B16923, Forwards Info Which Identifies Criteria for Declaring RBCCW Sys Ready for Functional Insp,Details of Remaining Work in Area & Details on Sys Mods Re Independent CA Verification Program Tier 1 out-of-scope Insp

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Forwards Info Which Identifies Criteria for Declaring RBCCW Sys Ready for Functional Insp,Details of Remaining Work in Area & Details on Sys Mods Re Independent CA Verification Program Tier 1 out-of-scope Insp
ML20202H108
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/10/1998
From: Bowling M
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16923, NUDOCS 9802200293
Download: ML20202H108 (36)
v • d • e


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Northeast impe rerry na. (nooie 1s6), r ierro,a, er 06383

@ Milletone Nuclear Power Station Northeast Nuclear Energy Corngany

. P.o. Dos 128 Waterfora, CT 06383-0128 (860) 447 1791 ras (860) 444 4277 The Northeast Utihties Systern FEB l 01998 Docket No. 50-336 B10923 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station. Unit No. 2 Readiness for the Independent Corrective Action Verification Proaram Tier 1 Out-of-Scope Inspection Northeast Nuclear Energy Company (NNECO) committed in our letter of November 5, 1997 to notify the NRC when Millstone Unit No. 2 will be ready for the ICAVP Tier 1 Out-of-Scope Inspection.

As discussed with your staff on several occasions in the recent past, NNECO has identified the status of the open issues for the selected systen; for this inspection, the Reactor Building Closed Cooling Water System (RBCCW). NNECO projects that sufficient corrective actions on this system to be able to demonstrate that the system meets its licensing and design bases requirements will be complete to the degree necessary to support the on-site portion of the inspection beginning March 2,1998.

We will advise the NRC if there is any change in this projection.

Additionally, NNECO agreed to provide your staff with the criteria used to restore the system to an operational status and at what point NNECO believes that the Fystem will be ready for the inspection. Attachment 1 identifies the criteria for declaring the RBCCW System ready for the functional inspection.

This criteria is based on completing the engineering required to fully restore the RBCCW System licensing and design bases. This requircs completion of design basis calculations, analysis, and supporting technical evaluations. Attachment 2 provides the details of the remaining work in this area. Any system modifications will be Plant Operations Review Committee (PORC) approved and scheduled for implementation prior to restart to ensure ths physical system is capable of performing its safety functional requirements. Attachment 3 provides the details on these modifications. i l \

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U.S. Nucirr R:gulttory Commission B16923\ Page 2 The functional inspection recdiness criteria ensures that the required corrective actions are identified, evaluated and incorporated in the RBCCW system design documentatior'. In addition, the criteria ensures that the required changes or revisions to RBCCW operation and surveillance procedures are identified. Final implementation of any required plant procedure changes will be Plant Operations Review Committee (PORC) approved and implemented in accordance with the Design Control Manual, which contains specific requirements for system modification close-out and turnover to operations.

Of the applicable Configuration Management Program (CMP) Topical programs to this system, the High Energy Line Break (HELB) and the Electrical Environmental Qualification (EEO) Programs both have corrective actions which could impact the RBCCW system. The environmental conditions for the RBCCW components may change due to reanalysis being performed for the HELB. The attached criterion to support the RBCCW inspection requires that the RBCCW System components be evaluated for potential impacts based on expected or assumed bounding environmental conditions and corrective actions identified for those components requiring replacement and/or requalification. Component replacement and/or requalification documentation Environmental Qualification Reports (EORs) will be completed in support of plant restart.

An inspection Response Team has been established to work with your staff, under the direction of Mr. Steven Brinkman, Unit 2 Engineering Direu v. As in past inspections on Millstone Unit 3, Mr. Raymond Necci, Director of CMP will provide liaison from the CMP.

There are no new regulatory commitments contained within this letter.

If there are any further questions on the information provided in this letter, please contact Mr. Richard T. Laudenat 860-444-5248.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY M. L. Bowling, Jr. V Millstone Unit No. 2 - Recovery Officer cc: See Page 2

U.S. Nucl3:r R gul: tory Commission B16923\ Page 3 cc: H. J. Miller, Region i Administrator W. D. Lanning, Deputy Director, inspections, Special Projects Office W. D. Travers, Ph.D., Director, Special Projects Office E. V. Imbro, Deputy Director, ICAVP Oversight, Special Projects Office S. A. Reynolds, Branch Chief, ICAVP Oversight, Special Projects Office f

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Docket No. 50-336 B16923 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 ICAVP Out-of-Scope System inspection Reactor Building Closed Cooling Water System February 1998

O U.S. Nuclear Regulatory Commission -

818923%ttachment 1\Page 1 -

Attachment 1 - Inspechon Readiness Matnx Millstone Unit 2 ICAVP Out-of-Scope System inspecbon -

Reactor Building Closed Cooling Water System ,

Inspection Readiness Activity le.spection Readiness Criteria Remaining Activities To Be Cc.T.A" . Ready for lascoction Date

1. System Design Basis . Complete RBCCW System Design . Calculation revisions to support flew 2/16/98 Basis calculations rebatance (Attachment 2. Section 3)

System Modifications Defined and . Obtain Plant Operations Review . SOV and Cable replacement for RB13.B Not Ready for 2.

Approved Committee (PORC) approval due to ESF Room elevated temperature. Inspection

. Modifications related to EEQ Not Ready for

'Inspecbon (Attachment 3. Section 1)

3. RBCCW Peak Temperature and . Complete Peak Temp and . None Remain Reedy for inspechon Containment Design Basis Analysis Containment Analyses Complete Calculations (Attachment 2. Sections 1 & 2)
4. Impact of Elevated RBCCW . Identify Components Which Are . Complete Technical Evaluations For Reedy for inspechon Temperature Calcu!stion Results Are Not Quahfied. Components To Be Impact On Components Evaluated and Reviews Documented Replaced Prior to Mode 4 . Identify Component Replacements (Attachment 2, Section 2 & Section 8 Items 8-5, 8-6. 8-8, 8-9, 8-10, 8-11 % 1 HELB/EEQ Program Reviews . Confirm Based On Preliminary . Complete The Following HELB/EEQ 2/28/98 5.

Completed For RBCCW HELB/ RAD analysis That Evaluations Using Preliminary Profiles:

Components Meet Revised EQ

( Attachment 2, Section 8. Items 8-9 Requirements 1. Define bounding EQ Condsbons For 8-10. 8-13) . Identify Correct!ve Action For RBCCW Components Based On Components That Do Not Meet Revised Environments Bounding EQ Conditions.

2. Define Impact On Individual Components j

U.S. Nuclear Regulatory Commission B16923\ Attachment 1\Page 2- -

Attachment 1 - Inspection Readiness Ma+Jix Millstone Unit 2 ICAVP Out-of-Scope System inspection -

Reactor Building Closed Cooling Water System .

Inspection Readiness Activity Inspection Readiness Criteria Remaining Activities To Be Completed Ready for Inspection Date

3. Identify Components Requinng Replacements of Requal:5 cation 6 RBCCW a Complete Flow Balance . Revise Flow Balance Procedure Note: The above flow Flow Balance Procedure Comp!eted . Redo Flow balance rebalance actnnties wi!! be and Approved. . Evaluate Re-Test Results g>erformed during the inspection penod (Attachment 2. Section 3, item 3-7)
7. Operational Procedures Updated For . Procedures Required To Support . Revise Procedures 2/28/98 RBCCW Operation And Maintenance System Operation Are Revised OP-2330A AOP-2564 (Attachment 3, Section 3) Note Other procedures are revised as part of modification release to operations. Refer to Attachment 3 for schedule of modification released to ops.
8. Open Activities Associated With This 1. GL 96-06 Water hammer stress analysis System . Pipe Stress and Supports Summary Complete GL 96-06 Cales (Attachment 2. Section 8. Items 8-4 . Revrse existing pipe support r: ales Not Ready for inspechen 8-6. B-11, 8-12)

. Reconcile inputs wrth revised 2/16/98 Containment Analysis

2. Hot Pipe Ampacrty

. Hot Pipe Ampacity Technical Complete Evaluation

3. CAR Cooler TI Range

. Regulatory Guide 1.97 CAR Cooler TI Complete Range Technical Evaluation

4. Control Room Separation

. Correctree Action identified For 2/6/98 Control Room Panel Separation issues

5. ESF Response Time Testing for RBCCW Components b #

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I U.S. Nucl:ar Regulatory Commission 816923\ Attachment 11Page 3 Attachment 1 -Inspection Readiness Matrix 1 Millstone Unit 2 ICAVP Out-of-Scope System inspection  :

Reactor Building Closed Cooling Water System inspection Readiness Activity inspection Readiness C iteria Remaining Activities To Be Completed Ready for inspection Date

. Revise TRM To Address RBCCW Not Ready for Inspection Response Time Testing & Revise Surveinance Procedures

6. LER Supplements e issue LER 97-015-00 supplement for 2/27/98 GL 96-06 Review Resutts

. Issue letter to NRC cn RG 1.97 2/27/93 7 deviation for CAR Ti range

. Issue LER 97-014-00 supplement for 2/27/98 flow to ECCS pump seats  !

7. Integrated Safety Functional Review Not Ready for inspection
8. Revised 125 VDC Load calc. Not Ready for inspection
9. IST Basis Document and List of Valves in 2/27/98 Program
9. FSARCRs for RBCCW . Required FSAR Change Requests PORC approve remaining RBCCW FSARCRs 2/16/98 Approved By The PORC (Attachrnent 2, Section 6) 10 A!! RBCCW Synem Temporary . Temp. Mods identified Remove remaining Temp Mods prior to 2/16/98 Modifications Restart (Attachmerit 3 Section 2)

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11. Operator Training And Simulator . Identify Specific Operator . Re-Training Requirements identified 2/16/98 Retraining . Simulator Upgrades identified (Attachment 3, Sections 4 & 5) . Identify Simulator Fidelity Issues 12 Other (Attachments 2 & 3) . Identify other documentation (i.e e Complete detaillist of documentation and Eee Attachments 2 ar'd 3 Design Pasis Summary) status l

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Docket No. 50 336 B16923 Attachment 2 ,

Millstone Nuclear Power Station, Unit No. 2 Millstone Unit 2 ICAVP Out-of-Scope System inspection Reactor Building Closed Cooling Water System i

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ATTACHMENT 2 i Millstone Unit 2 ICAVP Out-Of-Scope System Inspection  !

] Reactor Huilding Closed Cooling Water System l

! Section Document Document ' Title Rev Schedule Status / Remarks l j Number Type No. Date -

SECTION I CONTAINNIENT ANALYSES CALCULATION  !

I-I 00(>-ST97-C-021 Calculation Updated CEII.ASif-4A LOCA Blowdown Containment Analysis O Complete Transferred to NDS j for Atillstone Unit 2 ftw pmeessing. E l-2 (MEST97-C-022 Calculation Updated FLOOD 3 LOCA Blowdown Containment Analysis for 0 Complete Transfened to NDS Mdistone Unit 2 fa pmcessing j I-3 IXWST97-C-023 Calculation Updated CONTRANS LOCA Containment Peak 0 Complete Transferred to NDS Pressure / Temperature Analysis for Millstone Unit 2 for processing

]; r I-4 006-S'IV7-C-024 Calculation MP-2 Containment Related Main Steam Line Break Analysis for 0 Complete Transferred to NDS FSAR Update for proccasing j

SECTION 2 RBCCW PEAK TE%fPERATURE ANALYSES  !

2-1 0%-ST-97-C-019 Calculation RBCCW Peak Temperature Analysis for Millstone Unit 2 0 Complete Transferred to NDS l for pmcessing j 2-2 96-ENG-1529M2 Calculation StP2 ESF Rooms Temperature Profile During a LOCA; Coolers O Complete [

l 16A/B (PPC)97-083 [

SECTION 3 RBCCW SYSTEM DESIGN BASIS CAI'CULATIONS, DESIGN BASIS

SUMMARY

, & FLOW BALANCE PROCEDURE 3-1 97-0M Calculation MP2 RBCCW - Component Outlet Temperature for Headers A- I Complete Resised to i, elude and 'B- 2 Complete RB-402 change.

Transferred to NDS I for procewing.

I 3-2 97-169 Calculation MP2 RBCCW - Design Basis Flow Distribution 1 Comple:e Rev i for RB-402 I ' 2/16/98 modification. L i

Transferred to NDS l for processing. [

Rev 2 to increaw j

margin fiw flow  !

balance to account

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i flow uncertainty.  !

3-3 97-170 Calculation MP2 RBCCW System - Documentation oI PROTO-FLO lhermal O Complete [

llydraulie Model [

3-4 97-ENG-01862-M2 Calculation RBCCW System - IIcat leads and flow Rates O Complete 3-5 97-ENG-Ol962-M2 Calculation RCS Cooldown Time With Reduced RBCCW I' low During 0 Complete f I

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ATTACHMENT 2

  • Minstone Unit 2 ICAVP Out-Of-Scope Systen Inspection '

Reactor Building Closed Cooling Water System Section Document Document Title Rev Schedule Status / Remarks Number Type No. Date -

Normal Shutdown 3-6 DBS-2330A DBS RBCCW System Design Basis Summary (DBS) 0 2/27N3 Issue /appmval upon final appmval of DB cales-3-7 SPROC 97-2-19 P ocedure RBCCW Flow Balance I C,mplete Revision 2 to 2 2NNS incwporate flow rehalance reg'ts SECTION 4 RBCCW GL 96 46 CALCULATIONS 4-I III-97l 847 Calculation IIOLTEC fluid transient analysis O Complete llOLTEC fluid transient analysis - Calculation Change Notice O Complete Transferred to NDS 4-2 111-971847 CCN 1 Calculation rw pmcessing RBCCW Piping Code Qualification for GL 96-06 Water llammer 0 Complete Transferred to NDS 43 GLRBCCW-02139-C2 Calculation fw pmcessing Loads & Temperature Changes M CCN-01 (CCN to be issued to add evaluation of the welded pipe 01 2NN8 attachments) 229 IndivMual pipe support calculation require a CCN to N/A Not ready 4-4 Pipe Support Cales (229) Calculations f*

document impact of GL 96-06 Inspection SECTION 5 RBCCW MISC. SYSTEM CALCULATIONS v7-005 Calculation MP2 RBCCW System Thermal flydraulic Analysis in support of 0 Complete 5-I NRC Generic letter %4)6 97-038 Calculation MP2 RBCCW - Flow Distribution for Maximum RBCCW I Complete 5-2 Temperature Analysis MP2 Car Unit Performance using PROTO-IIX Ver. 3.0 1 Complete 5-3 97-mo Calculation MP2 CEDM Cooler Performance using PROTD-IIX Ver 3.0  ! Complete 5-4 97-057 Calculation O Complete 5-5 96-M7 Calculation MP2 RBCCW System Devchyment of PROTO-FLO Thermal flydraulic Model MOV 2-RB4)30.l A CA' RBCCW IIcader Containment Supply 0 Canplete 5-6 89-078-851ES Calculation Valve) Target Thrust Calculation to Support REF/OD 92-46 1

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ATTACHMENT 2 ~

Millstone Unit 2 ICAVP Out-Of-Scope System Inspection Reactor Heilding Closed Cooling WaterSystem Section Document Document Title Rev Schedule Status / Remarks Number Type No. Date -

5 Complete 5-7 894178-875ES Calculation Unit 2 Target Thrust Calculation for 2-RB--30.I A ('A' RBCOy IIcader Contaimnent Supply Valve) and 2-RB-37.2A ("A' Return Vahe)

Unit 2 Target Thrust Calculation of 2-RB-30.1B ('B' RBCOy 3 Cemplete 5-8 89-078-921ES Calculation IIcader Containment Supply Valve) and 2-RB-37.2B ('B' Return Valve) _

4 Complete 5-9 95-ENG-1198M2 Calculation RBCCW Surge Tank (T3) Restraint 0 Complete 5-10 96-ENG-01487M2 Calculation Temperature Analysis of the Ausiliary. Bkfg. following a LOCA w/ loss of ventilation O Complete 5-11 96-ENG-0151 iE2 Calculation Thermal Aging Analysis of GE Vulkafle, "I-58709 Motor Leads I Complete 5-12 97-ENG-01668E2 Calculatism FE-6337 (RBCCW Flow Element Orifice from PDT/ Quench Tank Cooler). FE-6732 (RBCCW From ESAS Room Air Cooling Coil X36A Flow Element). FE-6736 (Cuil X36B) Differential

. Pressure O Complete 5-13 97-ENG-01785C2 Calculation New Lifting Device for RBCCW lleat Exchangers (X-18A/B/C)

Bell Cover Calculation Verification of Accumulator size for valves  ! Complete Rev 2 to clarify input 5-14 97-ENG4)I823M2 2-RB- 13.1 A & B 2 2/13/98 hasis 97-ENG-1774E2 0 03/15/93 Not ready hr 5-15 Calculation Battery 201 A and Charger. Associated Cable and Device Inspecthm Electrical Verification Calculation 0 03/I5/98 Not ready for 5-16 97-ENG-I775E2 Calculatiin Battery 201B and Charger. Associated Cable and Device inspection Electrical Verification Calculation I Complete 5-17 A-EE Calculation RBCCW IIcat Exchanger Pier Support Missile Protection for RBCCW Surge Tank 0 Complete 5-18 A-ZZZ Calculatitm 3 Complete 5-19 AL7RAN 94102-C-13 Calculation Weak Link Seismic Assessment MOV's: 2-RB-301 A & 2-RB-37.2A

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ATTACHMENT 2 -

Millstone Unit 2 ICAVP Out-Of-Scope Systent Inspection '

Reactor Building C1med Cooling Water S3 stem Section Document Document Title Rev Schedule Status / Remarks Number Type No- Date -

SECTION .i FSAR CHANGE REQUESTS (FSARCR)

Complete 6-I N97-MP24X)2 NOSE' RBCCW - Design Beis RBCCW - (IX3 M2-97018) Intersystem LOCA 02/16/98 6-2 97-MP2447 FSARCR RBCCW -(ACR 07886) Suneillance Testing Complete -

6-3 97-M P2-I 82 FSARCR RBCCW - Availability and Reliability Tests and Inspections Complete 64 98-MP ' FSARCR 02/16/98 6-5 9841PN FSARCR RBCCW - Design Criteria 98-MP2-6 FSARCR Millstone Unit 2 Peak RBCCW Temperature Analysis 02/16/98 6-6 l (S2-EV-984X)13) l 98-M -7 FSARCR RBCCW Normal Opera: ion and Shutdown Heat Loads 02/16/98 6-7 (S2-EV-98-0014)

  1. to be Assigned FSARCR Post LOCA Restoration of Spent Fuel Cooling 02/I6/98 gg (S2-EV-98-0017)

"8-MP2 -8 FSARCR RBCCW Rad. Monitor Description 02/16/98 49 (S2-EV-984Kil9)

  1. to be Assigned FSARCR RBCCW Manual Valve Identificatic.a Detail 02/16/98 6-10 (S2-EV 984W)20)
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ATTACHMENT 2

  • Millstone Unit 2 ICAVP Out-Of-Scope System Inspection Reac or Huilding Closed Cooling Water System Section Document Document Title Rev Schedule Status / Remarks Number Type No. Date -

SECTION 7 FNGINEERING RECORD OF CORRESPONDENCE (ERC)

ESF Roorn Temperature Pmfile O Complete 7-1 25203-ER-96-374 ERC O Complete 7-2 25203-ER-97-0)2 ERC Design of Inputs for Deselopment of RBCCW Hermal flydraulic Computer Model O Complete 7-3 25203-D' 974X)8 ERC Safety Ana!pis Input for RBCCW Analysis Maximum RBCOV Chilled Water Flows Brough flest I Complete 7-4 25203-ER-97-013 ERC E.schangers X-36A. X-36B, X-24, X-84 A. X-84B Transmittal of IST 2-96-006 Test Results RBCOV Pump U Complete 7-5 25203-ER-974)49 ERC Performance Testing 0 Complete 7-6 25203-ER-974173 ERC Design Input Assumption for Proto Power Calculation 97-038 MP2 RBCOV Flow Distribution for Maximum RBCOVTemperature Analysis RBCCW Surge Tank Level Monitoring 0 Not in NDS 7-7 25203-ER-97-165 ERC Reduction in SDC IIcat Exchanger RBCOV Outlet Valves O Complete

?-8 25203-ER-97-170 ERC Operating Time I Complete 7-9 25203-ER-97-179 ERC Calculated Stroke Time. Mot w Nameplate Data. Motor Venthw Curve Required to Support Hermal Overhud Calculation for 2-RB-30.l A and 2-RB-37.2A l Calculated Stroke Time. Motor Nameplate Data. Motor 0 Not in NDS I

7-10 l 25203-ER-97-199 I ERC i l Vendor Curve Required to Support Hermal Overkud l l r

Calculation for 2-RB-30.1 B and 2-RB-37.2B 0 Canplete 7-1I 25203-ER-97-226 ERC RBCCW System Flow Element tE-6337 Basis Information 0- Compiere  ;

7-12 25203-ER-97-252 ERC Design input for 2-RB-30.!B and 2-RB-37.2B I

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ATTACHMENT 2 -

Millstone Unit 2 ICAVP Out-Of-Scope System Inspection '

Reactor Building Closed Cooling Water System Section Document Document Title Rev Schedule Status / Remarks No. Date Number Type 7-13 25203-ER-97-342 ERC Maximum Expected SurFe Lesel for Normal Operation of -

RBCCW Surge Tank Load Combinations for Pipe Supports USAS B31.7 - 1%9 0 Complete 7-14 25201ER-97-348 ERC Class 11 and 111 Piping (USAS B31.0 - 1%7) for Millstone Unit 2 0 Complete 7-15 25203-ER-97-353 ERC Design inputs for MP2 Large Break LOCA Containment Analysis Design Inputs for RBCCW Flow Balancing 0 Complete 7-16 25203-ER-97-370 ERC I Complete 7-17 25203-ER-97-381 ERC Design Inputs for MP2 Containment MSLB Analysis .

O Complete 7-18 25203-ER-97-391 ERC Design Inputs for MP2 Peak RBCCW Temperature Analysis 0 Complete 7-19 25203-ER-97-412 ERC RBCCW Design Review - Responses to Proto Power Report I Complete 7-20 25201ER-97-413 ERC Loss of Inventory for Procedure Changes I Complete 7-21 25203-ER-97-421 ERC RBCCW Design Review Peak RBCCW Temperature

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ATTACHMENT 2 -

Millstone Unit 2 ICAVP Out-Of-Scope S3stem Inspection '

Reactor Building LW Cooling Water System Section Document Document Title Rev Schedule Status / kemarks i

Niember Type No. Date -

SECTION 8 TECHNICAL EVALUATIONS Installation of Air Accumulator for RBCOV Valve O Complete 8-1 E2-EV-97-007 Esaluation 2-RB-30.1 A/B O Complete 8-2 M2-EV-97-021 Evaluation RBCOV System Evaluation System Design Pressure RBCOV System Failure Position for Valve 2-RB-402 0 Complete 8-3 M2-EV-97449 Evaluation O Complete 8-4 M2-EV-97-060 Evaluation Separation Evaluation - Main Control Room Panel Minimum RBCCW Flow Requirement for HPSI and LPSI O Complete 8-5 M2-EV-97-070 Evaluation Pumps Design Verification of RBCOV Piping and Support GL 96 I Complete 8-6 M2-EV-97-103 Evaluation 06 Water llammer Load and Temperature Change Structural Integrity Esaluation of CAR and CEDM Cooler 0 Complete 8-7 M2-EV-98-001 Evaluation Due to Generic Letter 96-06 RBCOV System Fluid Transient O Complete 8-8 M2-EV-98-002 Evaluation RBCCW System Evaluation of Design Temperature Technical Evaluation for ESF Room EEQ Temperature O Complete 8-9 M2-EV-98-003 Evaluation Evaluation Addressing MOV 2-51-411.653 through 656 Evaluation of EEQ Canponents to New ESF Room O Complete 8-10 M2-EV-98-005 Evaluation Temperature During a LOCA CAR Cooler Outlet Temperature Instrumentation 0 . Complete 8-1I M2-EV-98-010 Evaluatien 0 Complete Tech Eval fw effec *, of-8-12 M2-EV-98-026 Evaluation Potential Effects of Ilot Pipes on Cable Ampacity Ikx Pipes in vicinity of RBCCW cables Evaluation of EEQ Bounding Enviram ental Conditions for 0 02/28/98 Tech Eval for cifects of 8-13 M2-EV-98-034 Evaluation revised room temp.due RBCCW Components to IIELB

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V ATTACHMENT 2 "

Millstone Unit 2 ICAVP Out-Of-Scope System Inspection ,

Reactor Building Clowd Cooling Water System Section DocuNnt Document Tif'e Rev Schedule Status / Remarks Date Number Tyoe No.

SECTION 9 SAFETY EVALUATIONS '

DCR 512-96078 RBCOV Rc!ief Valve Replacement 1 Complete 9-I S2-EV-97-015 Es aluation RBCCW System Rehef Valses Replacernent 0 Complete 9-2 S2-EV-97-036 Evaluation 0 Complete 9-3 52-EV-97-038 Evaluation Addition RBCCW Check Valves 2-RB-t17 and 2-RB-418 Complete 9-4 S2-EV-97-069 Evaluation Irstallation ofInter-System LOCA Relief Valves 0 Complete 9-5 S2-EV-97-074 Evaluation ECCS Pump Cooler Piping 51mlification 0 Complete 9-6 S2-EV-97-085 Evaluation 51P2 Air Accumri for RBCOV Valve 2-RB-13.l A/B 0 Complete 9-7 S2-EV-97-I 12 Evaluation Leidown Cooling th Outlet Valse 2-RB-402 Failure Position Change 2 2/16/98 Rev.2 for blales I-4 9-8 S2-EV-97-113 Evaluation h1P2 RBCOV System Shutdown Cooling Ileat Exchanger Inlet and Outlet Valve Position Change Suneillance Testing of RBCOV Valves Different fawn SIAS 0 Complete 9-9 S2 EV-97-147 Evaluation Testing 0 2/16/98 For FSARCR 9-10 S2-EV-984X)l3 Evaluation Millstone Unit 2 RBCOV Temperature Analysis RBCCW Normal Operation and Shutdown Heat leads 0 2/I6/98 firf5ARCR 9-1I S2-EV-98-0014 Evaluation Post-LOCA restoration of Spent Fuel Pool Cooling 0 2/16/98 fieFSARCR 9-12 S2 EV-98-0017 Evaluation 0 2/16/98 For 15ARCR 9-13 S2-EV-98-0019 Evaluation RBCCW Rad. hionitor Dexription ,

0 2/I6/98 fieFSARCR 9 14 S2-EV-98-0020 Evaluation RBCOV hianual Valve Identification Detail

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ATTACHMENT 2 "

Millstone Unit 2 ICAVP Out-Of-Scope System Ir*spection ,

Reactor Building Closed Cooling Water System .

Section Document Document Title Rev Schedule Status /

Number Type No. Date Remarks SECTION 10 51ISC. PIPE STRESS & SUPPORT CALCULATIONS Reactor Building Conyonent Cooling Water Pump Discharge to 6 Complete 10-1 Bechtel Stress Problem Calculation -

85 Surge Tank 0 Complete 10-2 51-COV-001 Calculation Temporary Support Design Load Calculation for RBCOV Piping O Complete 10-3 512305672-01427C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-305672 &

3 M Ii and CCN 01 0 Complete 1(h4 512305688-0142iC2 Calculation Calculation for RBCOV Pipe Support 25203-22200-305688 and CCN 01 O Compiere 10-5 512305691-01425C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-399520 &

305691 and CCN 01 O Complete 10-6 A12305733-01426C2 Calculation Calculation for RBCCW Pipe Support 25201-22200-305'e33 &

3N and CCN 01 Calculation for RBCCW Pipe Support 25203-22200-305762 0 Complete 10-7 h12305762-01422C2 Calculation and CCN 01 O Complete 10-8 512305889-01428C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-399615 &

and CCN 01 O Complete 10-9 A12305926-01429C2 Calculation Calculation for RBCOV Pipe Support 25203-22200-399632 &

6 and CCN 01 O Complete 10-10 A12305927-01430C2 Calculation Calculation for RBCOV Pipe Support 25203-22200-399659 &

305927 and CCN OI O Complete 10-1I h12350115-01431C2 Calculatmn Calculation for RIsCCW Pipe Support 25203-22200-39974I &

3E 15 and CCN OI p 9 of 17

ATTACHMENT 2 -

Millstone Unit 2 ICAVP Out-Of-Scope System inspection ,

Reactor Building Closed Cooling Water S3 stem .

Section Document Docament Title Rev Schedule Status /

Number Type No. Date Remarks O Complete 10 12 M2350116-01432C2 Calculation Calculation for RBCCW Pipe Support 25203-222(Xh399742 &

50H 6 and CCN 01 O Complete 10-13 Af235011741433C2 Calculation Calculation for RBCCW Pipe Suppon 25203-22200-399743 &

350117 and CCN 01 O Complete 10-14 M2350118-01434C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-3501IS &

399744 and CCN 01 O Complete 10-15 M2350120-01435C2 Calculation Calculation for RBCCW Pipe Support 25203-222(Xb399746 &

350120 and CCN O1 Calcul; tion O Complete 10-16 M2350127-01436C2 Calculation for RBCCW Pipe Suiport 25203-222(Xb399759 &

350!27 and CCN 01 0 Complete 10-17 M2350143-01437C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-3997SI 350143

& 350144 and CCN 01 O Complete 10-18 M2350145-01438C2 Calculation . Calculation for RBCCW Pipe Support 25203-22200-350145 &

and CCN 01 O Complete 10-19 M235015l-01439C2 '~4feulation Calculation for RBCCW Pipe Support 25203-222(Xb399792 &

350151 1 and CCN 01 Calculation for RBCCW Pipe Support 25703-22200-350153 and 0 Complete 10-20 M2350153-01440C2 Calculation 399794 and CCN 01 0 Complete 10-21 M2389008-01423C2 Calculation Calculation for RBCCW Pipe Support 25203-222(Xb389008 and 380383 and CCN 01 O Complete 10-22 M2389009-01424C2 Calculation Calculation for RBCCW Pipe Support 25203-222(Xb389(XN &

380384 and CCN 01 p.IO of 17

ATTACHMENT 2 -

Millstone Unit 2 ICAVP Out-Of-Scope System Inspection ,

Reactor Building Closed Cooling Water Syrtem .

Document Document Title Rev Schedule Status /

Section Number T3pe No. Date Remarks 0 Complete 10-23 M2405362-01442C2 Calculation Calculation for RBCOV Pipe Support 25203-22200-405362 and CCN OI 0 Complete 10-24 M2405364-01443C2 Calculation Calculation for RBCOV Pipe Sugpxt 25203-22200-4053(4 and CCN 01 0 Complete 10-25 M2405365-01444C2 ,

Calculation Calculation for RBCCW Pipe Support 25203-22200-405365 and CCN 01 0 Complete 10-26 M2405368-01445C2 Calculation Calculation for RBCOV Pipe Support 25203-22200-40536g and CCN 01 Crb i-tion for RBCCW Fipe Support 25203-22200-405402 0 Complete 10-27 M2405402-01446C2 Calculation and CCN 01 0 Complete 10-28 M2405403-01447C2 Calculation Calculation for RBCOV Pipe Support 25203-22200-405403 and CCN 01 0 2/17/98 CCN02 to be 10-29 M2405562-01448C2 Calculation Calculation for RBCOV Pipe Support 25203-222(XM05562 issued.

and CCN 01 0 Complete 10-30 M2405571-01449C2 Calculation Calculation for RBCOV Pipe Support 25203-222(xM05571 and CCN 01 0 Complete 10-31 M2405572-01450C2 Calculation Calculation for RBCOV Pipe Support 25203-22200-405572 and CCN 01 0 Complete 10-32 M2405578-01451C2 Calculation Calculation fir RBCOV Pipe Support 25203-22200-405578 and CCN 01 0 Complete 10-33 M2405579-01452C2 Calculation Calculation for RBCCW Pipe Suppert 25203-22200-405579 and CCN O!

p.11 of 17

ATTACHMENT 2 '

Millstone Unit 2 ICAVP Out-Of-Scope System Inspection ,

Reactor Building Closed Cooling Water System Sectkm Document Document Title Rev . Schedule I Status /

Number Type No. Date Remarks

~

Calculation for RBCCW Prpe Suppwt 25203-222tXM05580 0 Complete 10-34 M2403580-01453C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-22200-405581 0 Complete 10-35 M2405581-01454C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-2220(MQ5586 0 Complete 10-36 M2405586-01455C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-2220tM05587 0 Complete 10-37 M2405587-01456C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-2220040558g 0 Complete 10-38 M2405588-01457C2 Calculation and CCN 01 Calculation for RBCLW Pipe Support 25203-22200-405589 0 Complete 10-39 M2405589-01458C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-2220tM05M2 0 Complete 1040 M2405M.-01460C2 Calculation and CCN 01 Calculation for RBCOV Pipe Support 25203-22200405M3 0 Complete 10-4I M2405M3-01461C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-22200405644 0 Complete 10-42 M24G5M4-01462C2 Calculation and CCN 01 0 Complete 10-43 M2405830-01463C2 Calculation Calculation for RBCCW Pipe Support 25203-2220(M05820 and CCN 01 Calculation for RBCOV Pipe Support 25203-22200405866 0 Complete 1044 M2405866-01464C2 Calculation and CCN 01 p.12 of 17 ,

1 l

l

/TTACIIMENT 2

  • Millstone Unit 2 ICAVP Out-Of-Scope System Inspe: tion Reactor Building Closed Cm> ling Water System  ;

Section Document Document Title Rev Schedule l Status /

Number Type Na- Date Remarks

~

Caiculation for RBCCW Pipe Support 25203-222tXb450177 0 Cemplete 10-45 M2450177-Ol441C2 Calculation and CCN 01 0 Complete 10-46 M2505018-01465C2 Calculation Calculation for RBCCW Pipe Support 25203-2220rk505018 and CCN 01 0 Complete 10-47 M2505021-01466C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-505021 and CCN 01 Calculation for RBCCW Pipe Support 25203-22200-505104 0 Complete 10-48 M25051(M-01167C2 Calculation and CCN DI 0 Complete l

10-49 M2 iO5105-01.E 3C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-505105 and CCN 01 0 Complete 10-50 M2505112-01469C2 Calculation Calculation for RBCCW Pipe Support 25203-22.00-505112 and CCN 01 0 Complete 10-5i M2505182-01470C2 Calculation Calculation for RBCCW Pipe Support 25203-22200- 505!82 and CCN 01 0 Complete 10-52 M2505199-01471C2 CaRdation Calculation for RBCCW Pipe Support 25203-22200-505199 l and CCN 01 0 Complete 10-53 M2305268-01472C2 Calculation Calculation for RBCCW Pipe Support 25203-222(Xh 50526g and CCN 01 0 Complete 10-54 M2505269-01473C2 Calcu!ation Calculation for RBCCW Pipe Support 25203-222(Xh 505269 and CCN 01 0 Complete 10-55 M2505270-01474C2 Calculation Calculation for RBCCW Pipe Support 25203-222(Xb 505270 and CCN 01 p.13 of 17

, - . u , ,

. ATTACHMENT 2 ~

Millstone Unit 2 ICAVP Out-Of-Scope S3stem Inspection ,

Reactor Building Closed Cooling Water System Section Document Document Title Rev Schedule Status /

Number Type No. Date Remarks 0 Complete 10-56 A12505287-Oi475C2 Calculation Calculation for RBCCW Pipe Support 25203-22'00- 505287 and CCN 01 Calculation for RBCCW Pipe Support 25203-22200- 505334 0 Complete 10-57 A12505334-01476C2 Calculation and CCN 01 Calculation for RBCCW Pipe Support 25203-22200- 611036 0 Complete 10-58 A12611036-01809C2 Calculatioa Calculation for RBCCW Pipe Support 25203-22200- 611037 0 Complete 10-59 h12611037-01810C2 Calculation Calculation for RBC "W Pipe Support 25203-22200-f I1038 0 Complete 10-60 A12611038-01SiiC2 Calculation 0 Complete 10-61 A12611039-01812C2 Calculation Calculation for RBCCW Pipe Support 25203-22200-611039 O Complete 10-62 A1P2-056-90-1373GP Calculation Excess Piping and llanger Removal (RBCCW IIX 18-A,18-B,18-C)

Stress Calc for RBCCW Retum lleader to RBCCW Pumps 1 Complete 10-63 PROBL150-01478C2 Calculation I Complete 10-M PROBLI51-01479C2 Calculation Stress Cale for RBCCW Supply to CEA Drive Cooler Stress Cale for RBCCW Retum and Supply to RCP Cooler PDT and I Complete 10-65 PROBL152-01480C2 Calculation Quench Tank fleat Exchanger I Complete 10-66 PROBLl75-01490C2 Calculation Stress Cale for RBCCW Return from CEA Drive Coolers Calculation 0 2/17N8 CCN to be issued.

10-67 PROBLO76-01913-C2 Stress Analysis of RBCCW Return Piping fron: Spent Fuel Pool to 20" IIBD(B)-132 Calculation 0 2/17N8 CCN to be issued.

10-68 PROBL080-02(M l-C2 Stress Analysis of RBCCW Pump Inlet Piping Ileader 'A' from El.(-)

12*-6" to El.(-) 8*-6" Calculation 0 2/17N8 CCN to be issued.

10-69 PROBLI33-01877 C2 Stress Analysis of RBCCW Piping from Containment Air Recire.

Cooler X-35A to Containment Penetration #32 Calculation 0 2/17N8 CCN to be issued.

10-70 PROBL153-02(M2-C2 RBCCW Piping - CEA Cooler X-34B O.det Piping between El. 4g .

9" and El. 4'- 10 3/4" Calculation 0 Complete 10-71 RBCCW-02135-C2 Calculation for Pipe Support 405129 l p.14 cf 17

m m -- -

NrTACHMENT 2 ~

l Stillstone Unit 2 ICAVP Out-Of-Scope System Inspection Reactor fluilding Closed Cooling Water System Section Document Document Title Rev Schedule Status /

Number Type No. Date Remarks 0 Compi.te 10-72 RBCCW-02136-C2 Calculation Calculation for Pipe Support 60573 0 Complete 10-73 RBCCW-02137-C2 Calculation Calculation for Pipe Support 305923 Calculati.,n 0 Comp!cte Itb74 RBCCW-02138-C2 Calculation for Pipe Support 405783 Calculation 0 Complete 10-75 RBCCW-02140-C2 Calculation for Pipe Support 505227 Calculation 2 Complete Traasferred to NDS 10-76 S&A 2986-Cl Piping Stress Problem #S6 for procewing 2 Complete Transferred to NDS 10-77 S&A 2986-C2 Calculation Analysis Problem #75 for processing Calculation I Co plete Transferred to NDS 10-78 S&A 2986-C3 Analysis Problem #73 for processing i Complete Transterred to NDS 10-79 S&A 2986-C4 Calculation Analysis Problem #79 for processing 3 2/17NS CCN to be issued.

! 3o go Stress Problem 61 Calculation hiillstone Unit 2 RBCCV. ..aps to lleat Exchangers 3 2/17N8 CCN to be issued go_gg Stress Problem 62 Calculation hlillstone Unit 2 RBCCW Pumps to RBCCW Surge Tanks Stress Problem hiillstone Unit 2 RBCCW Supply to X-25A fleat Exchanger 2 2/I7N8 CCN to le issued.

3o.g3 Calculation 2 2/17N8 CCN to be issued.

iggg3 Stress Problem 66 Calculation RBCCW from IIcat Exchangers X-ISA, X-18B, and X-18-C and CCN I 2 2/17N8 CCN to be issued.

io.g4 Stress Problem 67 Calculation hiillstone Unit 2 RBC4 , ply to X-23B htillstone Unit 2 RBCCW 1[eturn from X-23A Ileat Exchanger 2 2/17NS CCN to be issued.

10-85 Stress Problem 68 Calculation 2 2/17N8 CCN to be issued.

10-86 Stress Problem 69 Calculation hiillstone Unit 2 RBCCW Piping from ficat Exchanger X-28B 2 2/17N8 CCN to be issued.

10-87 Stress Problem 70 Calculation hiillstone Unit 2 RBCCW Stress Problem 81 hiillstone Unit 2 RBCCW Supply to D.E. Cooler and Letdow n lleat i 2/!7N3 CCN to be swued.

g o.gg Calculation Exchanger Stress Problem 82 hiillstone Unit 2 RBCCW Supply to D E. Cooler 2 2/I7N8 CCN to be issued.

10.g9 Calculation 1 2/17N8 CCN to be issued.

g g.99 Stress Problem 83A Calculation hiillstone Unit 2 Pump Suction from RBCCW Surge Tank T-3 p.15 of 17 q , ,

ATTACIIMENT 2 '

31illstone Unit 2 ICAVP Out-Of-Scope System Inspection Reactor Building Closed Cooling Water System Section Document Document Title Rev Schedule Status /

Number Type No. Date Remarks Stress Problem 83B 2 2/17N8 CCN t'o be issued.

o_9 i Calculation hiihtone Unit 2 Pump Suction from RBCCW Surge Tank to 20" IIBD Stress Problem 84 3 2/17N8 CCN to be issu-d.

g o_9; Calculation hiillstone Unit 2 Pump Suction from RBCCW Surge Tank Stress Problem 85 6 2/17N8 CCN to be issued.

10-93 Calculatum Millstone Unit 2 Reactor Building Ckised Coohng Water Stress Probiem 87 Millstone Unit 2 RBCCW Return from Spent Fuel Pool IIcat i 2/17NS CCN to be issued.

3o_94 Calculation Exchangers 20A & 20B and Evaporator Coolers 11-25 & 1126 Stress Problem 88 hiillstone Unit 2 RBCCW Return from Spent Fuel Pool ifeat 2 2/17NS CCN to be issued.

10-95 Calculation Exchanger 20B and Evaporator Stress Problem 125 2 2/17N8 CCN to be issued.

10-96 Calculation Millstone Unit 2 RBCCW Surge Tank Vem and Drain Stress Problem 126 Millstone Unit 2 RBCCW Supply to Oil Cooler on Pump P-40D 1 2/17N8 CCN to be issued.

l l o_97 Calculation 1 2/17N8 CCN to be issued.

g9 93 Stress Problem l~ Calculation Millstone Unit 2 RBCCW Return from Engineered Safeguard Coil, Stress Problem i 3 2/17N8 CCN to be issued.

10-99 Calculation Millstone Unit 2 RBCCW Supply to Engineered Safeguards Room Recire. Coils Stress Problem 129 Millstone Unit 2 RBCCW Return from Engineered Safeguard Room 3 2/17N8 CCN to be issued.

io goo Calculation Stress Prob'em I39 Millstone Unit 2 RBCCW Supply to Oil Cooler on Pump P-40A 1 2/17N8 CCN to be issued.10-101 Calculation Stress Problem 140 2 2/17Nf CCN to be issued.

io_i92 Calculation Millstone Unit 2 RBCCW Return from Oil Cooler Stress Problem 14i 2 2/17N8 CCN to be issued.10-103 Calculation Millstone Unit 2 RBCCW to Oil Cooler 1 2/17N8 CCN to be issued.10-104 Stress Problem 142 Calculation Millstone Unit 2 RBCCW Supply to Oil Cooler on P-40C Stress Problem 143 1 2/17NK CCN to be issued.10-105 Calculation Millstone Unit 2 RBCCW from Oil Coolers I 2/17N8 CCN to be issued.10-106 Stress Problem 144 Calculation Millstone Unit 2 RBCCW Supply to Oil Cooler on P-40A 1 2/17N8 CCN to be issued.10-107 Stress Problem 145 Calculation Millstone Unit 2 RBCCW to Oil Cooler Stress Problem 147 5 2/17N8 CCN to be issued.10-108 Calculation Millstone Unit 2 RBCCW Supply to Evaporator lleater & Spent Fuel

& Quench Tank IIcat Exchanger p.16 of 17

- - . - - - .--. .. -a ..- - - .. . l-.+ .

i

.- .....-- - r---- . - --- . . . - . ...m- .--. .. ... . . ...

ATTACHMENT 2 '~

Millstone Unit 2 ICAVP Out-Of-Scope System Inspection ,

Reactor Building Closed Cooling Water System Section l

Document Document Title Rev Schedule Status /

Number Type No. Date Remarks -

Stress Problem 148 2 2/17N8 CCN ti> be issued.10-109 Calculation Millstone Unit 2 RBCCW to Quench Tank Cooler X-24 Stress Problem 149 I 2/17N8 CCN to be issued.10-110 Calculation Millstone Unit 2 RBCCW Return from PDT and Quench Tank lie t Exchanger Stress Problem 152 Millstone Unit 2 RBCCW Return 11eaders from Exchangers 2 2/17N8 CCN to be issued.10-111 Calculation go.gg2 Stress Problem 155 Calculation Millstone Unit 2 RBCCW Return fro CEA Drive Coolers X-34A I 2/ lins CCN to be issued.

Stress Problem 167 3 2/17N8 CCN to be issued.

10-l13 Calculation Millstone Unit 2 RBCCW Return from Oil Cooler on P-40A Stress Prob!cm 168 Millstone Unit 2 RBCCW to Quench Tank lieat Exchanger X-82 1 2/17N8 CCN to be issued.10-114 Calculation Stress Problem 169 Millstone Unit 2 RBCCW from Quench Tank licat Exchanger X-82 2 2/17N8 CCN to be issued.10-115 Calculation Stress Problem 176 2 2/17N8 CCN to be issued.10-116 Calculation Millstone Unit 2 RBCCW Supply lieader to Boric Acid Evaporator Cooler p.17 of 17

" Docket No. 50-336 B16923 Y

Attachment 3 Ministone Nuclear Power Station, Unit No. 2 ICAVP Out-of-Scope System inspection Reactor Building Closed Cooling Water System

-Implementation items February 1998

v,wca U.S. Nuclear Regulatory Commission ~

B16923 Attachment 3\Page 1 ATTACHMENT 3 -IMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection Reactor Building Closed Cooling Water Syste.m SECTION 1 DESIGN CHANGES DCN's Materials PORC/MGT AWOs Misc- Turn Over ENG. Close-Out Item / Description Approval items For Release Number Date Retest for OPS DM2-S-1196-95 Rev.0 M2-95-11393 TRACKED BY j OPEN CPEN OPEN 2-064-95 RBCCW System; Air Accumulators DM2-S-1323-95 #2-95-386 Partial Partial for 2-RB-13.1 A&B DM2-S-0067-96 11/01/95 #2-96-06K 2/14/96 2/15/96 DM2-S-0088-96 Rev.1 (not an EWRW)

DM2-00-0638 97 #2-97-172' DM2-01-0638-97 8/ M 7 DM2-02-0638-97 JM2-03-0638-97 DM2-00-1420-96 #2-97-090 M2-87-01653 EWR# COMPLETE COMPLETE OPEN M2-96078 RBCCW System Relief Valve DM2-01-1420-96 4/11/97 M2-95-05511 M2-95-316A 12/12/97 1/28/98 Repla:ement DM2-02-1420-96 DE2-DT-546- M2-95-05512 M2-96-170 DE2-DT-2466- DE2-0T-0M9 DM2-03-1420-96 97 M2-95-07218 SQR-2-97-001 97 DM2-00-1421-96 M2-95-12170 NCR 297-297 r DM2-01-1420-96 M2-95-12171 NCR 297-300 DM2-01-1421-96 M2-95-12172 D'A2-00-0192-97 M2-96-05934 DM2-01-1421-97 M2-97-01862 DM2-02-1421-97 M2-97-01863 M2-97-01951 DM2-00-0192-97 M2-97-01952 DM2-01-0598-97 M2-97-01953 M2-97-01954 DM?-00-1390-96 Approved M2-97 01858 EWR# COMPLETE COMPLETE COMPLETE 7 M2-96581 Modification of 4 Indicating Light DM2-01-1390-96 2f28/97* M2-97-01865 M2-96-048 /26/97 Circuits DM2-02-1390-96 DE2-DT-443-97 l

U.S. Nuclear Regulatory Commission -

B16923 Attachment 3\Page 2 ATTACHMENT 3 -IMPLEMENTATION ITEMS

' Millstone Unit 2 ICAVP Out-Cf-Scope System inspection Reactor Building Closed Cooling Water System SECTION 1 DESIGN CHANGES Materials PORCIMGT AWOs Misc- Turn Over ENG- Close-Out Itemt Description DCN's Approval items For Release Number Date Retest fer OPS l COMPLETE OPEN RBCCW Surge DM2-00-1210-96 #2-97-121 M2-97-04420 EWR# COMPLETE M2-97015 DM2-01-1210-96 5/30/97* M2-98-00020 M2-96-078 1/11/98 1/12/98 Tank Make-up Line DM2-00-0268-97 DE2-DT-632- M2-98-00021 BJ 2-97-059 DE2-DT-0139- DE2-DT-0174-9 Check Valves DM2-01-0268-97 97 BJ 2-97-060 98 NCR 297-597

  1. 2-97-160 EWR8 OPEN OPEN OPEf-!

M2-97016 RBCCW System DM2-00-0458-97 DM2-00-0554-97 7/30/97

  • M2-95-3168 Partial Partial j Relief Vr:ve DM2-00-0347-97 DE2-DT- M2-96-170 1/10S8 1/12/98 Replacement -

Phase 2 DM2-00-0449-97 1143-97 DE2-DT-0148- DE2-DT-0149-9 DM2-00-0663-97 98 DM2-00-0443-97 DM2-00-0345-97 DM2-00-0346-97 DM2-00-0347-97 DM2-00-0449-97 DM2-00-0663-97 DM2-01-0449-97 DM2-00-0598-97

-._J

I U.S. Nuclear Regulatory Commission

  • 816923 Attachment 3\Page 3 ATTACHMENT 3 - IMPLEMEttTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection '

Reactor Building Closed Cooling Water System SECTION 1 DESIGN CHANGES -

Description DCN's Materials PORCIMGT AWOs Misc. Turr. Over ENG. Close-Out item / -

Number Approval items For Release Date Retest for OPS RBCCW System DM2-00-0344-97 Rev.A M2-97-04523 EWR8 COMPLETE COMPLETE OPEN M2-97018 DM2-01-0344-97 6/10/97* M2-97-04565 M2-92-172 10/30/97' 11/14/97 Installation of Intersystem LOCA DM2-02-0344-97 Rev. O M2-97-04567 Procedure DE2-DT-2040- DE2-DT-1484-9 Relief Valves DM2-03-0344-97 #2-97-165 M2-97-04960 SP 2605D 97 DM2-00-0469-97 8/08/97 M2-97-04987 DM2-01-0469-97 M2-97-05135 NCR OM2-02-0469-97 M2-97-05145 297-231 DM2-03-0469-97 M2-97-06100 297-233 DM2-04-0469-97 M2-97-06105 297-282 DM2-05-0469-97 M2-97-06106 297-298 DM2-06-0469-97 M2-97-06107 297-307 DM2-00-0827-97 M2-97-06111 297-381 DM2-01-0827 97 M2-97-06112 297-408 DM2-00-1055-97 M2-97-06113 DM2-01-G335-97 M2-97-06114 DM2-02-0827-97 M2-97-06283 M2-97-08580 M2-97-04752 M2-97-04753 .

U.S. Nuclear Regulatory Commission -

B16923 Attachment 3\Page 4 ATTACHMENT 3 -IMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection .

~

Reactor Building Closed Cooling Water System SECTION 1 DESIGN CHANGES ~

Description - DCN's - Materials - PORC/MGT AWOs Misc. Turn Over ENG- Close-Out Item /

Approval items 'For Release Number Date Retest for OPS ECCS Cooler Piping DM2-00-0645-97 #2-97-241 M2-97-07788 EWR8 COMPLETE COMPLETE - OPEN M2-97025 Modifications DM2-00-0913-97 12/03/97' M2-97-07789 M2-97-143 1109/98 1/20/98 DM2-01-0913-97 M2-97-07790 NCR 298-012 DE2-DT-0127- DE2-DT-0128-9 DM2-02-0913-97 M2-97-09949 25203- 98 DM2-03-0913-97 M2-97-09950 26022,Sht.3 DM2-00-0639-97 M2-97-08703 DM2-01-0640-97 M2-97-08705 DM2-00-0919-97 M2-97-09948 DM2-01-0919-97 DM2-02-0919-97 DM2-00-0646-97 DM2-01-0646-97 l

DM2-01-0914-97 DM2-02-0914-97 DM2-00-0138 98

U.S. Nuclear Regulatory Commission -

B16923 Attachment 3\Page 5 ATTACHMENT 3 -lMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection ,

Reactor Building Closed Cooling Water System lSECTION 1 DESIGN CHANGES Close-Out Description DCffs Materials PORCIMGT AWOs Misc. Turn Over ENG.

Item /

Approval items For Release Number Date Retes', for

  1. 2-97-173 M2-97-07390 EWR* COMPLETE COMPLETE OPEN M2-97029 Limitorque Actuator DM2-00-0845-97 Replacements for 8'T 707* M2-97-08633 M2-97479 10/1M7 11/127 DM2-00-1035-97 DE2&-18559 MOVs 2-RB-30.1 A. DM2-00-1036-97 02 ~

M2-97-05386 8 and 2-RB-37.2A,8 M2-97-08660 DM2-00-1037-97 R 1 DM2-00-1038-97 82-97-205 M2-97-05296 DM2-03-0774-97 M2-97-08802 DM2-04-0774-97 M2-97-07346 DM2-00-0774-97 M2-95-13630 DM2-01-0774-97 M2-97-08525 DM2-02-0774-97 M2-97-08707 DM2-00-0776-97 M2-97-08614 DM2-00-0804-97 M2-97-08526 DM2-01-0804-97 M2-97-05259 DM2-00-0813-97 M2-97-0701 DM2-01-0813-97 M2-97-07265 DM2-01-0820-97 M2-97-07266 DM2-00-0823-97 M2-97-05295 DM2-00-1526-97 M2-97-05385 DM2-00-0812-97 M2-97-06642 M2-97-08614 M2-97038 Letdown Coohng Approved EWR#

Heat Exchanger #2-98-020 M2-97-106 Outlet Valve 2-RB- 1/28/98 402 Failure Position

v -

U.S. Nuclear Regulatory Commission '

B16923 Attachment 3\Page 6 ATTACHMENT 3 -lMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection .'

Reactor Building Closed Cooling Water Systec SECTION 1 DESIGN CHANGES DCN's Materials PORC/MGT AWOs Misc. Turn Over ENG. Close-Out ltem/ Description Approval items For Release ,

Number '

Date Re* tst for OPS DM2-00-0147-98 Approved

  • M2-97-144 M7-97039 Shutdown Cookn9 Heat Exchanger #2-97-241 DM2-00-0065-98 Flowrate Change 12/0M7 DM2-00-0016-98 *# "9 DM2-01-0016-98 "*

DM2-02-0016-98 Shutdown Cooling DM2-00-0301-97 Approved M2-97-03174 EWR# COMPLETE COMPLETE OPEN M2-97514 Heat Exchanger DM2-01-0301-97 7/19/97 M2-97-08170 M2-96-113 11/03/97 11/14/97 DM2-02-0301-97 M2-97-08208 NCR DE2-DT-2080- DE2-DT-2191-9 (X238) Gasket 97 Replacement DM2-03-0301-97 297-397 DM2-04-0301-97 297-415 DM2-05-0301-97 297-437 RO DM2-06-0301-97 297-437 R1 297-441

- 1

. . . . . - - . . - . - - - - . . _ . - - - - . . . . - - - . . . . . - - . -j

U.S. Nuclear Regulatory Commission '

B16923 Attachment 3\Page 7 r

ATTACHMENT 3 -IMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection ,,

Reactor Building Closed Cooling Water System ,

SECTION 1 DESIGN CHANGES ltem! Description DCN's Materials . PORC/MGT AWOs Misc- Turn Over ENG- Close-Out Number Approval items For Release Date Retest for OPS M2-97519 Genenc Motor DM2-01-0928-97 Approved M2-97-07641 EWR8 OPEN OPEN OPEN Operated Valve DM2-00-0840-97 '8/06/97 M2-97-07642 M2-96-079 Partial Partial (MOV) Modification DM2-00-0367-97 M2-97-07643 8/29/97 9/05/97 DM2-00-0465-97 Rev.1 M2-97-07644 NCR 297-130 DE2-DT-1388- 9/23/97 DM2-01-0465-97 Approved M2-97-08165 NCR 297-241 97 11/13/97 j DM2-02-0465-97 11/06/97 M2-97-09202 NCR 297-352 9/20/97 DE2-DT-1857- 1 DM2-00-0338-97 M2-97-05403 10/11/97 97 )

DM2-02-0838-97 M2-97-08903 10/14/97 11/15/97 DM2-00-0929-97 M2-97-09038 10/31/97 DE2-DT-2185-DM2-00-0928-97 M2-97-10025 DE2-DT-1867- 97 DM2-00-1176-97 M2-97-10029 97 12/19/97 DM2-00-1178-97 M2-97-05389 11/15/97 ~ DE2-DT-2532-9 DM2-00-1031-97 M2-97-10363 DE2-DT-2184- 1/14/98 DM2-00-1030-97 M2-97-10026 G7 DE2-DT-0059-9 DM2-00-1321-97 M2-07-10030 ' 12/13/97 DM2-00-1112-97 M2-97-05390 DE2-DT-2475-DM2-001

  • 13-97 M2-97-10369 97 DN2-00-1114-97 M2-97-11436 1/06/98 DM2-00-1094-97 M2-97-08266 DE2-DT-0002-DM2-02-1094-97 M2-97-04997 98 DM2-00-1162-97 M2-97-11436 1/14/98 O!/.-00-0692-97 M2-97-08266 DE2-DT-0144 DM2-00-1173-97 M2-97-04997 98 DM2-01-1173-97 1/17/98 DM2-00-1155-97 DE2-DT-0179-DM2-02-1155-97 98 DM2-03-1155-97 DM2-00-1169-97 DM2-00-1175-97 DM2-00-1172-97 DM2-01-1173-97 i

i 4

U.S. Nuclear Regulatory Commission .

B16923 Attachment 3\Page 8 ATTACHMENT 3 -IMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection ,,

Reactor Building Closed Cooling Water System SECTION 1 DESIGN CHANGES Item / Description DCN's Materials PORC/MGT AWOs Misc. Turn Over ENG. CI E ut Approval items For Release Number Date Retest for OPS M2-97519 Genenc Motor DM2-00-1022-97 Operated Valve DM2-00-1165-97 (MOV) Modification DM2-00-1185-97 DM2-01 1173-97 DM2-00-1486-97 DM2-00-1499-97 DM2-00-1540-97 DM2-00-1504-97 DM2-00-1485-97 DM2-00-1484-97 DM2-00-0739-97 DM2-00-1500-97 Approved M2-97-07457 EWR8 N/A N/A M2-97526 RBCCW Shutdown Flow Loop 9/11/97 M2-95-330 Modification RBCCW System DM2-00-103 ., Approved M2-97-09992 EWRs COMPLETE COMPLETE M2-97528 Mi'imum 10/14/97 M2-97-09995 M2-97-146 1/11/98 1/20/98 DM2-01-1032-97 DE2-DT-0151- DE2-DT-0366-9 Recirculation Orifice DM2-02-1032-97 M2-97-09993 NCR 297-594 M2-97-103% N DM2-03-1032-97 BJ 2-97-0 DM2-04-1032-97 BJ 2-97-060 DM2-05-1032-97 DM2-00-0028-98 Di 12-00-0033-98 RBCCW Pipe DM2-00-0044-98 Approved EWR#

M2-98004 Support DM2-00-0064-98 #2-98-020 M2-97-145 DCR Modifications for 1/28/98 GL-96-06 Water Hammer Loads SECTION 2 TEMPORARY MODS 1

. . . = , . . .. .

., . . .__..;. _ . .; ..)

U.S. Nuclear R@gulatory Commission ,

816923Attachfrent 3Page 9

(

ATTACHMENT 3 -IMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System inspection ,,

Reactor Building Closed Cooling Water System SECTION 1 DESIGN CHANGES DCN's Materials PORC/MGT AWOs Misc. Turn Over ENG. Close-Out Item / Description Approval items For Release Number Date Retest for OPS Approved L4/A installation Date Remwal Date M2-95-126 RBCCW Valves 2 RB-13.1 A & B 10/19/95 l

  1. 2-95-380 10/20/95 1/30/98

} Backup Air Supply SECTION 3 PROCEDURES Document Title Rev Schedule Status 1 Remarks Docuraent Number Type No. Date Procedure Loss of RBCCW 3 02/28/98 Note 2 AOP 2564 Procedure RBCCW System 17 02/16/98 Note 2 OP 2330A Procedure Containment Sump and SDC Heat Exchanger 14 Note 1 SP 2604G RBCCW Outlet Valve Tests, Facihty 1 Procedure Containment Sump and SDC Heat Exchar:ger 14 Note 1 SP 2604H RBCCW Outlet Valve Tests, Facilrty 2 Procedure "A" RBCCW Pump Tests 7 Note 1 SP2611A SP26118 Procedure "C" RBCCW Pump Tests 7 Note 1 SP2611C Procedure RBCCW System Abgnment and Valve Tests. Faciltty 5 Note 1

- 1 and Cross-Ties SP2611D Procedure RBCCW System Abgnment and Valve Tests, Facility 5 Note 1 2

Procedure RBCCW Valve Tests - Shutdown 5 Note 1 SP2611E SP2611F Procedure RBCCW Pumps Discharge Check Va've IST 0 Note 1 Procedure "B" RBCCW Pump Tests 0 Note 1 SP2611G Procedure Luss of Primary Coolant 15 Note 2 EOP 2532 EOP 2540 Procedure Functional Recovery 17 Note 2 OP 2201 Procedure Plant Heatup 26 Note 2 OP 2207 Procedure Plant Cooldown 21 Note 2 _

Note 1 - These procedures are revised as part of the release to operations for the modifications identified in Section 1 Note 2 - The OP, AOP and EOPs are revised as part of the Unrt restart and wil incorporate the RBCCW design basis calculation and modtfication char.;ies

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4 U.S. Nucle:r Regulatofy Commission '

B16923Attachmef t 3\Page 10 ATTACHMENT 3 -IMPLEMENTATION ITEMS Millstone Unit 2 ICAVP Out-Of-Scope System le. pection ,,

Reactor Building Closed Cooling Water System SECTION 3 PROCEDURES Document Document Title Rev Schedule l Status f Remarks Number Type No. Date {

l SECTION 4 OPERATOR TRAINING AOP 2564 Training Training on system modification dunng Cycle 3 OP 2330A Training Training on system modification during Cycle 3 EOP 2540 Training Training on system modification dunng Cycle O EOP 2532 Training Training on system modification during Cycle 3 SECTION 5 SIMULATOR UPGRADES M2-97038 Simulator upgrade for DCR M2-97038 for future change to provide Control Room endication of R8 402 position.

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