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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes 05000423/LER-1998-002, Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 9802071998-12-21021 December 1998 Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 980207 ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept ML20203F6931998-02-20020 February 1998 Rev 6 to PI-MP3-11, Discrepancy Rept Submittal & Closure ML20203E2131998-02-19019 February 1998 Cancelled Rev 26 to 1-OPS-10.11, Locked Valve List ML20203D4111998-02-18018 February 1998 Revised 1-OM-index Unit 1 Operations Dept OM Index & Rev 2 to OM 3.8, Millstone Unit 1 Operations Manual ML20203F6601998-02-16016 February 1998 Rev 5 to Audit Plan for Independent Corrective Action Verification Program ML20203F6751998-02-16016 February 1998 Rev 2 to PI-MP3-07, Review of Accident Mitigation Systems ML20216H7351998-02-11011 February 1998 Independent Corrective Action Verification Program Status Rept ML20203H3271998-02-0505 February 1998 Restart Assessment Plan Millstone Station 1999-05-10
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PARSONS PP-02
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MILLSTONE UNIT 2 ICAVP PROJECT PROCEDURES
Title:
Accident Mitigation Systems Review REVISION 4 Prepared by:
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t ager, Co pany Quality Program Approved by:
Lddh Date: /0 Project ctor REVISION HISTORY REVISION DATE REVISION DESCRIPTION 0
04/03/97 Procedure initiation 1
06/09/97 incorporation of NRC Comments 2
06/27/97 Revision for AMSR Process Details 3
09/19/97 incorporation of NRC Comments 4
10/05/98 Incorporation of NRC Comments lO lBA 188st Ola888 2 lC P
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MILLSTONE UNIT 2 ICAVP PP-02 g
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TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 2 OF 12 LIST OF EFFECTIVE PAGES Pace No.
Revision No.
All 4
TABLE OF CONTENTS 1.0 PURPOS E -
..,,,,,,,,,,,,3 2.0 DEFINITIONS 3
3.0 AMSR BASIS.
3 4.0 RESOURCES.
.4 5.0 PROCEDURE.
....,4 5.1 CDC DEVELOPMENT -DEFINE CRITICAL SAFETY FUNCTIONS..
... 7 5.2 CDC DEVELOPMENT -IDENTIFY CRITICAL CHARACTERISTICS AND PARAMETERS
...9 5.3 CDC VALIDATION - COLLECT SYSTEM DESIGN AND PERFORMANCE DATA...
.. 10 5.4 CDC VALID ATION - VALIDATE FSAR CHARACTERISTICS..
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' oQ TITLE: ACCIDENT MITIGATION SYSTEM REVIEW l
REVISION: 4 DATE: 10/04/98 PAGE 3 OF 12 1.0 PURPOSE The Accident Mitigation Systems Review (AMSR) will identify and verify the critical design characteristics for accident mitigation systems and their components required to meet the Design Bases Events (DBEv) identified in Chapter 14 of die Millstone Nuclear Plant Unit 2 Updated Final Safety Analyses Report (UFSAR).
2.0 DEFINITIONS 2.1 Design Bases Event (DBEv) - Design Bases Events are defined as those initiating events as presented in Chapter 14 of the UFSAR and form the bases for the operating license of the Millstone Unit 2 Nuclear Power Plant.
OU 2.2 Critical Safety Functions (CSF) " Critical Safety Functions" are defined as the required specific set of activities that must occur in order to ensure that a success path associated with the design bases event mitigation is met and maintained.
2.3 Critical Design Characteristic (CDC) - A critical design characteristic is defined as that aspect of the functional / system design that must be provided to ensure that the system or component will meet the performance criteria identified in Chapter 14 of the UFSAR.
2.4 Critical Parameters - A numerical value associated with a CDC.
3.0 AMSR BASIS l
'Ihe following documents are the basis for the ICAVP AMSR l
UFSAR Chapter 14 Accident Analyses & Supporting Calculations
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Technical Specifications p
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PROJECT PROCEDURES.
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,' Q TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 4 OF 12 System P& ids & Diagrams i
System Design Descriptions (SDD) e Design Calculations Emergency Operating Procedures Safety System Logic Documents Safety Evaluation Report (SER)
Regulatory Commitments e
4.0 RESOURCES The following resources are utilized to perform the AMSR System Engmeer
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V Accident Analyst e
Electrical Engineer Mechanical Engineer Controls Engineer Operations Engineer e
Tier-2 Database 5.0 PROCEDURE Oveniew: Determine the critical design characteristics for systems and components that must be confmned in order to ensure that the plant complies with the safety analyses identified in Chapter 14 of the UFSAR. Validate the presence of the critical design characteristics in the installed plant systems. The simplified process flowchart is presented in Exhibit 2-1. The DBEv groups covered by this procedures are identified in Exhibit 2-2.
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g MILLSTONE UNIT 2 ICAVP PP-02 PROJECT PROCEDURES
> PARSONS TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 5 OF 12 Exhibit 2-1 AMSR Process FS AR Chanter 14&
Tech Snee E Develop Define Each Devebp System Emem Oo pre I
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TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 6 OF 12 1
Exhibit 2-2 DBEv GROUPS DBEv Variation Increase in Heat Removal Decrease in Feedwater Temperature by the Secondary System Increase in Feedwater Flow Increase in Steam Flow Inadvertent Opening of a Steam Generator Relief or Safety Valve Steam Pipe Failure Inside and Outside containment Decrease in Heat Removal Loss of Erternal Load by the Secondary System Turbine Trip Closure of Main Steam Isolation Valve Loss of Normal Feedwater Flow Decrease in Reactor Loss of Forced Reactor Coolant Flow V
Coolant System flow Reactor Coolant Pump Rotor Seizure Reactivity and Power Uncontrolled Control Rod Bank Withdrawal From a Distribution Anomalies Subcritical or Low Power Startup Condition Uncontrolled Control Rod / Bank Withdrawal at Power Control Rod Misoperation Startup of an Inactive Loop CVCS Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant Control Rod Ejection Accident Decrease in Reactor Inadvertent Opening of a Pressurizer PRV Coolant inventory Steam Generator Tube Failure - Rad Consequences LOCA From Breaks in the RCP Boundary Radioactive Releases from Waste Gas System Failure a Subsystem or component Fuel Handling Accident Spent Fuel Cask Drop Accident Non-Standard Review Plan Containment Analyses Events Hydrogen Accumulation in Containment Radiological Consequences of the Design Bases Accident O
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I Q TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 7 OF 12 5.1 '
CDC DEVELOPMENT - DEFINE CRITICAL SAFETY FUNCTIONS Purpose 1.1 he purpose of this activity is to develop CSF Definitions e
CSF Diagrams System Boundary Diagrams Tier-2 Database Structure e
Action 1.1 Review UFSAR Chapter 14 and identify design bases events by groups (refer to
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Exhibit 2-2).
1.2 Evaluate DBEv groups to identify Critical Safety Functions essential to achieve and maintain a controlled condition following an event. (e.g. RCS Heat Removal, Reactivity Control, RCS Inventory Control, etc.)
1.3 Define Critical Safety Function objectives and system level processes / actions to achieve objectives.
1.4 Create generic Critical Safety Function Diagrams for each Critical Safety Function.
1.5 Identify system level active components that support the process or action.
(Example shown as Exhibit 2-3) i
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TITLE: ACCIDENT MITIGATION SYSTEM REVIEW i
l REVISION: 4 DATE: 10/06/98 PAGE 8 OF 12 1.6 Develop a Boundary Diagram for each System involved with the DBEv.
1.7 Develop a data base structure to record the system and component critical characteristics and parameters for each DBEv.
Exhibit 2-3 SAFETY FUNCTION DIAGRAM Loss ofFeedwater Flow ikj RCS Presswe &
Reacuvity Heat Removal Inventory Control Control Mamtam Pm um M
Cored M waw ControlMam Mamm Reacw Ranctor Pressure Baron Level Rods To SG Stream Flow Tempersnare Component Critical Design Criteria i
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TITLE: ACCIDENT MITIGATION SYSTEM REVIEW j
REVISION: 4 DATE: 10/05/98 PAGE 9 OF 12 5.2 CDC DEVELOPMENT - IDENTIFY CRITICAL CHARACTERISTICS AND PARAMETERS Purpose 1.1 The purpose of this activity is to develop Functional / system level critical characteristics e
Database file and reports of the critical parameter for each system and e
DBEv safety function.
Discrepancy report Action Oh 1.1 Review each FSAR chapter 14 DBEv, including supporting analyses and calculations, to identify design requirements. Using the Critical Safety Function Diagrams, identify functional / system level critical characteristics for each DBEv.
1.2 Using the System Boundary Diagrams identify the components and their critical parameters essential to achieving the functional / system critical characteristics for each DBEv.
1.3 Enter DBEv critical characteristics and parameters into the Tier 2 database (T2DB).
1.4 Document source of analyses parameters and key assumptions.
1.5 If an inconsistency exists, a discrepancy report shall be prepared in accordance with the discrepancy report process (PP-07).
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TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 10 OF 12 1.6 Submit the DBEv functional / system level critical characteristics to the NRC for review.
1.7 Provide system and component critical design data to Tier I for Systems selected for review.
5.3 CDC VALIDATION - COLLECT SYSTEM DESIGN AND PERFORMANCE DATA Purnose 1.1 The purpose of this activity is to develop Critical System / Component listing including performance requirements and p
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capabilities Discrepancy Reports e
Action 1.1 Develop system composite database for critical safety function systems using documented information (plant design drawings, calculations, DBDs, test procedures, etc.).
1.2 List component design performance requirements into the T2DB.
1.3 Document references and source infbrmation used to identify the important to safety components and systems.
1.4 If a component or system is found to contain a discrepancy, a discrepancy report shall be prepared in accordance with the discrepancy report process (PP-07).
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TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 11 OF 12 5.4 CDC VALIDATION - VALIDATE FSAR CHARACTERISTICS Purnose 1.1 The purpose of this actisity is to Validate that the Functional / System level Critical Design Characteristics are present in the installed plant systems.
Develop Discrepancy Reports Action 1.1 Validate 100% of the functional / system level critical characteristics derived from FSAR chapter 14 and supporting analyses. This validation will be based on D
[Q review of plant test data, Technical Specifications, calculations, A/E design requirements or alternate methods, as appropriate.
1.2 Review Emergency Operating Procedures versus critical design characteristic to determine consistency.
1.3 Document the following information:
Critical system / component design requirement from the FSAR DBEv resiew Confirmation that the installed design meets the design requirement Validation references 1.4 Validation of the Critical Design Characteristics for the NRC selected systems will be coordinated with the Tier 1 SVSR team.
1.5 Tier 2 personnel will validate that the Critical Design Characteristics are in place O
and properly documented for the remeuung systems.
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> PARSONS TITLE: ACCIDENT MITIGATION SYSTEM REVIEW REVISION: 4 DATE: 10/05/98 PAGE 12 OF 12 1.6 Systems and components not meeting the Critical Design Characteristics will be identified as a discrepancy in accordance with PP-07.
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