February 1994 during.the south Texas Project bobbin tubesheet profile analysis of data from the September 1993 outage.
2.
pESCRIPTION OF NONCONFORMANCE: Fourteen (14) tubes in Unit #1 Steam Generator D were not examined by bobbin coil during the September 1993 outage, as a result of an error by the. ROGER (manipulator) operator.
These tubes ares 26-17 33-17.
27-17 34-17 28-17 35-17 29-17 36-17 30-17 37-17 31-17 38-17 32-17 39-17 The tube numbers-examined in place of those listed.above have been verified by tubesheet profiles to be tubes 26-18 through 39-14.
When the ROCER operator repeated tubes 26-18 through 39-18, he did not recognize his previous error in encoding 26-17 through 39-17.
As a result, the missed tubes listed above were not run, despite W appearance to the contrary at data management.
The following io.a brief description of the sequence of events. At the start of Cal 12, the Roger operator was off by one column number, starting with tube 26-18 which was encoded as 26-17.
Acquisition was performed in increasing-row order until the operator ranched tube 40-18 which was encoded as 40-17.
At this point the ROGER operator discovered the error and changed to acquiring data in decreasing-row order in column 18 starting with tube 41-18.
The last tube in the cal 12 was 23-l 1s.
Comparison of.the tubesheet profiles for tubes 26-17 through 40-17 with 26-18 through 40-18 verifies that they are the same tubes.
In addition, a tube search revealed that tubes 40-17 and 40-18 were also run on Cal 227.
Comparison of the tubesheet profiles of tube. 40-1s on Cels 12 and 227 verified that both were the same tube.
Comparison of the tubesheet profiles of tube 40-17 on Cals 12 and 227 verifled that these were not the same tube.
t 3.
RQHCONPORMANCX JIOLATESA The root cause is the failure of the ROGER operator to detect his' error in encoding the tube identities. This is a violation of the Tube Inspection Plan.
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.O.*W6N Bular SPIS F-162 T-WJ3 P-010 APR 27 '94 13:37 RESPDHSE TO BWNT NCR #94-00187 (CONTINUED) 4.
pDRRECTIVE ACTION: Correct the ROGER Operating Instruction to require the Roger and acquisition-computers to be connected by the RS-232 9-pin to 25-pin cable..
This will automatically make the Roger and soquisition computers show the same row / column identification for a given tube.
This change will be made by July 31, 1994.
NOTE: The ROGER software and Eetec acquisition both now run on the same computer / operating systen.
In this case, the tube number encoded by acquisition is the same as the RocER location.
5.
PREVENTIVE ACTION 1 TA Richards, NDE Technology Manager, will i
issue a memorandum by May 1,1994, to all BWNT (and vendors in the future) certified addy current personnel ^ emphasizing the importance of encoding correct tube numbers.
(302-NCR94187)
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SPR ACTION COMPLETION VERIFICATION FORM
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The undersigned have verified that the above action (s) have been cocepleted as described. This corepicte forro is subject to QA Audit and gjL%L be filed with the SPR file.
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DOCUMENT CHANGE NOTICE DATE 25$UEDs_8 /32/94 SERIAL NO.: 94-957 CHANGE I6:
GENERIC CONTRACT SPECIFIC CONTRACT NO.(S) (IF CONTRACT SPECIFIC)s__.112 7141.__.
DrsTnzasuT20sts RL mossRo/xR-11 RW MVNDSTAD/MA-11 (OTHER/MR- )
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FROJ BNGINEER OTHER 00GNISANT ENGINEER DasemIFTIcer or caANGB:
I Add the following to the end of Step 4.1.11:
In order to implement this, the ROGER Cornputer muet be Connected to the addy current acquisition computer by an RS-232 cable.
AFFECTED TITLEROCER OI SDLC COMPUTER BYSTEM DOCUMENT NO(S) _1149279A-REV.s_14 REV.t, ccur.oute ron enAnors _ u/A _
(SITI WORK, TRAININC, TDL, REFURBISPDGNT)
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The Night Shift Report (3/9-3/10 - 94)
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1.-
The B&W DCN Welding Proidem:
PROBLEM DESCRIPTION:
a)
B & W welding procedure specification /750/ plug-01. HL&P log number 400999-00029-AZU on page 3 of 5 states in part "Use this Weld Procedure Specification in conjunction with: WPN-7".
b)
WPN-7 has been superseded by procedure S P-2 ( General Procedum for Arc Welding) and B&W issue DCN 129246-00 to 400999-00029 equivalent number to correct the update.
c)
In an effort to update 400999-00029, an HL&P DCN was initiated to reflect change specified on B&W DCN 1229246-00. During approval process of this DCN, procedures S{P-2 or WPN-7 could not be verified being approved by HL&P.
d)
Procedure OPGP04-ZG-0310 states in paragraph 4.3.1.2 that " The contractor procedure and supporting procedure qualification records shall be submitted for review". This step is not clear on how in depth the procedure review needs to be enforced.
DECISION PROCESS:
a)
The following personnel were involved in the decision to continue to work:
-Randy Fast
-Mark Kanavos
-Ken Silvertorne
-Jim Halley
-Faramarz Pournia
-Carlos Gonzalez b)
Mr Groth and Mr Rchkugler were informed and agree with the decision made to continue the weld process and to take care of the procedure review in the morning since it was considered an administrative problem.
c)
A problem report needs to be generated to document this incident and to review procedures as required.
l SPR 940636 1 of 2 SPR 940636 B&W DCN WELDING PROBLEN I.
EVENT DESCRIPTION on the evening of 9 March 1994, during preparations to weld a tube sheet plug in the Unit 1
'C' steam generator, it was l
identified that a B&W Nuclear Service Company (B&W) welding i
procedure (51-1205396-01) referenced a superseded document.
A i
B&W Safety Document Change Notice was issued to correct the procedure.
During this change process it was noted that the STPEGS Welding Program (OPGPO4-ZA-0310) required that:
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"The contractor's procedures and supporting procedure qualification records shall be submitted for review and statusing to DED's Codes, Standards and Materials Group prior to the performance of Welding".
Appropriate HL&P management were informed of the situation, a
decision was made to proceed with the welding and address this administrative problem on the morning of 10 March, 1994.
II.
EVENT SIGNIFICANCE The reference to a superseded procedure and the subsequent correction had no impact on the quality of the welding performed.
The actions taken to correct the procedure and resolve the problem delayed the completion of welding by about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
This delay did not impact returning the plant to operation.
i The superseded B&W procedure (WPN-7) was replaced by BAW procedure (SPP-2).
SPP-2 is the B&W: " General Procedure for ARC t
Welding".
t During the subsequent review of this event the HL&P approval authority (for the STPEGS Welding Program) stated the following i
(see attached):
i The intent of procedure OPGP04-ZA-0310 is that the contractor's Welding Procedure (WPS) and the supporting procedure qualification records (PQR) shall be submitted for HL&P review and statusing prior to welding.
Other supporting procedures such as general welding procedure etc.
t are not required to be reviewed and statused.
This intent would not be understood unless the question was directed to the approval authority, i
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SPR 940636 f
2 of 2 III. CAUSE OF EVENT i
.The cause of the event was that B&W personnel failed to recognize
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the need to revise the Welding Procedure Specification (51-
-1205396-01) when the referenced document (WPN-7) was changed to SPP-2.
IV.
CORRECTIVE ACTIONS Immediate Remedial Actions Rl.
The B&W procedure was revised to reference the correct document (SPP-2).
R2.
A question regarding the need to review the newly referenced document (SPP-2) was deferred until the next work day.
Remedial / Compensatory - None Correctirre Actions j
Cl.
The STi'EGS Welding Program (OPGP04-ZA-0310) sponsor will revise th gram document to clarify the requirements for st tusing by DED.
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Due Date:
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Trend Codes M[p/ '
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Event Codes EKIL z Vendor manual / document
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2.
Casual Factors - [I I-dTT Change related documents not developed or not revised C51:s e
STP 1230 (08/90)
SOUTH TEXAS PROKCT ELECTRIC GENERADNG STATION VENDOR DOCUMENT COVER SHEET SUPPLIER DOCUMENT NO.: 8/~~/OOb3b ~O/
PACKAGE NO.: Yk88//
DOCuutNT rnTLE:llMLD/A/G hY&htPC.STt'lF/C47/DA//7SD //'L/JK-o /
SUPPLtER NAME: bY N] llll5'l5AA SfSlllff Cil, EOUIPMENT TAG NO*S HL&P LOG NO.(S) 4@D999-Oooa9-82u (MPORTANT Permission to proceed does not constitute occeptonce or approval of design detoils, cofculations, onofyses, test methods or moteriots developed or selected by the supplier and does not relieve supplier from fuit comotionce with contractual obligotions.
DATE HL&P RECEIVED C3-/O-9[
SIGNED DOCUMENT STATUS
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1 N APPROVED FOR USC/ WORK MAY PROCEED.
2 O APPROVED FOR USE AS DATE STP NOTED/ REVISE AND RESUBMIT, WORK MAY 3 - t o - 9 y, PROCEED SUBECT TO CONTROLLED COPY INCORPORATION OF CORRECTION INDICATED.
SOUTH 3 0 NOT APPROVED / REVISE TEXAS MAR 101994 AND RESUBMIT. WORK MAY PROJECT NOT PROCEED.
4 O Review NOT REOUiRED ST-RM-0147 (02/86) 0" 0cv je.
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