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| | number = ML20137U410 | | | number = ML20137U410 |
| | issue date = 04/09/1997 | | | issue date = 04/09/1997 |
| | title = Rev 0 to CK-MP3-07-01, Independent Corrective Action Verification Program (Icavp) Sys Review Checklist,Fsar Chapter 15 Accidents,Sys & Components Review Checklist | | | title = Rev 0 to CK-MP3-07-01, Independent Corrective Action Verification Program (ICAVP) Sys Review Checklist,Fsar Chapter 15 Accidents,Sys & Components Review Checklist |
| | author name = Johnson J, Peebles W | | | author name = Johnson J, Peebles W |
| | author affiliation = SARGENT & LUNDY, INC. | | | author affiliation = SARGENT & LUNDY, INC. |
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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 ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit 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 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 ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL 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 ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls 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 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 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 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 ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage 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 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 ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments 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 ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls 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 ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station 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 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 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 ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 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 ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts 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 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 ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air 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 ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info 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 B17159, Backlog Mgt Plan for Unit 31998-03-31031 March 1998 Backlog Mgt Plan for Unit 3 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 ML20203F6751998-02-16016 February 1998 Rev 2 to PI-MP3-07, Review of Accident Mitigation Systems ML20203F6601998-02-16016 February 1998 Rev 5 to Audit Plan for Independent Corrective Action Verification Program ML20216H7351998-02-11011 February 1998 Independent Corrective Action Verification Program Status Rept 1999-05-10
[Table view] |
Text
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I A Northeast Utilities i Millstone - Unit 3 Independent Corrective Action Verification Program (ICAVP)
I System Review Checklist l l
CK-MP3-07-01, Rev. 0 l 1
FSAR Chaoter 15 Accidents. Systems and Comoonents Review Checklist Prepared by: ' 3.kimscnh K.Wc5 5 /}
Name Signature h//h / ' q.J.qy Date Approved by: kD d2tl'R' ~
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- . Name Signature /' Dale '
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J IMPLEMENTATION Accident Name i
FSAR Section
. Verified by: Date:
j Concurrence by: Date:
9704160381 970411 PDR ADOCK 05000423 O PDR j v
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4 i Northeast Utilities CK-MP3-07-01 Millstone Unit 3 Revision 0 i Page 2
- FSAR Chapter 15 Accidents, Systems and Components Review Checklist Instructions i
! This checklist is used by the Accident Mitigating Systems Review Group (ARG) to i supplement the procedure PI-MP3-07 in order to identify systems and components
- i. available for mitigation of accident effects and systems credited with mitigating the l consequences of accidents. This checidist shall be used to record the critical parameters
[ associated with these systems that are used in the accident analysis.
System Critical Parameten are defmed in PI-MP3-07 as the parameters of an accident mitigating system that are relied upon for performing the safety related function. For the purpose of this checklist, critical parameters are grouped into two categories, which are not mutually exclusive. Safety analysis parameters are those parameters used to evaluate the system response to an accident and the ability of the system to perform those functions related to mitigating the damage caused by the accident. Radiological parameters are those parameters used to evaluate the consequences of an accident and the ability of the system to mitigate the accident consequences. Note that accident consequences are defined as the harmful effects (including radiation exposure) to the general public or plant operators resulting from the accident.
This checklist is divided into three parts consisting of:
. Part I - Identification of Safety Analysis Parameters
- Part II - Identification of Radiological Parameters
.. Part III- Parameter Verification A separate checklist shall be completed for each accident. Use of the checklist will be as follows:
- 1. The ARG Lead shall initiate the checklist for each accident by completing the accident name and FSAR section block on the cover sheet and assigning a lead verifier.
- 2. The lead verifier or a designated discipline verifier shall complete Part I of the checklist by;
- a. Reviewing the safety analysis presented in the FSAR, SER. reload analysis or related technical documents.
- b. Entering a description of the accident and identifying the documents reviewed.
l
- _ . -. _ . - . I
Northeast Utilities CK-MP3-07-01 j Millstone Unit 3 Revision 0 i Page 3 I FSAR Chapter 15 Accidents, Systems and Components Review Checklist l c. Identifying the systems or structures used for accident mitigation in the i safety analysis by checking Applicable or Not Applicable as appropriate in the list in Part I.
l d. Specifying the safety analysis parameters associated with this accident.
This is done by attaching comment sheets as appropriate to Part I. Each q j system marked as applicable to this accident shall have at least one
{
numbered comment. On a comment sheet associated with each comment I
number will be one or more parameters with the assumed values used in the i
safety analysis and, if appropriate, the related system components. l t e. Verification of the input parameters is accomplished in Part III of this !
- checklist.
- f. Signing Part I of the checklist and returning it to the ARG Lead.
1
- 3. The lead verifier or a designated discipline verifier shall complete Part II of the i checklist by
- a. Reviewing the safety analysis presented in the FSAR, SER, reload analysis or related technical documents to determine if an accident consequence I analysis has been performed for this accident.
- b. Entering a description of the accident and identifying the documents reviewed.
- c. Completing questions 2 and 3 to document whether there is an accident consequence analysis for this accident. i
- d. Identifying the systems or structures used for mitigating the accident
]
consequences by checking Applicable or Not Applicable as appropriate in !
the list in Part II.
- e. Specifying the radiological parameters associated with this accident. .This i
is done by attaching comment sheets as appropriate to Part II. Each system marked as applicable to this accident shall have at least one numbered comment. On a comment sheet associated with each comment number will be one or more parameters with the assumed values used in the consequence analysis and, if appropriate, the related system components.
- f. Verification of the input parameters is accomplished in Part III of this checklist:
- g. Signing and returning Part II cf the checklist to the ARG Lead.
4 .Upon completion of Pans I and II of the checklist, the ARG Lead or his designee shall:
- a. Initiate a separate copy of the form in Part III for each parameter identified in Parts I and II of the checklist by entering items 1 through 7.
bc Enter the data for each parameter in the ARG database. (See the attached input format.)
. - . , .m -
- -me i 4g _a,-, - --we++.
Northeast Utilities CK-MP3-07-01 Millstone Unit 3 Revision 0 Page 4 FSAR Chapter 15 Accidents, Systems and Components Review Checklist
- c. For those parameters associated with the vertical slice systems under review by the Systems Review Group (SRG) and the Operations and Maintenance and Testing Review Group (ORG), forward the list of
- parameters to the SRG and ORG for verificat:on.
- d. Assign discipline verifiers to complete items 8 and 9 in Part III for each safety analysis and radiological parameter for systems not under review by the SRG and ORG.
- 5. The discipline verifiers will complete Part III of the checklist by:
- a. Identifying the documents that provide the basis for the input assumptions that define the parameter.
- b. Review the basis documents in accordance with the checklists in PI-MP3-
- 02. Enter a description of the basis documents and a summary of the verification in item 8 in Part III.
- c. If review of the basis documents identifies a discrepancy between the value used in the analysis and the basis document, the verifier shall initiate a DR in accordance with PI-MP3-11.
i If the parameter cannot be verified, the verifier will enter "Not Verified" in the comments section.
- e. Sign and return the completed Part III to the ARG Lead. !
- 6. Upon receipt of the completed Part III, the ARG Lead or designee shall:
- a. Enter the data in the ARG database.
- b. For those parameters that are identified as not verified, initiate a DR in accordance with PI-MP3-11.
- c. Assemble a complete checklist for each accident that consists of Part I, Part II, all comment sheets, and Part III for each parameter.
- d. Sign and date with concurrence and forward to the Verification Team Manager.
1 l
l
d Northtast Utilities' CK-MP3-07-01 i Millstone Unit 3 Revision 0 Page5 FSAR Chapter 15 Accidents, Systems and Components Review Checklist PART I Identification of Safety Analysis Parameters Accident Name:
a 4
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- 1. Accident
Description:
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- 2. Safety Analysis Documentation i
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. 1 Northeast Utilities CK-MP3-07-01 l Millstone Unit 3 Revision 0 Page 6 '
FSAR Chapter 15 Accidents, Systems and Components 1 Review Checklist l Accident Name: j
- 3. Systems and structures identified in the Safety Analysis: I Not System / Structure Applicable Applicable Comment #
Containment Systems Primary Containment Secondary Containment Containment Isolation l
Combustible Gas Control '
Emergency Core Cooling Systems Safety Injection Residual Heat Removal O O Containment Spray Chemical and Volume Control Ventilation Systems Supplementary Leak Collection O Auxiliary Building O O Fuel Handling Building Control Room O O Other Structures and Systems O
O Prepared by Date Part I, Page 2 of 2 9
a
Northeast Utilities CK-MP3-07-01 Millstone Unit 3 Revision 0 Page 7 FSAR Chapter 15 Accidents, Systems and Components Review Checklist PART II Identification of Radiolonical Parameters .
Accident Name: i
- 1. Accident Description (include applicable FSAR section or licensing commitment document): -
t
- 2. Are the consequences of the accident evaluated in the FSAR or licensing commitment document?
1
- a. No. State the rationale for not evaluating the accident consequences.
- b. Yes. Identify the location of the accident consequence analysis in the 1 FSAR or licensing commitment document.
1 i
- 3. Has the NRC evaluated the consequences of this accident and issued a SER or 1 other official document describing the results of their evaluation?
- a. No.
- b. Yes. Identify the SER or document and summarize the acceptance criteria used by the NRC.
Part II, Page 1 of 2 I
i j
i Northeast Utilities CK-MP3-07-01 Millstone Unit 3 Revision 0 Page 8 FSAR Chapter 15 Accidents, Systems and Components Review Checklist Accident Name:
- 4. Systems and stmetures identified in the accident consequence analysis:
Not System / Structure Applicable Applicable Comment #
l Containment Systems 1 1
Primary Containment !
Secondary Containment O }
Containment Isolation l Combustible Gas Control Emergency Core Cooling Systems Safety Injection O Residual Heat Removal Containment Spray Chemical and Volume Control l
Ventilation Systems Supplementary Leak Collection O l Auxiliary Building i Fuel Handling Building O !
Control Room i Other Structures and Systems Prepared by _ Date Part II, Page 2 of 2
Northeast Utilities CK-MP3-07-01 Millstone Unit 3 Revision 0 Page 9 FSAR Chapter 15 Accidents, Systems and Components j Review Checklist PART III. Parameter Verification i 1. Parameter Type Safety Analysis Parameter O RadiologicalParameter 3
- 2. System i
4
- 3. Component
- 4. Parameter Description
]
J
.' 5. Input Assumption i
- 6. Reference Analysis i
- 7. Accident Name i
l 8. Basis Documents and J
Verification
- 9. Comments l
Prepared by_ Date Part III, Page of
Northeast Utilities CK-MP3-07-01 Millstone Unit 3 Revision 0 Page 10 FSAR Chapter 15 Accidents, Systems and Components Review Checklist Comment Sheet Accident Name: :
Comment # Comment i
1 I
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1 i
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Comment Page of
Chapter 15 Accident Mitigating Systems- Mildene Iinit ICAVP sysran >iu ior ut,u.
PARAM ETER SAFETY ANAI YSIS AFFECTED COMPONEN I pl3CitIPilON DESCRIPTION INPUT ASSUMPTION REFERENCE ACCIDENT Em *6 -w w 5
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Cliapter 15 Accident Mitigating Systems Afilweese lfadt SYSTEM i al .Wiut* i lor 2 PARAMETER I COMPONi:N l' Ill3Cf Ul'I'lON DFSCRIPTION DESIGN INPUT VERIFICATION COM M EN'IS l
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