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1.0 PURPOSE 1.1 This procedure establishes the responsibilities and requirements for maintaining Plant Design Control at the Vogtle Electric Generating Flant (VEGP). 1.2 This procedure establishes the minimum requirements for initiating and processing Request for Engineering Review (RER), Request for Engineering Assistance (REA), Design Change Request (DCR), Minor Departure from Design (MDD), As Built Notice (ABN), Facilities Indices Change Request (FICR) and Field Change Request (FCR). NOTE ( Design changes to the plant will be initiated an a final alternative to a plant condition. Methods of correcting a plant condition while maintaining plant configuration and function will be exhausted prior to initiating design change activities. 2.0 DEFINITIONS 2.1 DESIGN HODIFICATION ? l 2.1.1 A. design modification is a permanent physical change which alters the function of a structure, system or component as described in the FSAR, impacts the Plant Design Bases or impacts the Security Plan. A design modification either directly or indirectly impacts safe plant operation or plant reliability. A 92022003939201g6 DR ADOCK 0500 4 l mnm== 1
a l,,, enoceountmo. navescm paet wo. VEGF 00400-C 11 2 cf 33 i NOTES a. Plant reliability is impacted by those structures, systems or components which are directly involved in power generation (i.e., main turbine generator, stator cooling, etc.), b. Physical changes to ancillary buildinas such as the Service Building, Administration Building, Maintenance Building, Production Warehouse or to facilities outside the protected area which are not part of a aystem involved in power generation are excluded from-the requirements of this procedure. Impact to power generation will be determined by the (t General Manager-Nuclear Plant (GMNP). 2.1.2 Any physical changes made outside the protected area, within the site boundarias, shall have an environmental review per Procedure 00056-C, 'Safet These changes include,y and Environmental i Evaluations. but are not limited to, changes in withdrawal and usage of surface water, changes in withdrawal and usage of ground water, changes in the contour of the land, changes in + discharges, etc. l 2.2 SAFETY RELATED L 2.2.1 . Plant structures, systems, and components necessary to l assures a. the integrity of the reactor coolant pressure 1
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sWOOlM M MYWoo84 PA41 No. ' 9 VEGP 00400-C 11 3 of 33 l c, the capability to prevent or pitigate the consequences of accidents which could result in offsite exposures that exceed the guidelines established in 10 CFR 100. 2.2.2 Systems, components, or instrumentation designated as nuclear safety class 0, 1, 2, or 3 and listed in FSAR Table 3.2.2-1: and instrumentation designated category 1 or 2, as listed in FSAR Table 7.5.2-1: Fire Protection systems / components as described in Procedure 92000-C " Fire Protection Program": Radwaste systems / components having a Project Classification of XX7, where XX are safety class and seismic class, respectively. NOTE Procedure 11850-C, " Safety-Related Equipment Classification" contains the information listed in FSAR Table 3.2.2-1 and FSAR Table 7.5.2-1, 2.3 DESIGN BASES ( Information which identifies the specific functions to be performed by a structure, system or component of a facility and the specific design values or ranges which have been chosen for design controlling parameters as reference bounds. These values may be a. restraints derived from generally acceptable " state of the art" practices for achieving functional goals, or b. requirements derived from design analysis (based on calculation and/or experiment) of the effects of a postulated accident for which a structure, system, or cow onent must meet to achieve its functional goal. 2.4 CRITICAL DRAWINGS Drawings which are utilized for safe operations or shutdown of the plant. These drawings are limited to ( one-lines, elementary, and P&ID drawings. l II man l -~
na i enume wo. newsson PAos wo. VEGP 00400-C 11 5 of 33 t i 2.10 DESIGN CHANGE PACKAGE (DCP) A package which contains the complete details of a design modification. The package includes, but is not limited to, the DCR which initiated the change, a narrative sumniary of the change, a safety evaluation of the change, list of materials required for the change, and details of the change including drawing changes and any special installation instructions. DCPs are generated by the Architect / Engineering (A/E) organizations. 2.11 FACILITIES INDICES CRANGE REQUEST (FICR) A document generated by the Engineering Suaport Department to detail required changes to t:1e Plant Equipment Index, Instrument Index, Valve Designation List, Line besignation List, Penetration Seal Designation List or Power, Vent, Drain and Root Valve List. 2.12 AS BUILT NOTICE (ABN) ( A document generated by the Engineering Support Department to detail required changes to plant design documents. 2.13 SITE DESIGN CHANGE PACKAGE (SDCP) A Design Change Package which is generated by the Engineering Support Department to accomplish a design modification. 2.14 HINOR DEPARTURE FROM DESIGN (MDD) A MDD is a design change generated by the Engineering Support Department. A minor departure is a design change of von limited scope. A minor departure from design is a change which will be incorporated into permanent plant design, i I 9 ? t d'rw,a y ,y9g ---e9,9mg-+- - --- y... ,,pp,,7 37 ,m. 9
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PROCEDunt No. AgysesoN PAot Peo. ~ VEGF 00400-C 11 6 of 33 ( 2.15 TEMPORARY MODIFICATION (TH) A Temporary Hodification is a temporary physical change which alters the function of a structure, system or component as described in the FSAR, impacts the Plant Deslgn Bases, or impacts the Security Plan. A Temporary Hodification either directly or indirectly impacts safe plant operation or plant reliability. 2.16 EQUIVALENCY DETERMINATION j NOTE An equivslency determination may not be used to effect a change in parts or materials involving: a non-compliance new design,pecification, a to an A/E s a major material change, or a major change to a system / component support interface (i.e., adding pneumatic or electrical connections, mounting changes, ( etc.). A technical evaluation performed to confirm that an alternative item, which is not identical to the original item, will satisfactorily perform its intended function once in service. 3.0 RESPONSIBILITIES t 3.1 MANAG3R ENGINEERING SUPPORT The Manager Engineering Support (MES) will ensure the following: 3.1.1 Technical assistance is provided to disposition Request for Engineeting Review. 3.1.2 Development of departmental procedures to control L physical changes to the plant. These procedures will l cnsure the following a. All Design Modifications are processed as either a .g DCP, or SDCP or MDD. M
MIDCEDURE P*C REYiseCW PAot peo. VEGP 00400-C 11 7 of 33 b. Design Modifications which are extensive or complex are processed as DCPs. c. Equivalency determinations are used to verify that an alternative item, which is riot identical to the original item will satisf actorily perform its intended f unction once in service. NOTE The MES will ensure an equivalency determination is not used to effect a change in parts or materials involving a non compliance to an A/E specification, a new design, a major material change, or a major change to a system / component support interface. 3.1.3 Developing desartment procedures for processing DCRs, DCPs, SDCPs, KDDs, FCRs ABNs, REAs, PICRs and Equivalency Determinations. 3.1.4 Assignment of control numbers and tracking of site enerated RERs, REAs, DCRs, MDDs, FCRs, FICR snd ( kquivalencyDeterminations. 3.1.5 Processing of Design Change Packages, Site Design Change Packages and Minor Departure from Design Packages in accordance with approved department procedures that include as applicable: 3.1.5.1 Coordinating with the Financial Services Department to verify budget availability and proper budget documentation. 3.1. 5. 2 Ensuring design modifications are reviewed by qualified reviewers. 3.1.5.3 Coordinating with the Outages and Planning Department to develop an implementation schedule when required. l 3.1.5.4 conducting constructability,ffected departments. maintainability, operability and ALARA with a l 3.1.5.5 Developing required Safety Evaluations and Equipment Environmental Qualification Statements when required, in accordance with Procedure 00056-C, " Safety and Environmental Evaluations". l L/ i t W E'.
'PRoCtDURE No. MtYISfoN PAGE No. VEGP 00400-C 11 8 cf 33 3.1.5.6 Initiating required Licensing Document Change Request ( pCR) in accordance with Procedure 00402-C, " Licensing D(ocument Change Request". 3.1.5.7 Verifying compliance with the FSAR, applicable codes, standards and regulatory requirements. 3.1.5.8 Providing design change narrative summaries and other necessary support documentation to other department heads as notification of a pending design modification for use in determining if procedure revisions or additional training are required. 3.1.5.9 Initiating procurement requisitions with supporting documentation when non-stock equipment / parts are required. 3.1.5.10 Notifying materials section when new items are added or items are made obsolete in accordance with Procedure 00852-C, "New Or Obsolete Parts". 3.1.5.11 Developing functional test requirements. 3.1.5.12 Ensuring adherence to ALARA Program requirements from a design and design implementation viewpoint. ( 3.1.5.13 Initiating Maintenance Work Orders in accordance with Procedure 00350-C, " Work Request Program". 3.1.5.14 Establishing clearances in accordance with Procedure 00304-C, " Equipment Clearance and Tagging" to ensure the structure, system or component is not returned to service until the applicable design modification installation is completed, tested, applicable procedures revised, required training completed, ABNs issued for appropriate "ctitical drawings", and appropriate labeling installed. 3.1.5.15 Providing technical support when iaquasted during implementation of design modifications. 3.1.5.16 Initiating and obtaining appropriate approvals on FCRs for DCPs/SDCPs or HDDs when required. 3.1.5.17 Verifying validity and acceptability of functional test results. 3.1.5.18 Initiating ABNs when required. ( ms
'4 sRDesoWRs No. Rayssaoed pu,,s wo, VIGP 00400-C 11 9 of 33 3.1.5.19 Ensuring FCRs for DCPs/SDCPs are reviewed by the A/E pudor to. returning the associated system to service. 3.1.5.20 Verifying the modification is properly installed, properly tested, critical drawings revised, procedures revised and training completed and appropriate labeling installed prior to notifying the Manager Operations that a system / component is available for return to service. 3.1.5.21 Reviewing closure documentation for completed design modifications and transmitting closure documentation to Document Control for storage as lifetime Quality Assurance Records. 3.1.5.22 Ensuring Site Design Change Packages which affect l safety rela <.ed structures, systems or components are reviewed by the A/E prior to implementation. 3.1.5.23 Ensuring Safeguards information used in connection with modifications of security system / components is rocessed in accordance with Procedure 00650-C, p' Safeguards Information Control". 3.1.5.24 Maintaining a brief description of plant modifications ( and associated safety evaluations, as applicable, in order to cog ly with the annual reporting requirements to 10CFR 50.59(b) in accordance with Procedure 00152-C, " Federal And State Reporting Requirements". 3.2 MANAGER TECHNICAL SUPPORT The Manager Technical Support will ensure the following: 3.2.1 Processing licensing document change requests in accordance with Procedure 00402-C to support-design modifications. 3.2.2 Revising applicable Technical-Support and Plant Administrative Procedures to reflect design modifications and associated licensed document change when notified by the NES. '( ,._.s.. - - ~ ~ ~ - - - - - - - ~. - - - - - - - - - -l
~ anocaouaa wo. mnesow past wo. VECF 00400-C 11 10 of 33 [ 3.3 MANAGER OPERATIONS i The Manager Operations will ensure the following: 3.3.1 Revising applicable operating procedures to reflect design modifications and associated licensing document amenhents when notified by the MES. 3.3.2 Participating in DCP/SDCP walkdowns, when required. 3.3.3 Installing / removing plant identification tags as necessary to identify equipment / components added or removed as a result of design modifications. 3.3.4 Declaring the system / component operable and restoring it to service after notification by the MES. 1 3.4 MANAGER MAINTENANCE The Manager Maintenance will ensure the following: 3.4.1 Notifying the MES and the Work Planning Group when an installation cannot.be performed as designed. 3.4.2 Participating in DCP/SDCP walkdowns, when required. . 4.3 -Revising applicable maintenance procedures and 3 preventive maintenance procedures to reflect design -modifications and associated licensing document changes when notified by the HES. 3.4.4 Ensures design modifications which affect ASME Class 1, 2, and 3 systems or components are in compliance with the VEGP ASME Section XI Repair / Replacement Program, as -applicable. 3.5 MANAGER HEALTH PHYSICS AND CHEMISTRY The Manager Health Physics and Chemistry will ensure the following: 3.5.1 Reviewing design modifications to ensure adherence to ALARA Program requirements. 3.5.2 Participating in DCP/SDCP walkdowns, Tduen required. 3.5.3 Revising of applicable Health Physics and Chemistry procedures to reflect design modifications and associated licensing document changes when notified by the MES. ( m
anocsouns No. m Paat No. VEGP 00400-C 11 11 of 33 l s gy 3,6 FINANCIAL SERVICES SUPERINTENDENT The Financial Services Superintendent will ensure bud et account numbers are assigned to approved design mod fications. 3.7 MANAGER PLANT TRAINING AND EMERGENCY PREPAREDNESS The Manager Plant Training And Emergency Preparedness i will ensure the following: 3.7.1 Developing and conducting training programs, as necessary,to train personnel on the changes that will result from implementation of design modifications when notified by the MES. 3.7.2 Revising of applicable Plant Training and Emergency Preparedness Department procedures to reflect design j modifications and associated licensing document changes when notified _by the MES. 3.8 MANAGER PLANT ADMINISTRATION (, The Manager Plant Administration will ensure the following: 3.8.1 Maintaining Quality Assurance records associated with modifications and associated licensing" Quality document changes in accordance with Procedure 00100-C, Assurance Records Administration". 3.8.2 Assigning ABN control numbers, maintaining ABN logs, posting ABNs against control drawings, transmittal of ABNs to the Architect / Engineer (A/E) for incorporation into the design drawings and closure of ABNs following receipt of revised design drawings. 3.8.3 Distributing controlled or working copies of DCPs, MDDs, SDCPs and FCRs to support field installation and inspection activities. k l
si emoctovas wo. neviscw paos n VEGP 00400-C 11 12 cf 33 k NOTE Engineering Support will provide = a copy of the DCP/SDCP, MDD (Implementation Package) and FCRS to Document Control for use as the " original" for controlled distribution. Personnel, performing field work or inspections, must obtain a working copy of the package from Document Control. 3.8.4 Revising applicable Administration Department procedures as necessary to reflect design modifications and associateo licensing document changes when notified by the MES. 3.8.5 Processing procurement documents associated with design modifications in accordance with plant procedures. 3.9 MANAGER OUTAGES AND PLANNING The Manager Outages and Planning will ensure the following: 3.9.1 Processing of Maintenance Work Orders to implement design modifications in accordance with Administrative Procedure 00350-C. 3.9.2 Updating NPRDS and NPMIS when required to reflect design modifications. 3.9.3 Procuring stock materials for implementation of DCP/SDCP. 3.9.4 Developing, when required, implementation schedules for DCPs/SDCPs and notifying the appropriate departments of the schedule. 3.9.5 Participating-in DCP/SDCP constructability walkdowns ,l when required. ~ ^ 3.9.6 Revising applicable Outages and Planning Department procedures to reflect design modifications and associated-licensing document changes when notified by the MES. 's k. WS
PRoCECMME No. EYltWoN PAGENO. VEcP 00400-C 11 13 cf 33 3.10 MANAGER ENGINEERING, MAINTENANCE AND OUTAGE PLANNING The Manager Engineering, Maintenance and Outage Planning (SONOPCO) or designee acting as the design agent GPC interface with the Architect Engineer (A/E) will ensure the following: 3.10.1 Providing A/E engineering support for development of DCPs. 3.10.2 Providing A/E Engineering Support when requested by a REA. 3.10.3 Ensuring the A/E develops modifications in accordance with the FSAR and all applicable regulations, codes and standards. 3.10.4 Ensuring the A/E updates design documents to reflect ABNs and performs all necessary reviews for ABNs. 3.10.5 Ensuring the A/E reviews FCRs submitted for review and approval. 3.11 PLANT REVIEW BOARD (PRB) ( The PRB shall ensure the following for design modifications: 3.11.1 Reviewing proposed design modifications to safety related structures, systems or components and recommending approval / disapproval to the General Manager - Nuclear Plant. s 3.11.2 Reviewing proaosed MDDs to safety-related components / systems to maie determinations if the requested change can be processed as a minor departure from design. 3.11.3 Ensure copies of Safety Evaluations associated with safety related design modifications are transmitted to the Safety Review Board in accordance with Technical Specifications. G NN
^ i ~PMoCEDUME No. REYlSeON MhG(Pio, VEGP 00400-C 11 14 cf 33 4.0 INSTRUCTIONS AND REQUIREMENTS FOR PROCESSING RERs, DCRs, SDCRs, MDDs, FCRs, ABNs, FICRs and REAs 4.1 PROCESSING RERs 4.1.1 If technical assistance is required from the Engineering Support Department, the requester should complete Part 1 (Problem Identification) of the Request for Engineering Review (RER) form shown in Figure 1. A RER may be used for, but is not limited to, requesting an engineering evaluation, requesting technical information, or requesting a design modification. When completing the form the requester must: 4.1.1.1 Provide a system identification number and component identification number as applicable, in the space provided, to clearly define the structure, system or component in question. 4.1.1.2 Describe the problem in detail in the " Detailed Description of Problem" section. Enough information must be provided to determine if an engineering evaluation is necessary. ( 4.1.1.3 Provido recommended or potential solutions and fustification for the review of the p'roblem in the Proposed Solution and Justification section. This should include details of the benefits if a plant modification requested and an estimated cost, if available. 4.1.1.4 List any special commitments or requirements detailing the need for fulfilling the request. These may be regulatory requirements, NRC commitments, commitments to other organizations. ALARA concerns, Industrial Safety concerns, or other special circumstances. The source of a commitment should also be identified. 4.1.1.5 Provide a requested comaletion date in the space provided. This should be based on any commitments or requirements or the impact of the problem on plant or personnel safety, health and welfare of the public or plant operational efficiency. 4.1.1.6 Provide an estimated cost in the space provided, if known. 4.1.2 The RER must be reviewed by the originator's superintendent and after approval, the RER should be forwarded to the Engineering Support Department.
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'NtoCEDURE No. LEVI 8aoN PA E No. VEGP 00400-C 11 15 of 33 4.1.3 The HES will assign the RER a tracking number and send a copy to the originator with a target completion date. 4.1.4 The MES will assign the RER to appropriate personnel for evaluation and final disposition. 4.1.5 The MES will ensure the RER is dispositioned by the target completion date. The disposition must include technical justification to support the disposition and may result in generation of additional documents including a DCR, MDD, FICR, ABN, REA, MWO or other docunents. 4.1.6 A copy of the dispositioned RER will be returned to the originator with the original being transmitted to Document Control as a permanent record. 4.2 PROCESSI! ' DESIGN CRANGE REQUEST NOTE A DCR must be unit specific. If the same modification is ( to be implemented in both units, a separate DCR shall ( be initiated for each unit. 4.2.1 A Design Change Request will be generated by the MES when a design modification is required. 4.2.2 The Design Change Request shall identify the Design Objective, specify a suggested change if one is available and provide the source document (if applicable) which necessitated the change (i.e., RER, HREA, etc.). 4.2.3 The MES shall assign a DCR Control number and maintain a log to track DCRs through design development, implementation and closure. 4.2.4 The HES will determine if a DCR will be processed on site as a SDCR or if offsite desipi engineering support is required to generate a DCP. This determination will be based on the following: 4.2.4.1 If the requested design modification is complex or extensive and affects the facility as described in the FSAR, the DCR will be pr> cessed as a DCP, I 4.2.4.2 If the requested design modification is not complex or extensive or does not affect the facility as described j ( in the FSAR, the DUR may be processed as a SDCR. [ l l W5 l ~
'PUIOCEDURE No. ' REVl8CN PAGE NJ ~9 VEGP 00400-c. 11 16 cf 33 4.2.5 If a DCR is to be developed as a DCP then the DCR must be approved by the General Manager - Nuclear Plant to authorize budget expenditures. 4.2.6 The MES in conjunction with Financial Services will establish budgets and accounting charge numbers as appropriate for the DCR. 4.2.7 DCRs for DCPs will be transmitted to the Manager Engineering, Maintenance and Outage Planning or designee. 4.2.8 DCRs for SDCPs will be processed in accordance with approved Engineering Support Department procedures. 4.3 PROCESSING DCRs/DCPs 4.3.1 The MES will ensure DCPs and SDCPs: 4.3.1.1 Contain an approved Safety Evaluation and Enironmental Evaluation. 4.3.1.2 Have Licensing Document Change Request (LDCR) initiated and approved, if applicable, in accordance witn 00402-C, " Licensing Document Change Request". ( 4.3.1.3 Comply with the FSAR, applicable codes, standards, and regulatory requirements. 4.3.1.4 Contain a narrative summary detailing the design objective and method of achievement. 4.3.1.5 Are reviewed by qualified reviewers 4.3.1.6 Have constructability, maintainability, operability and i ALARA valkdowns performed by affected departments prior to implementation, if appropriate. 4.3.1.7 Adhere to ALARA program requirements from a design and j design implementation viewpoint. l 4.3.2 The MES must ensure initiation of procurement l requisitions for DCP/SDCP specific equipment / parts and I provide supporting documentation to specify procurement requirements. 4.3.3 The NES must notify the materials section when new items are added or items are made potentially obsolete by a DCP/SDCR in accordance with 00852-C. ( m,
PRoctoWIE800. RfynssoN PA'.t No. j VECP-00400-C 11 17 of 33 4.3.4 The MES must coordinate with the Manager Outages and t Planning Manager to develop an implementation schedule when required. 4.3.5 The NES must ensure the DCP/SDCP specifies functional test requirements and after implementation that the functional test results adequately verify / prove the capability of the system / component to perform its design function. 4 3.6 The MES will ensure SDCPs for safet related equi are reviewed by the A/E prior to lementation. pment 4.3.7 The MES shall ensure safet related SDCPs and DCPs are reviewed and approved by t e Plant Review Board (PRB) prior to implementation. 4.3.8 The MES will initiate Maintenance Work Orders for DCPs/SDCPs in accordance with 00350-C. 4.3.9 1me MES must establish clearances in accordance with Procedure 00304-C to ensure the structure, system or cogonent is not returned to service until the applicable design modification installation is complete, appropriate procedures revised, required training complete and critical drawings revised. ( 4.3.10 The MES will provide technical support when requested [ during Laplementation of design modifications. 4.3.11 The MES will initiate and obtain approvals on FCRs for DCPs/SDCPs when changes are required to DCPs/SDCPs after the DCPs/SDCPs has been approved for implementation. FCR aprroval shall be by the same organization which approved the original DCP/SDCP. (See Section 4.10) 4.3.12 After completion of a DCP/SDCP the NES will review all supporting documentation and verify the structure, system or compenant is ready for return to service. 4.3.13 ' For return to service, the MES shall: o as Complete a verification walkdown to ensare that the modification was implemented according to final design. ( 2.n v v o-m.w,m-,--n-m-.,- ,,--m-- .gv w m rs.-n-,,.m ,--,,-1w, w-,.-,- r..,w-
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l 'pnOCEDumt Iso. AfvitaON PAGE No, l VEGP 00400-C 11 18 ef 33 b. Verify that new procedures and procedure revisions required as a result of the modifications are approved and issued. c. Verify that ABNs or marked up drawings (TABNs) have been issued to Control Room files for affected P&ID, single-line electrical drawings, and elementary diagrams. d. Verify that training required as a result of the modification has been completed and cognizant o)erating personnel are aware of the effects of the modification. e. 'erify that functional test and surveillance test requirements have been successfully completed. f. Verify appropriate labeling is installed. 4.3.14 The MES will notify the Manager Dperations when a system / component is ready for return to service. 4.3.15 The. Manager Dperations witl return the structure, system or component to service in accordance with applicable procedures. (_- 4.3.16 The MES will verify all closure documentation and note this on the DCP/SDCP. i
- 4.3.17 After appropriate approvals, the MES will transmit the DCP/SDCP to Document Control for storage as a permanent record in accordance with Procedure 00100-C, " quality Assurance Records-Administration".
4.4 REVISING DCR/DCP/SDCP 4.4.1 If the intended scope of a DCR/DCP/SDCP increases, or j' The Scfaty Evalvetten changes afts: approval for design or implementation, the DCR vill be revised by. generating a new DCR with the original number but a new revision number. Portions of the original DCR/SDCP/DCP may be utilized in the revision but must be clearly annotated with the revision number.
+ mocEDURE No. MSbN PA.E NO. l VEGP 00400-C 11 19 of 33 ,M. 4.4.2 The old DCR/DCP/SDCP should be marked or stamped " Revised" and submitted as a'permane,t record with the revised DCP after completion of the DCP/SDCP implementation. The revision will be processed in accordance with the requirements of this procedure. 4.4.3 The revised DCR/DCP/SDCP must be approved by the same groups as the original DCR prior to implementation of the work added by the revision. 4.4.4 If a DCP/5DCP is in progress when the need for a revision is identified, the MES will determine if in-process work should be suspended until the revision 3 can be processed. 4.5 SEQUENTIAL DC'P/SDCP Portions of DCPs/SDCPs may be issued as a sequence to facilitate installation and tracking. These portions may also be revised independently so long as each page is clearly noted with the sequence number and revision level. 4.6 CANCELLING DCR/DCP/SDCP (_ 4.6.1 A DCR/DCP/SDCP which requires cancelling and has been a? proved by the GMNP will be returned to the GMNP, via tie PRB if Safety Related by the MES with an explanation of the requese to cancel, If the DCR/DCP/SDCP has not been approved by the GMNP, the MES may cancal the DCR. The DCR/DCP/SDCP is cancelled by 3 writing " cancelled" next to the last approval signature and then signing / dating. 4.6.2-For DCPs/SDCPs in progress which are to be cancelled, the NIS will ensure: s. Notification of any department manager or who received the narrative summary, that the DCP has been cancelled, b. Cicsure of associated MWO(s) and listing of each on the DCP/SDCP form, c. Coordination of restoration of the plant to the approved design configuration, d. Coordination of development and approval of functional test (s), as appropriate, to ensure that the affected alant systems / components have been i (, returned to t ae design configuration. 4 m - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ - - - - _ _ - _ _ - - - _- _ _ - - - - - - - - - - _ - - _ _ _ _ - - - _ _- - - - -. - - - - - - _ - _ - - - - - - - - - _ - - _ - - - - - - - - - - - - - ~
p meocaouRE NoJ LEVisH:W P AGE No. VEGP 00400-C 11 20 of 33 I-4.6.3 The MES will transmit cancelled DCRs/DCPs/SDCPs to Document Control for storage of in accordance with Pr.pcedure 00100-C. ^ 4.7 TROCESSING MINOR DEPARTURES FROM DESIGN (MDD) 4.7.1 A minor departure from design will be generated by the MES for design changes of very limited scope. 4.7.2 The MDD will include a detailed description of the change and the reason the change is necessary. 4.7.3 The MES will assign s MDD control number and maintain a log _to track MDDs through implementation and closure. 4.7.4 The HDD package will be assembled and processed in accordance with Engineering Support Department procedures. 4.7.5 The MES will ensure the MDD package contains an approved Safety Evaluation, PRB Review Checklist (Figure.2,), and Human Factors Checklist. 4.7.6 The MES shall ensure that all safety-related MDDs are reviewed.by the Plant Review Board (PRB) prior to
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4.7.7 The MES shall ensure thse *!1 non-safety related MDDs with a "Yes" answer on ths,4B Review Checklist are reviewed by the PRB prior to implementation, f NOTE Non-Safety Related MDDs with the answer "No" to all questions on the PRB Review Checklist. do not require PRB review prior to implementation. 4.7.8 The PKB will review MDDs submitted prior to ieplementation to determine if the change can be accomplished as a minor departure. The PRB recuamendations will be forwarded to the GMNP for approval prior to implementation. 4.7.9 The MES will initiate Maintenance Work Orders (HW0s) for MDDs in accordance with 00350-C. 4.7.10 The MES will initiate and obtain approvals on FCRs for MDDs when changes are needed on MDDs that have been approved for implementation. (See Section 4.10) 5 tc3us
PROCEDURE No. G EVIS8oN PAGE No-VEGP 00400-C 11 21 ef 33 4.7.11 After completion of the MDD the MES will r(view documentation and verify the structure, system or 3 component is ready for return to service, i 4.7.12 For return to service the MES will verify that a. ABNs are issued for posting against plant
- drawings, b.
New procedures and/or revisions as a result of the MDD are approved and issued, c. Functional tests are successfully completed. 4.7.13 The MES will notify the Manager Operations when a component / system is ready for return to service s 4.7.14 The Mantger Operations will return the structure, system or component to service in accordance with applicable procedures. 4.7.15 After reviews and approvals for HDD closure are completed, the MES will issue a Drawing Change Only DCR to Design Engineering. The HES will include the MDD package with the crawing change only DCR, ( 4.7.16 Design Engineering will revise the plant drawings and reference the MDD control number in the drawing revision block. 4.7.17 Design Engineering will notify the MES upon comaletion of the revision to plant drawings. The W D package will 'oe kept with design engineering. 4.7.18 The MES will verify that the Drawing Change Only DCR has been incorporated within one year of the MDD implementation. The one year time limit may be extended with the written permission of the GMNP and the Vice President Nuclear - Vogtle Project. (Figure 3) NOTE 1 If the MDD affects critical drawings, the MES will ensure the A/E incorporatas the revisions on a priority basis. 4.7.19 The MES will resolve any problems that the A/E may have during review for incorporation the MDD into plant l drawings. A Field Change Request (FCR) or revision to I the MDD will be used to resolve problems with the i drawing change only DCR. 1 1 12WS l l
7...-~.- .~ - - - ~ . - ~. DRoCEDUJ.E No. REVIS4oN PAgg No, VEGP 00400-C 11 22 of 33-C 4.8 -REVISING MDDs 4.8.1 I4 the intended scose of the_MDD increases or the Safety Evaluation c:1anges after the MDD is approved for implementation, the MDD will be revised by generating a new MDD with the original number but a new revision number. Portions of the original MDD may be utilired in the revision but must be clearly annotated with the revision number. 4.8.2 The old MDD should be marked or stamped " revised" and kept with the MDD package. The revision should be processed in accordance with Section 4.7. 4.8.3 If a MDD is in progress when the need for revision is identified, the MES will determine if in-process work should be suspended until the revision is approved. 4.9 MINOR DEPARTURE CANCEL 1.ATION OR VOIDING 4.9.1 Prior to implementation, if it is determined that the MDD is no longer required or needs cancelling, the MES will void the MDD by writing " VOID" on the MDD cover page and signing and dating. The MES will update the MDD log to reflect the voided MDD. ( 4.9.2 For MDDs in progress which are to be cancelled or voided the MES will ensure: a. Closure of associated MW0s and listing of each on the MDD-package, b. Coordination of restoration of the plant to the approved design configuration. 4.9.3 The MES will transmit cancelled or voided MDDs to Document Control in accordance with Procedure 00100-C. 4.10 PROCESSING FCRs 4.10.1 Field Change Requests may be used to perform the following: 4.10.1.1 Describe and obtain a aproval for any changes to DCPs, MDDs and SDCPs which :Tave been approved for implementation. 4.10.1.2 Describe and obtain approval of design information in DCPs end SDCPs submitted for review but not approved for implementation.
PROCEDURE ko. REVIStoN PAGE No. VEGP 00400-C 11 23 cf 33 NOTE FCRs associated with DCPs/SDCPs or MDDs may only be used if the FCR does not alter the inten'Jed scope the DCP/SDCP or MDD or invalidate the approved Safety Evaluation. 4.10.2 The MES will develop departmental procedures for processing FCRs. 4.10.3 Procedures for arocessing FCRs for DCPs/SDCPs or HDDs shall require tLie following: 4.10.3.1 FCRS may only be used if the change does not alter the intended scope of the DCP/SDCP or MDD or change the Safety Evaluation. 4.10.3.2 FCRs shall be approved prior to implementation by the same organization which performed the original design for the DCP/SDCP or MDD. 4.10.3.3 Verbal approval nny be obtained prior to implementation of the FCR but written approval shall be obtained prior to closure of the aosociated DCP/SDCP or MDD. ( 4.10.3.4 PRB review is required prior to implementation of the FCR if the FCR is considered major by the MES and affects safety related equipment. 4.11 PROCESSING ABNs 4.11.1 An ABN is generated by the HES to detail required changes to plant design documents, 4.11.2 The MES will develop departmental procedures for processing ABNs. Tne procedure will identify the individuale responsible for reviewing and approving ABNs. 4.11.3 ABNa are be used for, but are not limited to, the following: 4.11.3.1 Update design documents to reflect As-Found conditions. 4.11.3.2 Make changes to design documents that result from implementation of Design Modifications and minor departures from design (MLDs). 4.11.3.3 Update design documents to reflect addition or revision of plant identi ficatiott numbers on a structure, system or component, vms
MtoCED'.FdE No. LEY:SfoN PAGE No. VEGP 00400-C 11 24 of 33 4.11.3.4 Update design document to reflect additional or revised nomenclature on a structure system or component (i.e. change switch labels, annunciator window engravings, etc.) 4.11.3.5 Revise design documents to reflect equivalent parts replacement information. 4.11.3.6 Revise design documents to reflect modifications which do riot require a DCP/SDCP or MDD, (i.e. changes to ancillary buildings) 4.11.4 The MES may issue temporary ABNs (TABNs) to reflect transient plant conditions such as temporary modifications. These shall not be incorporated into the design drawings. 4.11.5 The Document Control Supervisor should ensure ABNs and TABNs on critical drawing (P& ids, one lines and elementaries) (8-1/2 x 11 size) are distributed to the control room within 24 hours of receipt. 4.11.6 Document Control will distribute ap ropriate ABNs in accordance with Procedure 00101-C, p, Drawing Control". 4.11.7 As Built Notices will remain open until Document ( Control has received revised drawings from Design l Engineering showing the ABN has been incorporated on the drawing. 4.11.8 Upon receipt of the revised drawing (s) Document Control personnel shall perform the following: a. Distribute revised drawings in accordance with Procedure 00101-C. b. Indicate that the ABN is closed, and c. Maintain the ABN as a lifetime Quality Assurance record in accordance with Procedure 00100-c. 4.12 PROCESSING FICRs hFICRisgeneratedbytheMIS.todetailrequired 4.12.1 changes to facility indices, specifically the Plant Equf.pment Index, Instrument Indez, Valve Designation List, Line Designation List, Penetration Seal Designation List or Power, Vent, Drain and Root Valve List. J ( l l m,
[ amocsounsNo, AtVmoN PA48 No. VEGP-00400-C 11 25 of 33 / 4.12.2 The MES will develop-departmental procedures for. processing FICRs. + ~ 4.12.3 ' Completed FICRs shall be transmitted to Document Control for storage as permanent records. -4.13 EQUIVALENCY DETERMINATION 4.13.1 The MES will develop procedures for performing Equivalency Determination. 4.13.2 An Equivalency Determination shall verify that the alternative item will satisfactorily perform its intended function once in service. 4.13.3 Equivalency-Determinates shall not be used to effect a change in parts or materials invoTvings a non-compliance to an A/E specification, a new design, a major material change, or a change to a system component support interface.
5.0 REFERENCES
( .5.1 Title 10CFR 50, Appendix B, Criterion III ' 5. 2 - -Title 10CFR 50.59 5.3-U.S. NRC Regulatory Guide 1.33-1978, " Quality Assurance Program Requirement-(Operation)" - 5. 4' U.S. NRC Regulatory Guide 1.64-1976, " Quality Assurance Requirements for.the Design of Nuclear Power Plants" ~ 5.5 ANSI N45.2.11-1974, " Quality _ Assurance for Design of Nuclear Power Plants" 5.6. ANSI N18.7-1976,7 " Administrative Controls and Quality Assurance for the' Operational Phase of Nuclear Power Plants" 5.7 Vogtle Electric' Generating Plant FSAR Sections 1.9.33, .1.9.64, 17.2.3, and 3.2 - 5.8 Technical-Specifications, Section 6.0 "#685
MiocsDURE No, WM-PAGE NO. i
- VEGP
-00400-C 11 26'of 33 5.9 -PROCEDURES 5.9.1 04053-C,, " Temporary Procedures" 5.9.2' 00056-C, " Safety And Environmented Evaluations" .5.9.3 .00100-C, " Quality Assurance Records Administration" 5.9.4 00101-C, " Drawing Control" 00152-C, " Federal'and State Reporting Requirements" '5.9.5 5.9.6 00304-C, " Equipment Clearance And Tagging" 5.9.7 00307-C, " Temporary Modifications" 5.9.8 00350-C, " Work Request Program" 5.9.9 00650-C, " Safeguards Information Control" 5.9.10 00852-C. "New Or Obsolete Parts" 5.9.11 00910-C, "ALARA Program" END OF PROCEDURE TEXT ( ..~
'anocsouna No. tev*oM Pace No. VEGP-00400-C 11 27 of'33 SHEET 1 of __ REQUEST POR ENGINEERING REVIEN RER NO.- UNIT 1 PART 12 Problem Identification (1) System No. Component 15o. (2) Detailed Description of Problem I (3) Proposed Solution and Justification: [ ] Personnel Safety [ ] Plant Safety [ ] Regulatory Requirement [ } ALARA* [ ] Other -(4)_ Requested Complation Dates Estimated Cost: Point of Contact Phone: Initiator / Date Department Manager / Supt. / Date Engr. Supv. Assigned Target Completion Date i.
- Copy to Manager Health Physics and Chemistry j
4 FIGURE I ~ roues
anot.aouns wo. nevocm paos wo. VEGP 00400-C 11 of 33 SHEET 2 of RER NO PART 2: Enginsedag-Support Department Review (5) Disposition: ( (' -. Safety Related No [ ] Tes [ -) i Document 1 Generated No [ ] Yes [ '] No. Eng. Manhostra Required for Review Approvals: Design Engr. / Responsible Engr. / i (if applicable) Date Date Engr. Supv. / Mgr./Y.ngr. Support / Date Date 4 ( FIGURE 1 (C0!rt'D.)
~ c.. - SEWCSOURt No. REVIssoN ~ Pall No, 'l VEGF-00400-C 11 30 of 33 Sheet 1 of 3 MDD - f REV i PRB REVIEW CHECKLIST (FOR MDD) -INSTRUCTIONS If all questions can be answered with a "No" and the MDD is non-safety related, then the minor departure may be implemented prior to PRB approval.. If any question is answered "Yes" or the MDD is safety-related, the PRB must review and approve the' MDD prior to implementation. 'If any' licensing document requires -1 changing as a result of the MDD the LDCRs associated with that change are to be included with the MDD for PRB review. All supporting information and calculations are to be included in an engineering calculation package in accordance with EngineeringL Support Department procedures. Identify the Structures, Systems, or Components involved, i-L 1. Does.the Minor Departure change the basic
- f function of the.-structure, system or
-( component involved? []Yes [}No-2. Does the Minor Departure change the function of other plant structures, systems, or-i components associated with the structure, l _ system, or component involved? []Yes []No 3. Could the Minor Departure adversely affect L the-conduct of operations of. plant programa such as: Emergency' Plan []Yes ()No Primary / Secondary Chemistry []Yes [}No-V -Radiological' Protection (]Yes []No Environmental Qualification []Yes []No. Fire-Protection- []Yes []No Security []Yes []No
- Other:
[]Yes []No- []Yes- []No- ! :(. FIGURE 2 mue -=,=.c...,
y. MtoCEDURE No. REVIS8oN PAoE No. VEGP 00400-C 11 31 of 33 1 Sheet 2 of 3 [ MDD f REV i 4. Could the Minor Departure cause degradation of performance characteristics or adversely affect operating / design parameters such as: System Pressure []Yes []No System Temperature []Yes []No System Flow and/or Capacity (lyes (lNo Voltage and/or Current Carrying Capability ()Yes []No Response Time []Yes [}No Structural Support, Stress, or Seismic Qualification []Yes ()No Materials Compatibility ()Yes []No Other: [ lyes (1No {~ []Yes []No 5. Could a failure of the structure, system or component changed by the Minor Departure result in operating in a degraded or an unanalyzed condition, or cause subsequent failure in associated structures, systems, or components? []Yes []No 6. Does tha Minor Departure deviate from established industry standards and accepted plant practices? []Yes []No 7. Does the Minor Departure require a change to the Technical Specifications? []Yes (lNo 8. Does the Minor Departure require a change to any licensing document? [ lyes
- i. ] No List applicable LDCR Numbers k-FIGURE 2 (CONT'D.)
a pnocsouns wo. nevision paag wo. VEGF 00400-C 11 32 of 33 Sheet 3 of 3 MDD i REV i 9. Does the Minor Departure deviate from identified applicable design codes? [ lyes []No [lNA List applicable codes considered: 10. Does the Minor Departure, if installed as specified, deviate from applicable installation codes and specifications? Consider material, pressure rating, support types, support span, separation criteria, size etc. [ lyes []No [INA ~ List applicable codes and specifications considered: ' Prepared By_ Date -MES Data i PRE Chairman Date-(N/A if PRB review is not required) L l-( FIGURE 2 (CONT'D.) mus ~
r- +. -] MtocEpunt No. ftFvise0N PAos No. VEGP 00400-C -11 33 of 33 MINORDEPARTUkECOMPLETIONEXTENSIONREQUEST MINOR DEPARTURE i-DATE REV $ SUBJECT INITIALLY APPROVED ESTIMATED COMPLETION DATE, PREVIOUSLY APPROVED REVISED ESTIMATED COMPLETION DATES REQUESTED ' DEVISED ESTIMATED COMPLETION DATE REASON FOR EXTENSION 4 I p SUBMITTED BY DATE L p DATE l MIS APPROVED BY DATE u usazm. muusa-uuctuR Furr APPROVED BY DATE != VICE FRESIDENT NUGLEAR-VOUILE PROJECT 3 FIGURE 3 F03mS
s PRCEtOust NO. LEvisiON PaGE No VEGP 00400-C 9 26 of 32
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""' ' b FOR IN 0RVIAT ON fMY RIR NO. O "O /'9. 7 NIT-M- ~ PART !_: Froblem Identification (1) SystemNo.hCO '\\/ Component No. k ib lbl. 9 c [_.9 C (2) Detailed Description of Problem: C "T~ g(ds, ct ]f qp_/J /3 .< t.C{ < t.1J Mw 2000 bw L es & cat,. (3) Proposed Solution and Justification [ ] Personnel Safety [ ] Plant Safet) { ] Regulatory Requirement [ ] ALARA* [ ] Other l rf M.& Y Yo _ cht J f (A) Requested Coupletion Date: 3!2 /!? ci Estimated Cr.att Point of Contact i ihm Phones 3 a y.t 0 WcuQCu 3bll9o k0m 3 2i To Initia or / Date Departadot Super %tendent / Date Engr. Supv. Assigned (1*[~) O_m Target Completion Date
- / 7C f-0 Copy to Manager Health Physics and Chemistry I
FIGURZ 1 l
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h E C. TO '/57 ) DM Chengo Notice ;823 g Dated 7 17. ,3 a. akvin w. vost6:mucasA.*LANT 4 DE$tGN BA$t5 Joe No, es t o VNP DESIGN MANUAL 3 2-W g g y._ eAtg_ StEu ho - DC-1823 gli;*RICAL PR071CTION CRITT.RIA ,,y,,_ Pinim elP AL RESPONs tBILitY-IECEIEI
- ELECTRICAL
]vgs ]wo g gigt .vstru nassericAriom Q sa esiv.skatro CsarstYsummer [otsan 1.0 PRINCIPAL TWCTION The electrical protection criterie aball serve as a guide to determine the el protection required for both Class it and non Class II electrical equipeent. This protection criteria vill cover all electrical prote protection, switchyard, transatission lines, diesel generators, and utility substation systems, sAFtTY CLASS-- 1 a art 0WIC CATEGe#Y-1, ! ng i a i 19 1 14 1 Ta 1 } - -- nd 1 ima
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3,,, w ,,3,q,-,,, .,. _ _.,,_.,,_. ~, _,_ -- - ..f 7 y - - ---~--~" ~~ -- g IFO** f,/ jo )M o g, t h O, s 4. a t. + a DN Change Notice 1823-2 Dated 7-17-8) TilP Dt31GN MNVAL DC 1823 RET 1 DATE _1-3 I_L 3.0 PaoftCTION DESIGN CRITEt h A. Electrical protection schemes shall be designed to assure as i continuity of service with alntmum damsgo to equipment. Imum will const.antly monitor the electrical system to detect ebnormal conditions protectles devices sod' automatically initiate isolation of affected equipment. 8. for solsetion and applicatlen of rolsys and other protective 1 the determination of settings for coordination of i L.- imit equipment damage and/or system disturbsnces. protective rolsys to l I C. Thn protection criteria covers requirements to prevent damage to all electrically operated equipeont. and should not to considered as protection neceanary for the esfo shutdown of the reactor. be selected from GS 1019 dated June 24, Specitte relay types shnu subsequent revisions issued by Goorgia Fower Company which are identit la persgraph 60. i D.. The alactrical protective systet. available short aircuit current such as ystens utt11 stag inverters andat:spt for will be provided:reguisting transformers shall be destaned such that the followlag fes i 1. Quickly (selste the faulted portten of the systen while astn-taintag normal service for the rest of the sleetelsal system. 2. The protective device nearest to the fault will operate (1rst with backup, by the nest protective devise la the system. 3. Itinimlae offsets of short-circuit la teres of systen dialesa. tien and damage.
- 3. -
have espah!11ty-for soottauses. eperstles-between 100 and P. - occurring withia the protettive some, sensed by the escrest shall flew to. the = relay." 4 6. Based en the above, a low voltage.breater sising telteria is issued as Attachanat A titled. Law foltage treaker si Las Criteria fee the Georgia Power company getts 1 and 8. Surte County Georgis Revleles 1. January 1, 1983. Devistles free this criteria shall only be allowed for breakers utl11:ed for asa e4fety related systems outside the sueleer island (SC8 scope) when approved by SpC.- 3.1 EAPITT Dg8 ION SA888 Proteetten for the redundant, safety related. Class 13 AC and DC power systoon shall be destgaed to alaistas loss of power to all safety-related leads during plant notaal operstlen, anticipated operattenal occurrences, and during accident conditions. -2 save.
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4 vfg Event Report No. 1-90-003 (fg,, Report: Page of Sequence of Events Chronology g 3 ~/O 3' p SITE AREA EMERGENCJ g 3/20/90 0n eut. o E M #- EST TIMELINrj 9 0900 Fuel truck entered protected area ~,2,J, f 0920 / Loss of 1A ti 2B RAT due to switchyard accident because fuel truck backed into insulator support -/,2<1 Y 0920 Unit 2 Trip - Unit stable ) Unit 1 D/G-1A started, tripped 1 mintte 20 seconds after breaker closure. PEO dispatched to investigate D/G trip, SRO dispatched to investigate sequencer, d 0921 Security Diesel started and loaded properly. 5, 7 0940 Site Area Emergency (SAE) declared due to loss of all AC power to Unit 1. /j 3 0941 A train sequencer reset and D/G 1A Auto started and tripped 1 minute 10 seconds after breaker closure. [ 0945 Core exit T/C temperature was 118 degrees F, increasing approximately 1 degree per minute. /, Ji[ 0956 Local start of D/G-1A - power to 1E Bus, NSCW and CCW pumps on A Train. Onsite power restored. /1 0957 Start initial notification of SAE using SC Backup ENN. /d 0958-NRC operations center notified of SAE. /jf,[- 1000 _ Started A Train RHR pump and pl m d it in the shutdown . cooling mode. At this time RHR 1hlet was 136 degreas F. / 1001 Page announcement to site (Site Area Emergency Announcement). 1002-Security commenced accountability. [ 1002 Security (PESB) notified by ED via communicator. /f 1005 General Office Operations Center (GOOC), Birmingham activated. // 1009 Visitors Center initial notification (Public Information), f - h e. [ A rcs N A*J f*Y'*'bt
L ? Event Report No. 1-90-003 l Report Pt.ge of_ Sequence of Events I Chronology ) 81TE AREA EMER9ENCY I 3/20/90 So n <.t. _ d 7d** ZET TIMELINE ./7 1011 GPC Public Information in Atlanta notified by Ray Harris. i t [ 1013 Completed initial notifications to Aiken, Allendale, Barnwell, SRS, S.C. (GEMA and BCEMA not notified). /[1013 TSC ENN communicator conducts roll call to test TSC equipment. jf 1015 Called GEMA on commercial phone numbers, did not transmit .. message due to confusion by comnunicators. v j'h1015 George Bockhold relieves Joh'a Hopkins as Emergency r Director.- #2 Emergency Notification form approved by ED. ( 571015 Sit Area Emer9ency downvraded to Alert. ole =e1 4 Generator maintaining load. /J 11016 Initial notification made to Burke County EMA on i commercial telephone. ~ t /)] 1017.- Alert Plant Page announcement made. t // 1020 -OSC Activated ./['1022 EOF ENN communicator test ENN equipment from Eor. L 7 1026 TSC Activated. -y7'1030 Personnel dispatched to Net Tower to relay data. J'1034 Steam generator. Primary manways secured. - M 1035 EOF Standby Status. Y d 1035-Message _f3 started by communicator in Control Room (using L p BUENN) - //11035.. GEMA received notification message #1 from South Carolina L t EPD via FAX. +;in ;;;t ennfirmaA-4ivm availlrb%te-L .j L
_ - -. _ _. _ _ _. _. ~. _ P* i Event Report No. 1-90-003 Reporti Page _ _o f Sequence of Events e Chronology SITE AREA EMERGEWCX J/20/90 J.u ne - M (ESI IIMEL1HE -/? 1038 Message #2 complete to all South Carolina Agencies. /J 1040 Initial Notification completed to GEMA. - /, J, fj 7 1042 containment Equipment Hatch bolted. 27 1046 Met Data from MET Tower building 10 meter height, 8-9 i aph; 340 degrees; Delta T = -3.0. i Ji - 1050 , Radiation monitors information received from PERMS; all normal. // 1050-Message #2 completed to Georgia. db9 1050 Message #3 completed to all South Carolina agencies. J 1055 ED departs Control Room to=TSC. ~ JI/U7# 1056 Massage f2 and #3 completsd to Burke County. ED at TSC and assumes duties and responsibilities. 20 1059 Message $3 completed to Georgine j' 1100 Briefing in TSC concerning accountabilicy. PA announcement made for non-essential personnel to leave protected arek and report to Admin Bldg parking lot. .3 1103 Containment Personnel hatch interlocks set. / / 1105 Message f4 initiated by ENN communicator in TSC using Primary ENN for both Georgia and South Carolina. J,Y.1112-Unit 2 in Mode 3. 1 ,2/_ 1116 Massage f4 completed to all agencies by-TSC ENN-communicetor. t
rt Event Report No. 1-90-003 Reports Page o f _,. Sequence of Events Citronology SIIE AREA f!MERGENCY 3/20/90 j a arch s> f 50: ESI TIMELINE /2,21 1129 Hessage 65 initiated by ENN communicator in TSC. 5 1130 Unit 1B RAT has offsite power to hi-side. /, J, f 1140 1BA03 anergized from RAT 18. 7 1140 Pressurizer manway installed. 21 1141 Message #5 completed by TSC communicator. ~ f 7 1143 All buses off of IBA03 energized. j / 1159 Train B NSCW ctarted. / 1203 Train D CCW pumps started. 23 1205 Message #6 initiated by TSC ENN communicator. M.7 1212 Message #6 completed by TSC ENN communicator. J)7 1222 TSC Briefing. 27 1225 Public Information Manager leavec EOF and returno to Visitor Contar. 8;7 1229 TSC receives status of personnel accountability. / 1231 Train B RHR pump started. 24 123S Message 17 initiated by TSC ENN communicator. / 1238 RHR Train B place in shutdown cooling mode. RHR Train A placed in recire, yy 1241 Message 17 completed to all agencies by TSC ENN communicator. /j 3 1257 1AA0Z alternate incoming breater closed to supply power from RAT 1B/ paralleled with D/G 1A.
N Event Report No. 1-90-003 Report: Page of Sequence of Events Chronology SITE AREA _EMERGERQX 3/20/90 Fev e c. 36 160; EET TIMELINE /A,1Y 1259 Message #8 initiated by TSC ENN communicator. // 1310 ED conference call to local agencies to discuss termination of emergency. /4 1313 Message #8 completed to all agencies by TSC ENN communicator. 7 1313 offsite power restored - plant in normal refueling , configuration. / 1326 49 people unaccounted for by Security. j,J,f,7 1347 Emergency Terminated 24 135b Pessage 49 (Termination) initiated by TSC ENN communicator. 2 6 1356 Message 49 completed to all agencies by TSC ENN communicator. C) 1400 News Release concerning termination of emergency. /,3 1426 offsite power (from RAT 18) supplying 1AA02 and 1BA03 with Dola shutdown. 1430 Press Conference in Atlanta. g 1545 Joint News Release to Media. 1630 Press Conference at Vogtle,
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() ' lOl - f) f m.2 2.0 HARDWARE CONFIGURATION The ERP computer system is a digital main-frame computer based
- system, It includes a Central Processing unit and associated per-ipheral equipment, input / output equipment for scanning field sensors, color CRT display consoles, and various hardcopy printers and coptern.
The computer system hardware is physically located in the following five areast
- 1. Computer Room
- 2. System Input Room
- 3. Control Room
- 4. Technical Support Center
- 5. Emergency operations Facility The hardware included in the ERF computer system was specified to meet the criteria of NUREG-0696.
The individual components of the systers are outlined in the following sections. Refer to Figure 2.1 for information concerning system locations and interconnections. 2.1 CENTRAL PROCESSING UNIT The central processor integrates, synchronizes, and controls the l unctions of all other components of the system. It is triggered by an ~" internal interval timer or external events to scan field inputs, perform algorithm calculations, and transmit the results to display devices and archival storage. The central processing unit (CPU) is the Foxboro Co. F1100C series processor refered to as the FOX 1/A computer. It is a 24-bit machine with 128K words of semiconductor RAM maln memory (expandable to 256K). The features of the CPU includes real-time clock, power fail / auto-restart, 12 levels of priority interrupts, hardware floating point, memory battery backup, and processor control panel. Also included are interface nests for asynchronous and bisynchronous communications, DMA I/O chant.els, peripheral equipment, and FOXNET communications links. A detailed description of the CPU is provided in FOXBORD document MI 812-022 included in Appendix F1. 2.2 MEGASTORE The Megastore device is a Foxboro model F2103 bulk core storage unit with 1024K word storage capacity. It is an all-electronic, random access data storage unit utilizing ferrite cores as the storage element providing non-volatile memory. 3 . READ AND DEST l 20,1 N:0RETON OYY
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_ _.__. ~.. _ _ i \\ The Monastore serves as the primary storage mediun for all pro-It is also the primar grams, data base and data (excent archival). source for system reload upon bootstrap. For programming purposes,y the l Monastore is subdivided into 4096 tracks (0-7777n) of 256 words each. All requests for data to/from Megastore are tracR oriented and handled i through the Operating System. See "Hogastore Map" included in Appendix for Megastore track assignments Track zero of Megastore is utilized to initiate Doot loads from the Megastore device. Ilhen the "D0" button is pressed on the CPU j control panel, track zero is loaded into main memory by firmware. Track zero nust contain code to initiate system reload. Refer to i Foxboro document MI 506-030 for further information about the Megastore unit. I 2.3 MOVING HEAD DISK The noving head disk subsystem is the Foxboro model F2101B Disk I Storaoe-Unit. It is comprised of a disk interface unit and two Model .9427 disk drives nanufactured by Control Data Corp. Each disk drive includes a. fixed and a removable platter with each platter containing five million bytes of storage area. The disk storage unit serves as a backup device to the Megastore and is also used to store historical data and progran source files. the ton and bottom drives are numbered drive 0 and drive 1 respectivly. For programming purposes, each platter is subdivided into 6480 tracks (0-14517,) of 256 words each. All requests for data to/from the disk storage Unit'are track, drive and platter oriented and are handled though the Operating System. Track zero of drive zero of the disk are utilized as backup Boot load devices. Fixed disk track zero is called when "D1F" is pressed and removable track zero is called when "DIR" is pressed on the CPU control panel. See Foxboro documents MI 815-010 and MI 506-020 for information on the disk subsystem. 3.4 SYSTEM TERMINAL The system terminal provides bidi; 2ctional communications between the CPU and the programmer / technician. It hao two independent parts,-a keyboard / monitor and a printer. The keyboard / monitor is the Esprit model ESP 6310 terminal. Hardcopy capability is provided via the okydata-Microline-182 printer. The system terminal is sometimes setored.to as the " programmer's.consolo" in other documentation. ~ The system-terminal interface communicates with the keyboard /- r printer over a full-duplex asynchronous communications channel at 4800 4 r. ,_.-,_,0 .,-m,r s.., v%-...., .....-,-__,_._.._.-._..,.,.,.._.,._._m ,_,.,_,....._,m-
)aud. In the ERP computer system, a " control-B" keystroke combination is used to generate a manual intorrupt to facillitate operator innut. See Section 3.5 - Programmer's Console for use of the system terminal and Foxboro MI 812-022 for more information. 2.5 UTILITY PRINTERS The utility printers provide hardcopy logging and report cap-ability. The Vogite ERT system includes two Centrontes model 704 dot-matrix printers. Output to the utility printers is accomplished through the Foxboro model F6321 Character Output communication flodule which provides ports for up to eight printers. Refer to Foxboro document MI 813-020 for more information on the character output communication module. 2.6 LINE PRINTER The line printer is the model F7403A supplied by Foxboro (the printer is manufactured by Dataproducts Corp. under the model number 2230). It is a 132 character per line, 300 lines per minute printer. Communication with the printer is through the line printer synchronizer in the peripheral interface nest. It operates in a Direct Memory Access (DHA) mode. The line printer included in the Vogtle ERP system is used primary in software development to generate program listing. It may also be used for recort generation and logging. For more information on the lineprinter/inserface, refer to Foxboro documents MI 815 030 and MI 503-023. 2.7 FOXNET CO!!!!UNICATIONS NETWORK The Foxnet Communication's subsystem provides high-speed data communications between equipment of the ERF computer system. The subsystem consists of stationu, Linkports (LP), Link Control Stations (LCS), and the interconnecting coaxial cable system. The station types used in the Vogtle ERF. computer system include UIO, UFM, AIM, and UMttIs. Each station-type is discussed in following sections. 2.7.1 FOXNET CONFIGURATION The Foxnet subsystem may'be operated in one of two basic config-urations: Cluster or Linked Cluster. The ERP computer system normally operates using the Linked Cluster configuration. Refer to Figure 2.2 for configuration diagram. 4 . =.
Each Linkport supports up to ten stationn (masters or slaves). In the Cluster mode, the Linkoort supports connunications between the Stations. The Cluster is the basic building block of the network. The Linked Cluster confiouration allows communications cotween multiola Linkoorts. This confiquration uses coaxial cable to link the LP's which may be located in different areas into a conmon connun-ications network. Data connunication is via Link Interface Units (LIU's) located in the LP's and is controlled by the Link Control Station (LCS). The LCS consists of a noden and a microproccessor based controller. It arbitrates contention..nong network LP's for control of the link, and disconnects any master station that holds the link beyond a 100ns tino period. 2.7.2 FOXNET COAXIAL CABLE SYSTEM The coaxial cable systen connects the LP's and LCS to torn the network. It consists of the main (trunk) cable, terminators, couplers, and drop cables. The trunk cable in the ERF systen is a 13,000 ft buried coaxial cable run extending from the computer room in the power block to the EOF in the sinulator building. Tho drop cables connect the LP's/LCS to the trunk cable via couplers. The trunk cable is terninated on each end with a cable end tone generator. Each LP and LCS constantly nonitors the health of the cable Jystem. The LP/LCS sense a cable break by detecting the loss of either or both of the two cable end tones. If the LP detects a cable break, it drons into the cluster mode and will communicate only with it's own ten stations. Communications between LP's is impossible. Likewise, if the LCS if off or disabled, communications between LP's is impossible. 2.7.3 FOXNET SUBSYSTEM OPERATIONS When a naster station initi&tes a transaction, it issues a link request signal to the LP. When the link is available, the LP issues a link grant signal to the requestinq master, which then becomes the link master. The link master can send control information and/or data to slave stations and other masters. All stations on the conmunications link are addressable. Each LP has a unique address and each LP port address is fixed by position fron 0 to 9. In a Linked Cluster network, the LP has an LIU to transmit and receive messages over the Foxnet coaxial cable systen. A distinct tone frequency is transnitted over the link by the LIU when a naster station requests to be link master. The LCS sequentially monitors the link request tones from all LIU's on the link. Upon detecting an active tone and an inactive link, the LCS grants control of the link to the requesting master station. After the master completes its transac-tions, it releases the link by removing the request tone. c
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2.7.4 FOXNET LINK PROTOCOL The protocol used within the network for station-to-station communicatior,s is based on a request / reply, half-duplex operationa scheme similar to SDLC (synchronous data link control) protocol. Only master stations may initiate a link operation. A link master initiates a link operation by sending a request frame. All such requests result in a reply from the addressed station unless the request was made in the broadcast mode. Receipt of a reply or issuance of a broadcast command by a link master constitutes a transaction. A series of transactions by the same link master constitutes a link operation. The Foxnet protocol supports multimaster operations, but only one station may be link master at a particular time. 2.7.5 FOX 1/A FOXNET INTERFACE The Foxnet process communicatons link interface nest provides foub data communications channels between the FOX 1/A CPU and the LP's. Each port can operate in either a slave or master modo as directed by the CPU. The port provides network interlock and security signals, handles handshaking operations, and effects the transfer of data into and out of the station. The process communications link interface provides the translation of 8-bit parallel data from the linkports to a 24-bit word for use on the CPU buses. The interface operates in a DMA mode. All communica-tions between the interface and the LP's follow Foxnet timing and protocol requirements. 2.7.6 FOXNET REDUNDANCY The Vogtle ERP computer system is supplied with two identical Foxnet communications networks. All_Foxnet stations in the ERP system, i including the CPU interface are dual ported to allc9 communications over either network. Each of the two communication links, refered to as links "A" or "B", is capable of supporting all ERP stations. To-minimize link loading, both links are normally used simul-taneously. Each Foxnet device is assigned a primary link for commu-nications. Should either link fail, all devices assigned to that link would be addressed on the remaining link. If both Foxnet communications links were to become disabled, the ~ERP system would still be able to operate in the Cluster mode._ The CPU, UFM, UIO, AIM, and the UMMI's located in the control room are all attached to the same LP. Thus communications between these devices is _possible in the Cluster mode. However, communications with the TSC and EOF would be immpossible. -Refer to Figure 2.3 for Linkport station assignments.
'], i LINKPORT PORT DEVICE GPC DEV # S3 LINKPORT 0 0 UFM 23 0 1 -SPARE-24 1 l 2 UIO 25 2 3 AIM 26 3 + 4 UMMI 17 4 l 5 UMMI 20 5 6 -SPARE-6 7 UMMI 16 7 8 -SPARC-21 10 9 CPU 22 11 LINKPORT 1 0 UMMI 10 12 1 UMMI 11 13 2 UMMI 12 14 3 UMMI 13 15 4 UMMI 14 16 ~ 5 -SPARE-15 17 6 -SPARE-7 -SPARE-8 -SPARE-9 -SPARE-LINKPORT 2 0 -SPARE-1 (UMMI) 1 24 2 (UMMI) 2 25 3 (UMMI) 3 26 4 (UMMI) 4 27 5 (UMMI) 5 30 6 (UMMI) 6 31 7 (UMMI) 7 32 i 8 -SPARE-9 -SPARE-i FIGURE 2.3 FOXNET/LINKPORT STATION ASSIGNMENTS i
1 For moi? information on Foxnet communications, refer to the following Foxboro documents: TI 821-002 FOXNET COMMUNICATIONS SUBSYSTEM TI 821-004 FOXNET PROTOCOL MI 813-050 FOX 1/A FOXNET INTERFACE 2.8 UNIVERSAL MAN-MACHINE INTERFACE The Universal Man-Machine Interface (UMMI) is the primary means of interactive communication between the ERP computer and the user. It is-a free-standing console that includes a 19-inch video display monitor and a desk top operator keyboard. The UMMI may also be equip-ped with a 64-button annunciator keyboard. The UMMI is also refered to as the FWS1-FA Series-FOX 1/A Color Console in certain Foxboro doc-umentation. The UMMI is compatible with the Foxnet process communications link. It is dual-ported and operates as either a slave or a master station when linked to a FOX 1/A host system. The UMMI includes a microprocessor based controller to hand.le display and network commun-ications tasks. When the UMMI is powered up/ reset, it sends a broadcast message over Foxnet Port A to request initialization from a host (the CPU in the ERP system). If the message is received by the CPU, a request is y sent back-to place the UMMI in the initialized state. Upon successful initialization, the CPU will LOG IN to the UMMI and become it's host. Should-the initialization request not be answered after thirty seconds, the UMMI will repeat the broadcast on Foxnet Port B. The UMMI will continue to issue the request on alternate ports until it is initial-ized. The-UMMI normally operates as a slave station. The CPU, acting as master, issues-display commands to be carried out by the UMMI. The UMMI assumes the master status upon active function key hits to trans-for the appropriate information to the CPU for-action. Tranfer'of overlay insertion / removal are also UMMI master functions. Each overlay is coded with an specific I.D. which is passed to the CPU. Each UMMI contains an. internal Watch Dog Timer (WDT) to monitor communicatations with the host computer. The WDT is refreched period-ically by commands-from the CPU. Should the UMMI WDT not be refreshed before~it expires, the UMMI_ assumes a loss of communications with the CPU. The UMMI will then clear all foreground characters of the current display and sound the internal audible alarm to inform the user of communications failure. The UMMI must be reset either manually or from the CPU (via BOOTSTRAP) to restore communications. r
a, For more information on UMMI consoles, refer ~to the following Foxboro documents: MI 814-024 - FWSI-FA SERIES FOX 1/A CONSOLE MI 814-028 - FUNCTION KEYBOARD AND ANNUNCIATOR PANEL DRAFT REV B UMMI UNIV MAN MACH INTERFACE 2.8.1 COF UMMI ACTIVATION -The Emergency Operations Facility (EOF) presents some unique problems in the implementation of UMMIs. The EOF is normally used as a classroom and is set up only when necessary. All equipment used in the EOF, including the UMMIs, is stored in an adjacent room until needed. Thus,.the UMMI cabinets in the EOF have been fitted with castors to facilitate movement. To provide flexibility in the location of the consoles, ten panels with military-type quick connectors have been installed corresponding to the toi linkport stations. These panels include plugs to attach to, either thu Unit 1 or 2 ERP system. Thus, when the EOF is ac.tivated, the UMMIs will be rolled out, attached to the appropriate station panels, and powered up. The UMMIs are then initialized by the CPU. The VEGP Emergency Planning personnel requested the capability during an accident situation to take three of the UMMIs from the unaffected unit and implement them into the affected unit's ERF com-puter. This places seven UMMIs.in the EOF on one system. This repre-sents a significant ir.eresse in the scope of the EOF and came rela-tively late in the software development phase. Thus, because of software restrictions, a maximum of seven UMMIs may be implemented in each unit's EOF at any one time. The normally active stations will be ports one.(1) through seven (7). Ports 0, 8, and 9 may be utilized by changing station-software addresses in the Operating System but the total number of stations must not exceed seven. The above design goes by the common acronym MUFF (Mobile UMMI Force Facilitation). 2.9 UNIVERSAL FIELD MULTIPLEXER The Universal Field Multiplexer (UFM) is a remote field data acquisiton subsystem which inputs thermocouple, RTD, millivolt, and high level data to the.Foxboro computer. It communicates to the CPU via the Foxnet communications network. The UFM operates only as a slave station. r y. .,_e...,.,-,_----,_,r ...,._,__.,m.. --,,,.,_-,_m-.f-.-y
.. _ _ _.. ~ _ _ _ _. _ _ _ _. _ _. _. _.. _. _ _ _ _ _ - - + The UFM contains control logic which compute's linearized temp-eratures for thermocouple and RTD inputs. These results, along with millivolt and volt data, are updated in UFM memory once a second. The UFM can process a maximum of 768 analog inputs. The data is available to the CPU on request. The. CPU requests UFM status and data according to Foxnet protocol. The UFM is dual-ported and may operate on either Foxnet communications port.. For more information on the UFM, refer to Foxboro documents MI 200-314 and MI 200-318. 2.10 ANALOG INPUT MODULE The Analog Input Module (AIM) is the Foxboro Company Model 2DNA-C subsystem. The AIM accepts up to 48 analog input values and transmits them to the FOX 1/A on command via the Foxnet Communications network. The AIM provides 100 ms resolution fast scan capability. The AIM is currently only used in the ERT system for start-up testing. For more information on the AIM, refer to Foxboro documents TI 200-305 and MI 200-354. 2.ll: UNIVERSAL INPUT-OUTPUT SUBSYSTEM The Universal Input-Output Subsystem (Model 3 FIB) allows the FOX 1/A to read and change process signals tt or from field devices. The communications path between the UIO and the FOX 1/A is provided by the Foxnet communications link. The subsystem consists of two functional elements: a Universal Input-Output _ Module and a process interface. The UIO module controls the transfer of field values between the input-output components and . the_Foxnet system. The UIO module is dual-ported. The process interface consists of up to 30-I/O components which enable the subsystem to interface a variety of field signals to the processor. The I/O components provide termination, conditioning, and temporary storage of the signals flowing to and from the process devices. - Accommodation of specific signal types is ef fected by sel-ecting and inserting the appropriate I/O components into the subsystem. For more information on the UIO subsystem, refer to Foxboro document MI 200-358. b .-.......-...wm --..w .,,-..,,.c.# ,,,-m._ g e pm-,,3_%, -n.,wp> ,-.p,y -.,-,-yi--w,-,, y--w.. ..,,v-y,--,,,v,.
2.12 SEQUENCE OF EVENTS RECORDER ~ The ERF computer system is equipped with a Rochester Instruments Systems'Model RA-2800 Sequence of Events (SOE) recorder. The SOE provides contact status and real-time sequence of occurence of digital inputs. Time-tagging is provided to one millisecond resolution. The SOE monitor is equipped with an RS 232-C communications port through which is sends change of state i nformation to the FOX 1/A computer. This port is linked to the CPU's asychronous communications port by two IDS Model 6220 short haul modems. Data transfer is at the rate of 4800 baud. The SOE monitor is set to transmit any contact closure as " ALARM" and open contacts as " NORMAL". This provides actual contact position to the CPU which then determines true " ALARM / NORMAL" conditions. Data is normally sent to the CPU only on a contact change of state. The SOE will send a summary of all points currently in alarm on CPU Bootritrap or on demand. I t 7 q ,m .-~,, - -..., - -.. ,,nmn.-..-,-w.n--, urw.w.,w>. n..-----.n.-,--,.-m. ,-,.-m.nns,v.,m_w ,,w,. ,e,- ,,.a w w..,,--,,,,wwe,w--*
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For a c:mplete descriptien of the hardware and sof tware desf.'Jr., see Appendix G.
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, 4- - b#i/e t or 2 wemWm0N ON 3' S O DATA snEET 3 . VENDOR. DOCUMENT STATUS SHEET !:, ?e en c jj LOG No..M M N I-d YNM REVISION _ DOCUMENT.. TITLE: 9/#4. e 4 d,t>#r247792 /A/67#~ ad72#s / Mud .... ~. = VINDCR 3 A N bth'.AU.r'.N. F.0. _. DATE MCEIVED I e') 'l 3 5 d DOCUMENT LECIBLEt TES No ...,,,J. IF NO IS CNICKED. THE RESPONSIBLE REVIEWER SHALL DS,TIMf1NE IF THE DOCUMENT CAN BE USED IN ITS FRESENT CONDITION. IF IT CAN, THE NORMAL REVIEW CONTINUES. IF IT CAN NOT, TNF DOCUMENT MUST SE'- RETURNED TO DOCUMENT CONTROL FOR REJECTION HACK TO THE VENDOR. O - DISCIFtI = =v1= = UI= =
- A= C=E MAINTENANCE N 1 AFFROVID FOR PLANT USE OPERATIONS
[] 2 REVISE AND USUBMIT. VENDOR MAY FROCH D M ENGINEERING WITN MANUFACTURE SUBJECT /~ TO TM INCORPORATION [} NEALTR FNTSICS OF CNANCES INDICATED [] CRIMISTRY [] 3 REVISE AND USUBMIT. MANUFACTURE MAY NOT i PROCHD t [] OTHE_R [] 3 SUFERSEDED BY,_, -[] V VOID l DCNs INCORF0_ RATED: (IF AFFLICABLE) l Alff'%d, Efb$sz2l DATES 1 W lj -4. NAME OF M3F. D
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w:5 u t,:- TransamenOS e ne,",,"... 'e"no,n. o'$ 'ac o* .....on Delay 3l enero,. w., a abuen. . \\p-.. P O Bon 2161 e e, 8 T 8i Oakland. Caktornia 94621 (415) 577 7400 100 vw. tv1 A N LJ A L. CHANGf2 No. 7 G C 2 1 ~ 'D DATE: ,09 GEpiEMDER1986 MODEL: DSRV-16-4 DIEGEL/ GENERATOR GERIAL N0(E): 76021-2071, 76022-2072 76023-2073, 76024-2074 CUSTOMER: GEORGIA POWER COMPANY AFFECTED MANUALG INSTRUCTION MANUAL, VOLUME I CHANGE: Replace page 11 with new page provided. REASON FOR CHANGE: To correct the fuel injection point. O DjitrtDvtlen Custcaerr 03) Servlee 12) File U) v c b
\\ t O ~ Instruction Manual For Model DSRV-16-4 Diesel Engine / Generator Serial Numbers 76021-2871 76022-2872 76023-2873 O 7eo24-2874 Manufactured For: Georgia Power Company Alvin W. Vogtle Nuclear Plant P.O. No. PAV 481 & 6-20 Date Of Issue Manufactured By Transamerica Delaval Inc. Engine and Compressor Division O 550 85th Avenue, P.O. Box 2161 Oakland, California 94621 Phone: (415) 577 740CVTelen: (47) 33-1304/Cate Entertound L.
4 O ~ Transamerica ~ Dela~ val m-m seu ums 1 instruction Manual O Model DSRV 16 4 Diesel Engine / Generator Serial Nos. 76021 2871 l 76022 2872 76023 2873 76024 2874 Georgia Power Company Alvin W. Vogtle Nuclear Plant I 1 Transamerica Delaval nc. O Engine and Compressor Division u m
.,w - w,, ry instruction Manual u ENGINE DATA t MODEL............................... DSRV-16-4 i SERIAL NUMBER (B>.................... 76021-2871, 76022-2872 i 76023-2873, 76024-2874 l FUEL................................ DIESEL TYPE INSTALLATION................... STATIONARY CONFIGURRTION....................... VEE NUMBER OF CYLINDERS................. 16 SORE................................ 17 IN. STRONE.............................. 21 IN. CYCLES.............................. FOUR SM P................................ 223.7 PSI RATED HORSEPOWER.................... 9694 i RATED SPEED....................'..... 450 RPM ROTATION............................ CLOCMWISE WHEN VIEWED FROM i FLYWHEEL'END-1 -STARTING-SYSTEM.................... PILOT AIR, GEAR DRIVEN DISTRIBUTOR FIRING ORDER........................ 1L-SR-4L-5R-7L-2R-3L-6R SL-1R-5L-4R EL-7R-6L-3R DISPLACEMENT PER CYLINDER........... 4766.6 CU-IN. TOTAL DISPLACEMENT.................. _ 76,266 CU-IN. FLYWHEEL DIAMETER................... IN. FUEL INJECTION TIMINS............... _ RIGHT SANK 210-(12.46 IN.)ST; LEFT SANK 220 (13.05 IN.) BT; FUEL INJECTION ~ PUMP RACM........... SEE ENEINE NAMEPLATE VALVE CLEARANCE..................... INTAME & EXHAUST:- O.040 IN.. NOTER: REFER TO ENSINE NAMEPLATES - FOR FIRING ORDER AND FUEL PUMP ; RACMiSETTINGS AT FULL i.OAD. REFER TO APPENDIX X FOR COPIES OF THE FACTORY TEST LOGS.- t-ALWAYS INCLUDE. SERIAL NUMBERS WHEN COMMUNICATING WITH TRANSAMERICA DELAVAL INC.,= ENTERPRISE ENGINE DIVISION CONCERING ENGINE PERFORMANCE. 4 t E' Ff" e-v m w'* -e w ou ew w- + ppew w-a*Pse-NMw-=o
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EMt.nt,#1NL ede (Wasa ~ 1 y', 4 L r. JO!NT NEWS RELIA 38 Oflb]-tyg sergio Powar Co:pany (GPC) Tederal tser5ency Hanegacant Ageney(PDu) No.: JNR-l Georgia teergency Managesent Ageney(CDM) Ca. Dept. of Natural Resources. Datei t}WhO lavisonmental Prote2ttom Div. (DNREFD) Veuth Carolina tsargetty/ Tigge1 ~$ V e g Freparedness Division ($CDE) lavannah liver Plant krhe County Aiken County j laravell County Allendale County An emergency at the Vogtle Electric Generating Plant near l Waynesboro was ended at 1:47 p.n. EST soday. Both units era shut j down, and the plant is stable, There has been ne release of radioactive material. At no time was the public in any danger. A Site Area Emergency was declared at 10:00 a.m. EsT today when a construction vehicis backed into a power pole in the plan't's switchyard, resulting in a lose of on-site and off-site I electrical power to Unit 1. site Area Emergency is the second most l serious emergency classification. The event was downgraded to Alert status at 10:30 a.m. tat, after a backup diesel generator restored power to essential plant systems. No one was injured Ma a result of the incident. i A site Area Emergency is declared whenever on-and off-site power la lost for more than 15 minutes. At the time of the incident, Unit I was off line for a scheduled re-fueling outage. Shortly _after 10 a.m., non-essential plant personnel.were assembled and' accounted for in accordance with emergency operating procedures. There were no evacuations of personnel, Unit 2 tripped off line due to power fluctuations associated i l with Unit li however, Unit 2 did not experience a loss of electrical power. Unit 2 remains shut down. l L 6#4 ' Contacts Cindy Theiler 1-800-262-1696 or-(404) 526-7676
c' COPY ** COPY ** COPY ** COPY ** COPY ** COPY ** COPY ** COPY ** COPY ** COPY NUCLEAR PLANT MAINTENANCE WORK ORDER (CONTINUED) (3 OF 4) CONTROL NO. 19001576 00 g p, j, WORK INSTRUCTIONS: CAUTION ALL PERSONNEL INVOLVED IN THE TESTING MUST READ AND UNDER-STAND THE ATTACHED CAUTION STATEMENT. DURING THE ENGINE START AND SUBSEQUENT TESTING IF ANY TRIPS OCCUR OTHER THAN PLANNED TRIPS OR QBSERVE OTHER SIGNIFICANT MALFUNCTION, STOP THE TEST AND NOTIFY IIT TEAM. TEST WILL NOT CONTINUE WITHOUT THE CONCURRENCE FROM IIT TEAM MEMBER. ANY PORTION OF THE TESTING THAT COULD IMPACT THE RELIABILITY AND SAFETY OF THE D/G SYSTEMS MUST BE EVALUATED BY GA POWER CO:4PANY PRIOR TO TFSTING. IF A TEST NEEDS TO BE STOPPED, ENSURE ALL EQUIPM ?T IS PLACED IN A SAFE POSITION. fiERFORM ENGINE LOGIC TESTING PER PROCEDURE 27563-C, REV 2. COOPER ENERGY SERVICES PEPSONNEL WILL DE PERFORMING APPLIC-ABLE PROTIONS OF THE PROCEDURE WITH ASSISTANCE FROM GPC PERSONNEL, AS REQUIRED. THE ELECTRICAL PORTIONS OF THE PROCEDURE NEED NOT BE RETESTED. ADDITIONAL INSTRUMENTATION MAY BE CONNECTED BY TEST PERSONNEL TO AID IN TROUBLESHOOTING ANY INSTRUMENTATION CONNECTED OR LDIUSTMENTS MADE SHALL BE DOCUMENTED COMPLETE ON THIS MWO. DOCUMENT ANY PROBLEMS ENCOUNTERED WHILE PERFORMING THIS TEST. ~ NOTE: PRELUBE THE TUROCHARGER FRIOR TO EACH START. TURN ALL 3 VIEDO CAMERAS AND RECORDERS TO RECORD THE ANNUNCIATORS ann OTHER ENGINE & GENERATOR PARAMETERS. 5TEP 1: FOLLOWING THE LOGIC TEST THE ENGINE WILL BE STARTED IN THE EMERGENCY MODE AND A LEAK TEST PERFORMED ON THESE LINES. E-10A - TRIP LOW PRESSURE LUBE OIL B C E-16A - TRIP HIGH TEMPERATURE JACKET WATER B-C- E-68 - TRIP HIGH PRESSURE CRANKCASE E-92 - TRIP LOW PRESSURE TURBO OIL E-14 - TRIP LOW PRESSURE JACKET WATER E-23H - TRIP HIGH VIBRATION E-19 - TRIP HIGH TEMPERATURE ENGINE BEARINGS E-18 - TRIP HIGH TEMPERATURE LUBE OIL. AFTER RECONNECTING THE LINES FOLLOWING THE TEST, PERFORM LEAK DETECTION BY SNOOP DETECTOR AND FIX ANY LEAKS. ~ TEST FOR LEAKAGE BY DISCONNECTING TUBING AT CONTROL PANEL BULKHEAD AND CONNECTING PNEUMATIC BUBBLE TESTER. OBSERVE TESTER FOR AIR FLOW WHEN LINE IS PRESSURIZED. RESTORE TUBING CONNECTION AT BULKHEAD AND CONTINUE WITH NEXT INSTRUMENT LINE. 5 TARTING TIME BETWEEN EACH START MUST BE AT LEAST 10 MIN. l RECORD THE TIME IN WORKORDER.
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' !.TCLEAR PLANT MAINTENANCE WORK ORDER (CONTINUED) (4 OF 4) CONTROL NO. 19001576 00
PRIOR TO PERFORM MULTIPLE START TURN BOTH AIR COMPRESSORS OFF AND NOTE IN WORKORDER.
AFTER THE MULTIPLE START IS COM WORK INSTRUCTIONS: PLETED TURN THE AIR COMPRESSORS ON & PLACE IN AUTO AND RECORD IN WORKORDER. NOTE THE STARTING AIR PRESSURE AT THE BEGINNING OF EACH MULTIPLE START ann AFTER EACH STOPPING / TRIPPING. STEP s2 NORMI L START -TRIP BY HI-TEMP LUBE OIL 5TEP #3 LOSP START (JUMPER IN GEN CONTROL FANEL 211 TO 213) -TRIP BY HIGH VIBRATION STEP #4 NORMAL START ! TRIP BY HIGH PRESS CRANKCASE 5TEP $5 SI START (JUMPER IN GEN. CONTROL PANEL 204 TO 209) -TRIP BY 2 OF 3 L. O. PRESSURE XFTER RECONNECTING THE LINES FOLLOWING THE BUBBLER TEST PERF ORM LEAK DETECTION BY SNOOP DETECTOR AND FIX ANY LEAKS. ~ NOTE THE AREA OF TESTING LHALL BE ROPED AND ENTRANCE LIMITED TO ESSENTIAL PERSONNELAS DETERMINED BY COOPER REPRESENTATIVES AND GPC ENGINEERING. GPC ENGINEERING SHALL BE PRESENT FOR ALL TESTING AND QC REPRESENTATIVE PRESENT AS REQUIRED. e l l l 5
? O IMPORTANT EXTREME CAUTION MUST BE TAKEN TO ENSURE THAT THE WORK PERFORMED BY THIS MWO DOES NOT IN ANY WAY CAUSE A LOSS OF INFORMATION CONCERNING THE CAUSE OR CAUSES THAT LED TO THE TRIPS OF EDG 1A ON MARCH 20,1990 OR THE LOW JACKET WATER PRESSURE AND LOW TURBO OIL PRESSURE ALARMS FOR EDO IB ON MARCH 23,1990. CARE SHOULD BE TAKEN TO PRESERVE THE AS FOUND CONDITION OF REPLACED COMPONENTS ' (E.G;, PREVENTION OF DAMAGE DUE TO JARRING OR DROPPING), AND TO CAREFULLY DOCUMENT ANY ABNORMAL OR UNUSUAL CONDITIONS THAT COULD POTENTIALLY AFFECT COMPONENT OPERATION. ALL TESTING OR CALIBRATION ACTIVITIES SHOU D BE CAREFULLY OBSERVED L AND ANY ABNORMAL OPERATION OR MALFUNFTION OF EDG PARTS SHOULD BE CAREFULLY AND THOROUGHL? DOCUMENTED. '}}