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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis 1999-09-05
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program ML20084N3541995-03-24024 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20137B5371995-03-22022 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20081C1281995-03-0808 March 1995 Svc Water Sys Operational Performance Insp Self-Assessment Plan ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20078A7821994-06-24024 June 1994 Purge & Vent Containment Isolation Valves Resilient Seal Maintenance/Surveillance Program & Technical Basis ML20064G5391994-01-14014 January 1994 Rev 0 to Div I Mod Design Description MDD-OC-622-C Div I, Replacement of Recirculation Flow Monitoring Electronics ML20059M2301993-11-12012 November 1993 Rev 7 to 6610-PLN-4200.01, Odcm ML20057B3781993-09-0202 September 1993 Rev 6 of Solid Waste Staging Facility Sys Description ML20046B5271993-07-29029 July 1993 Emergency Operating Procedures for Oyster Creek,Including Rev 1 to 2000-EMG-3200.01A,.01B,.04A,.04B,.08A,.08B,Rev 2 to 2000-EMG-3200.12,Rev 4 to 2000-EMG-3200.05,Rev 5 to 2000-EMG-3200.10,.11 & Rev 9 to 2000-EMG-3200.02 ML20045E6931993-06-28028 June 1993 Rev 52 to Procedure 2000-RAP-3024.01, NSSS Annunciator Response Procedure. ML20056C3151993-05-0707 May 1993 Rev 1 to Vol IV of Gpun ISI & NDT Manual ML20127A2181992-10-15015 October 1992 Rev 1 to 6615-PLN-4520.01, REMP - Plan ML20127A2301992-08-11011 August 1992 Rev 30 to Emergency Procedure 1202-32, Flood ML20085L4141991-10-31031 October 1991 Rev 7 to Pump & Valve Testing Program ML20090D4031991-10-0404 October 1991 Rev 16 to Waste Solidification Process Control Program ML20082M2991991-08-29029 August 1991 Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20086B5131991-07-16016 July 1991 Rev 5 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Oyster Creek Emergency Dose Calculation Manual ML20127A1511991-07-0808 July 1991 Rev 4 to 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20082M2951991-06-27027 June 1991 Rev 14 to Operating Procedure 1104-28I, Waste Sodification Process Control Program ML20198B9741991-06-17017 June 1991 Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070L3331991-03-15015 March 1991 Rev 1 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070U9241991-03-0404 March 1991 Rev 0 to 6610-PLN-4200.01, Odcm ML20062G8641990-10-0404 October 1990 Rev 0 to Functional Requirements for Augmented Drywell Insp ML20062B9401990-09-17017 September 1990 Rev 2 to TR-050, Gpun Response to Generic Ltr 88-01 & NUREG-0313,Rev 2 ML20059H9031990-09-0707 September 1990 Rev 0 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20059C7931990-08-23023 August 1990 Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility ML20043C2511990-05-25025 May 1990 Rev 4 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Emergency Dose Calculation Manual. ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. 1999-09-05
[Table view] |
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TECHNICAL FUNCTIONS Numon jw: !
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BIN,jiJMC4OSI DIVISION 5000 4 tt*-7311,03
( EW-O f 4)
- T; tie Revesson No.
PRGIECT REVIEWS 1.nl AggNecaostety/ Scope , Responsible Office TechnicalFiinctionsDivision EP&S 5110 This document is important to safety Q Yes a No Effecove Oate Ust of Effective Pages 2-21-86
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Onginator il h/d/, ((, //[/ l Engrg. Proc & Stds ! tanager l J/g / gr- t concurrec ey j lhh[d i Director-Engineering Projects 9/g/gf i
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WEISS96-293 PDR 1.0 7T [ ,
hj bU Mf DVS N i OSNM-7311.03 Project Reviews
, 1.0 PURPOSE & SCOPE l' This procedure defines the process for the conduct of internal and multi-di' visional reviews of proposed plant modifications. Review and concurrence requirements for modifications and representation at specific review meetings (when called) are identified in this procedure. '
r
2.0 REFERENCES
2.1 1000-ADM-1215.02 " Technical Document Release" (EMP-008) 2.2 1000-ADM-1291.01 "GPU Nuclear Safety Review & Approval ;
Proceoure" '
2.3 5000-ADM-1291.01 " Safety Evaluations" (EP-016) ,
, 2.4 5000-ADM-1291.02 " Independent Safety Reviews" (LP-009) 2.5 5000-ADM-7313.01 " Modification and System Design Descriptions" (EP-005)
, 2.6 1504-ADM-7350.01 " Plant Modifications Engineered by Plant Engineering" (EMP-019) 2.7 5000-ADM-7370.03 " Control, Evaluation and Resolution of '
Review Comments on Technical Documents" (EP-008) 3.0 DEFINITIONS 3.1 Preliminary Engineering Documents (Baseline) - Including, but not limitert to, safety evaluation, design criteria documents, flow charts, System Design Descriptions, general arrangement drawings, single-line diagrams, and logic diagrams which show or define basic plant parameters. For instance Control Panel Layout and Control Room arrangement drawings are baseline documents. These dccuments cannot be released or revised without ^PTIC approval.
3.2 Modification - A configuration change initiated on a ccmconent, structure, system or piece of equipment (including deletions, additions or substitutions).
3.3 Project Engineer (PE) - The GPUNC individual assigned
- _ responsioility for monitoring a particular work effort. The effort may be totally within GPUNC or with an cutside contract
- r.
The PE .nay be frem any department of the echnical Functions j
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Divisicn.
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h a]ucJear !=". = " " "' F5-73" .o :
Project Reviews WT* ,
l is not called, the MEP shall designate a qualified Responsible Technical Reviewer to insure that all comments resulting from the
, review are resolved. Whether or not a meeting is called, the review group should include the organizations listed in paragraph ,
4.7.1 and the documents listed in paragraph 4.7.2. It is
- anticipated this (PEDR) review will be conducted only once during a j project unless significant changes are made to the baseline '
- engineering re, quiring a new multi-discipline review.
I 4.3.1 Suggested guidelines for holding a PEDR as a meeting:
Three or more technical disciplines involved. ,
Budget estimate of $100,000 or greater.
Schedule of 12 months or more. ,
Significant initial safety questions.
Significant plant operational impact or questions.
i Meetings should be considered as the review mechanism, for ,
any project having any one of the above criteria.
4.3.2 The Responsible Technical Review (RTR) shall be conducted as part of the PEDR process with the Chairperson serving as the t Responsible Technical Reviewer when a meeting is called or l through comment resolution as indicated in paragraph 4.3 when not conducted as a meeting. This review is a part of the safety review process as explained in 5000-ADM-1291.02 (LP-009). The purpose of the Responsible Technical Review (RTR) is to ensure that all the appropriate engineering concerns and safety considerations have been addressed during the design process. Generally the sco:e of tnis review shall folicw that for the ?EDR. The Independent Safety Reviewer and the Responsible Technical Reviewer signify approval by signing the Safety Evaluation /
Environmental Imcact Summary Sheet ::er ECCO ACM-1291.Cl
( EP-016) and SCCO- ACM-1291.02 (L?-CC9) .
5 i
!1 order to function as an RTR one must te :ertified
_' ( reference ICCO-ACM-1291.01) and assi:ned ne tas'< ov their management. The certification f:rm, wni:n assess botn RTR 3 ISR (reference L?-009 - 50CC 201-1291.02) is p
filed in EDICC I
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4.0
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- ve Project Reviews , "*'"f'.Cd f
- Technical progress since the previous review.
i Identification of technical or management issues needing l l' resolution. This should include major near term (three l or four months) decision points and data required to l l
effect a decision.
l In addition to the above, items from Section 4.5.2 should be addressed as appropriate.
4.5.2 Scope of PEDR - This review shall address the following basic questions as a minimum.
l Is' the work scope clearly defined and appropriate?
l l ,
Are the criteria and requirements clearly defined and will they result in an acceptable final design?
Will the proposed modification accomplish the intended li function?
l
- Will the design adversely impact the operability or maintainability of any component, system, or the overall plant (i.e. adverse system interaction)?
Are there any design features which will increase the possibility of operator error?
Are there any design features which will adversely affect licensing of the modification?
Will the prooosed modification to include construction and installation adversely imoact tne environnent?
Does the System Design Description, Jivision : and Preliminary Division II accurately and idecuately address the criteria requirements of 50CC-ADM-7313.01?
Is additional loading on the batteries or diesel generator required?
2 Are there any scecial consideration to be scd-ess+i I -
during installation - special cermits, safety g precautions, pl ant tecn. soec requirscents e .c.'
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E v 8< c a 6.0
l TECHNICAL FUNCTIONS I A,eer
[r 4-); pyg7 DIVISION SC00-ACM-7311.03 Project Reviews l 'T[
l 4.7 Conduct of PEDR Meetings - PEDR meetings normally will be arranged by Project Engineering. The afanager Engineering Projects (MEP)
, shall appoint a chairperson usually fecm GPUN Management, but not necessarily from Technical Functions Division. A/Es are expected l . to assist in preparation for and to participate in PEDRs for which they prepare preliminary (baseline) engineering.
4.7.1 The MEP and the designated PEDR chairperson will jointly
- select the organizations who should participate in the l PEDR. Required invitation to a PEDR meeting shall include as a minimum the following or their designated ,
representative: .
l Of rector, Engineering Assurance l .
Of rector, Engineering Projects Director, Engineering & Design Of rector, System Engineering Director, Startup & Test Manager, Engineering Projects i
Manager Licensing Plant Representatives Radiological & Environmental Control Representative (as required)
GPUNC Nuclear Assurance Representative (as required)
Maintenance and Construction Representative Manager of Security (for modification affecting Security Plan)
If the modification being reviewed is important to safety, the '.fcensing Manager or a designated etelegate who will perform the Independent Safety Review per 5000-ADM-!291.22 shall participate in the PEDR.
4.7.2 The review package for 2EJRs shall include coof es of t'e Safety Evaluation /Envirormental Im act Sumary S*r eet, i criteria (500 I), Preliminary 500 I*, flow diagrams, l elementary diagrams, and general arrangement drawings as l recuired to clearly define the scoce, functional require-l ments and conceptual design of the mcdification. Review
_ pacuges for PEDR meetings shall nor1 ally be issued in 2 sufficient time to allow a two-week review perted criar to i tne meeting.
! 1.7.3 -ce f:rmal mem:ers of tne ?E:R 3 card as definec i :3 3.
5 4.7.1 shdll not have been involvec in engineering :r
- managi9g tre engineerf og of tne design
- 3ckage being y 'eviewed.
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8.0
TECHNICAL FUNCTIONS l Nurr.cer
. (# L)]bMCMI DIVISION ;5000-A0f t-7311.03 i Title Revision No.
Project Reviews 1-00 F
4.8 Conduct of Ot1CR fleetings - The Project: Engineer shall schedule the l time and place for an onsite meeting and provide attendees with sufficient information, (f.e. 500-1, SDD-II (if avafiable)
Installation spec, etc.) to permit a meaningful review and to ,
conduct an informal presentation. The design engineering ;
organization (internal or external) will normally assist the ,
Project Engineer with the presentation.
4.8.1 Mandatory participants in this review, in addition to Projects and Design Engineers, are Plant Operations, Plant itaintenance/ Material, f4aintenance and Construction, Start-up and Test, Radiological Engineering, and GPUf!C Quality Assurance representatives. Other participants are at the
! discretion of the Project Engineer.
4.8.2 The Project Engineer shall issue minutes of the meeting to I include problems identified and follow-up action assign-ments.
5.0 RESP 0tlSIBILITIES 5.1 Project Review fleeting (Refer to Procedure Ficw Chart, Exhibit 1) 5.1.1 PROJECT Review Preifminary (Baseline) Engineering EtlGIt1EER/ Docucents SECTI0tt
!%flAGEP, (PE/ Sit)
- 5.1.2 l "AlAGER Cetermine need, type and scheduie c# Project l E
- :GI lEERI:lG Review neetings and the required PROJ ECTS/ attendees l SECTI0tl Select Chairperson for PECR who also acts as the
.A!!AGER Responsible Technical Reviewer
(.vEP / Sit ) Forward review package to '!anager Licensing ("L) for an Independent Safety Review (ISR) of :75 codifications (Ref. ECCO-ADM-1291.02) 5
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TECHNICA1. FUNCTIONS e %rreor ij (if- JT 1.,d
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BCCO-ADM-73?'.:3 Title Revision No.
Project Reviews 1-00 I I
5.1.8 ;
ENGINEERING File meeting minutes DATA & CON-FIGURATION CONTROL (ED&CC) 6.0 EXHIBITS .
6.1 Exhibit 1 - Project Review Meeting Procedure F10w Chart 6.2 Exhibit 2 - PEDR Review Form i
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~ ~ ' , TECHNICAL FUNCTIONS jNume :
C 'M /;'d C 3OI DIVISION :5000-ACit-7371.03 rice I Revision No.
Project Reviews 1 00
, EXHIBIT 2 PEDR Review I
t Project
Title:
I l Date of Review:
Indiv1 duals Participating in the Review:
thme Title l
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! Documents Reviewed:
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