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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20035F5601993-04-0505 April 1993 Rev 5 to Inservice Insp Plan (ISI-P-014) for Vogtle Electric Generating Plant,Unit 2 ML20035F0721993-03-22022 March 1993 Rev 7 to Inservice Test Program (ISI-P-008) for Vogtle Electric Generating Plant,Unit 1 ML20035F0731993-03-22022 March 1993 Rev 4 to Inservice Test Program (ISI-P-106) for Vogtle Electric Generating Plant,Unit 2 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20092G7441992-02-20020 February 1992 Undated Draft Site Safety Manual. Supporting Documentation Encl ML20092F7091992-02-19019 February 1992 Instructions GEK-45405B, Differential Voltage Relays Types: PVD21A,PVD21B,PVD21C & PVD21D ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20129J2961991-09-13013 September 1991 Rev 3 to Procedure 23985-1, RCS Temporary Water Level Sys ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20129H6151991-03-20020 March 1991 Rev 7 to Procedure 10004-C, Shift Relief. Supporting Documentation Encl ML20129J0311990-09-18018 September 1990 Rev 4 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20113G6141990-05-15015 May 1990 Rev 0 to VEGP-22981-C, Calcon Pneumatic Temp Sensor Calibr 1TSH-19110-1TSH-19119,1TSH-19146,1TSH-19153,2TSH-19110- 2TSH-19119,2TSH-19146 & 2TSH-19153. Supporting Documentation Encl ML20113G6051990-05-0808 May 1990 Rev 3 to 14210-2, Containment Bldg Penetrations Verification - Refueling ML20034C1061990-04-26026 April 1990 Rev 4 to Inservice Insp Program First 10-Yr Interval ML20129H9081990-04-16016 April 1990 Rev 3 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20113G3421990-04-0404 April 1990 Procedure T-ENG-90-016, DG1A J.W. Temp Monitoring & Recording ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20092F8621990-03-28028 March 1990 Rev 1 to Procedure T-ENG-90-11, A-Train Undervoltage Test ML20092F9691990-03-28028 March 1990 Rev 0 to T-ENG-90-15, Unit One Train a DCP 88-V1N0070 Sequencer Functional Test. Supporting Documentation Encl ML20092F7521990-03-27027 March 1990 Rev 20 to 13145-1, Diesel Generators ML20092F8741990-03-26026 March 1990 Rev 3 to Procedure VEGP 00053-C, B-Train Undervoltage Test ML20092F8481990-03-25025 March 1990 Rev 2 to Generator & Engine Control Panel Functional Test Procedure 27563-C, Power & Signal Removal/Replacement Data Sheet ML20092H0391990-03-23023 March 1990 Rev 16 to VEGP-10000-C, Conduct of Operations ML20092F5271990-03-21021 March 1990 Data Sheet 1 to Rev 12 to VEGP-10006-C, Reactor Trip Rept. Supporting Documentation Encl ML20092F7341990-03-19019 March 1990 Rev 16 to Procedure 25717-C, Torquing Electrical Type Connections 1998-05-25
[Table view] |
Text
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l Apprcui I
erx.ouro no.
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vogtl] Electric Generating Pl:nt A
10013-C
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q NUCLEAR OPERATIONS
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unit COMMON 0
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WRITING EMERGENCY OPERATING PROCEDURES FROM THE WEJTfNGHOUSE EMERGENCY reb 70H5E GUIDELINES p
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1.0 PURPOSE In conjunction with 10012-C, "EOP And AOP Writers Guide", this procedure will be used to convert Westinghouse Emergency Response Guidelines (ERGS) into Vogtle Emergency Operating Procedures (EOPs).
Revision 1 of the ERGS will be used to generate Revision 0 of the E0Ps.
As changes to the ERGS are received or as plant operating experienca dictates, the E0Ps will be updated per this procedure.
2.0 MECHANICS OF CONVERSION The ERG-to-EOP conversion process consists of the following phases:
a.
Preparation Phase, b.
Generation Phase, c.
Documentation Phase.
The Generation and Documentation Phases procede concurrently.
In this procedure, the word " step" refers to high level action steps, notes, and cautions.
2.1 PREPARATION PHASE Obtain and review the following informati(a a.
Westinghouse ERG-HP, Revision 1 Guidelines and Background Documents for the Revision 0 EOP generation.
Thereafter use the latest ERG materials, b.
10012-C,"EOP And AOP Writers Guide",
pO 9202200420 920116 PDR ADOCK 05000424 i
S PDR wna
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Final Safety Analysis Report, d.
Technical Specifications, e.
Plant Drawings, f.
Plant-specific setpoint/value documents, g.
Licensing Commitments, h.
Industry or plant operating experience, i.
EOP validation comments.
This list is the minimum amount of information to be used: other pertinent sources of information should be consulted.
2.2 GENERATION PHASE The ERGS list in generic terms the actions which catimize operator response to emergency conditions in the reference alant.
To be used in an operating unit, the ERGS must ie niade plant-specific to that unit.
The writing of an EOP will be done per these
( )
guidelines:
a.
Read the ERG to be converted, and ite corresponding background document, b.
Convert ERG steps to E0P steps by inserting plant-specific information derived from sources as given in Subsection 2.1 of this procedure, and in accordance with 10012-C, "EOP And AOP Writers Guide",
c.
Add, delete, or alter the ERG step as necessary to conform to plant apecific documents specified 'n Subsection 2.1 of this procedure.
The intent or aurpose of the ERG Background Documents should not 3e affected by these modifications, d.
If revising E0Ps from a Unit 1 design to a common unit design, applicable Unit 2 documents specified in Subsection 2.1 of this procedure should be reviewed for inclusion into the revision.
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2.3 DOCLHENTATION PHASE ll894-C, "EOP Step Documentation Form", will be filled out by the EOP vriter L, give a justification of how he arrived at a given E0P step from the corresponding ERG stdp.
2.3.1 The forms will be used as follows except as noted in Sub-subsection 2.3.2 or unless designated (optional) below:
a.
In "Section I:
ERG Step", enter the ERG step which is to be made plant-specific (optional),
b.
In "Section II:
E0P Step", enter the Eor step which was generated from the ERG step (optional),
c.
In "Section III:
Justification", explain why there are differences (or why there are no differences) between the ERG and E0P steps, Also note the sources of the plant-specific information, d.
For ERG steps, E0P steps, and associated Justifications that are short in length, the writer will use the documentation form containing
( )'
all three sections, e.
For ERG steps, E0P steps, or associated Justifications that exceed the space provided on the form containing all three sections, the writer will use the documentation form for Section I, Seccion II, or Section III as necessary to present the material, f.
If the length of the material requires the use of two or more of the documentation forms for individual sections, the writer will include
"(Continued)" at the bottom of the first documentation form for the section, and adjacent and to the right of the section heading of subsequent forms.
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2.3.2 The forma vill be usc3 for exceptional cases as O
follows:
a.
If an FRG step is to be deletud, i.e.,
not converted to a corresponding E0P step, then enter the ERG step' in Section 1, enter "Not Applicable to this v.0P in Section II, and justify deletion of the ERC step in Section III, including plant-specific information sources, b.
If an E0P ctep is generated for which there is no ERG step, enter "No corresponding ERG step"I, and in Section I, enter the E0P step in Section I provide justification in Section III., including
}
the, plant-specific infereation sourcas.
2.3.3 The completed step documentation forms will oe used as source documents to assist in the review, verification, validation, and approvcl procesens.
When an E0P step must be revised, a new step documentation form will be completed and forwcrded to the PRB for review along with the E0P PP.RF package.
Af ter review the reviced step docuuentation form will be filed immediately preceding any other forms applicable to the step.
This may be specified by Operationa-Engineering to be in a separate file or s.
within the E0P step documentation package.
2.3.4 Step documentaticn quality shall ba in accordance with 00100-0, "Quelity Assurance Records Administration",
Sub-subscuts.on 4.2.1 at the time of transmitting to Document Control as a QA record.
2.3.5 E0P step documentation justificationa should be detailed enough so that reviewer can understand why the E0P is different from the ERG sceu and should reference all sources necessary to justify 'the change.
Revisions to a step document should restate all justification references or state that previous step justification is still applicable.
A step docement update is considered an addendum of the str.p documentation.
2.3.6 Any reference souret document used to justify E0P step l
differences from ERG steps should be referenced within the justification.
Examples of how to use references for jcstification is included but not limited to the following.
2.3.6.1 ERG Feedback items for ERG changes aft 9r the most current ERG revision should be reftsrenced if approved and used to justify E0P step.
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Chanfnologyshouldreference10012.C,es to the EOP which are due to Vagule 2.3.6.2 (r-')
term E0P And AOP Writers Guide", if appropriate.
2.3.6.3 If the E0P step is identical to the ERG ttep, then the ERG step should be referenced.
1 2.3.6.4 If the E0P step is only different from the ERG step due to differences in terminology but is still consistent with the intent of the ERG step, then the ERG step and 10012-C, "EOP And AOP Writers Guide" should be referenced.
2.3.6.5 If the E0P step was modifieo to be more consister.t with the ERG Background, then the ERG Background for step i
=
should be referenced.
2.3.6.6 If the E0P step differs from the ERG step due to plant specific differences from the generic plant, then appropriate FSAR references, drawing numbers, or vendor manuals should be referenced.
2.3.6.7 If the E0P step differs from the ERG step by having or not having a cetpoint for adverse containment conditiona, the E0P Setpoint Document should be referenced with explanation.
p_
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2.3.6.8 A confirmation letter may be used to justify E0P
(_
differences from the ERG if directed to the appropriate approving body, i.e., Westinghouse Owners Group (WOG) and Westinghouse for ERG related items, Westinghouse for EOP Setpoint items.
2.3.6.9 Step number references changed due to addition or deletion of an EOP step does not require a revised step documentation form.
2.3.6 10 Changes to the.30P which alter the information utad by the operator to make decisions in performing tasks should be reviewed against task analysis review i
criteria in 10012-C, "EOP And AOP Writers Guide".
Thin criteria may be used in documenting why an EOP setpoint is used.
This criteria should also be need when instrumentation and controls and/or scales used to perform E0? steps have been changed.
2.3.6.11 During the Unit 1 to Common unit EOF revision, a newly issued step documentation form foc EOF (19xxx-C) documents that an in-depth Unit 1 to Unit 2 comparison has taken place and E0P procedural changes have been made, if necessary.
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2.4 MAI!iTENANCE AND REVISION OF E0P REFERENCE hATERIAL.S 2.4.1 The quality of EOP Reference Materials shall be maintained in accordance with 00100-C, " Quality i
f Assurance Records Administration ', Dub-subsection 4.1.1 at'the time of transmitting them to Document Control as a Ql. record.
2.4.2 The following E0P reference materials and revisions thereafter shall be controlled and distributed per 00103-C, " Document Diatribution And Control".
l 1
2.4,2.1 E0P Setpoint Document manual.
2.4.2.2 ERG Maintenance Prograu Summary manual.
c
' 4.2.3 ERG-HP Guidelines manual.
.2.4 ERC-HP Background manuals.
.2.5 ERG Executive manual.
.2.6 PGP manual,
-.4.3 The E0P Setpoint Document manual materials and cevisions thereafter shall be transmitted by z
O Westinghouse or be based on aparoved Westinghouse E0P setpoint documentation for both the controlled and information copies.
2.4.4 The following EOP Reference Materials should always be approved by the WOG and Westinghouse Engineering before E
use except in those cases Where plant specific information overrules the generic issues or used as justification for the EOP atep.
=
2.4.4.1 ERG Maintenance Progrcm Summary manual.
244.4.2 ERG-HP Background manual.
2.4.4.3 ERO-HP Guidelineo manual.
2.4.4.4 ERG Executive manual.
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l 2.4.5 Until an approved copy of revised E0P reference O) material.a is received by Operations Engineering, a (s
telephone confirmation letter may bc used for approval.
Such dccumentation revisions should be updated by a single line through the inforuation to be reviced, the ned information added, revision initialed and dated adjacent to the confirmation letter numbe.r.
Th39 method shall be used for all E0P reference materials referent.ed in this procedure.
l 2.4.6 Revised documentation rhall be maintained in an information copy of the following EOP Reference Materials to maintain a current approved status of changes until controlled distribution replaces it in the information copy and controlled copy.
2.4.6.1 E0P Setpoint Document manual.
2.4.6.2 ERG Maintenance Program Summary mcuual.
2.4.6,3 ERG-HP Cuidelines manual.
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2.4.7 EOP revisions should be ketpt current vith the most current approved reference raaterials, a
3.0 REFERENCE _S, k-3.1 PROCEDURES 3.1.1 10012-C "EOP And AOP Writern Guide '
3.1.2 11894-C "EOP Step Documentation Form" 3.1.3 00100-C
" Quality Assurance Records Administration" l
3.1.4 00103-C
" Document Distribution And Control" END OF PROCEDURE TEXT O
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