ML17334B473

Summary of 930407 Meeting W/Util in Rockville,Md to Discuss Planned Installation of Digital Processing Equipment in RPS for Both Units.List of Attendees & Viewgraphs Encl

ML17334B473
Person / Time
Site:	Cook
Issue date:	04/26/1993
From:	Bill Dean Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9305030321
Download: ML17334B473 (96)

Text

April 26, 1993 Docket Nos.

50-315 and 50-316 LICENSEE: Indiana Michigan Power Company (IMPC)

FACILITY: D.

C.

Cook, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

OF APRIL 7, 1993 On April 7, 1993, representatives of the American Energy Power Services Corporation (parent company of IHPC) and Foxboro met with members of the NRC staff and contractors from Idaho National Engineering Laboratory (INEL) in Rockville, Maryland to discuss the planned installation of digital processing equipment in the reactor protection systems (RPS) for both units.

A list of attendees is enclosed (Enclosure 1).

This meeting was a followup meeting from ones that were held in April and December 1992 and was timed to coincide with the inclusion of the INEL contractors to the project for review and audit purposes.

The licensee provided a brief history of the project, and discussed the proposed schedule and project organization.

A Foxboro representative described the instrumentation that will be installed and the licensee then briefly discussed its plans for conducting the verification and validation process for the project.

The final part of the licensee's presentation was associated with how the pertinent documentation is arranged and the scope of their license amendment package.

The licensee described the type and volume of information that was available to support the staff's review process.

This included an extensive effort to cross-reference the information to any staff issues or questions that have arisen in the past.

A copy of the licensee's presentation is enclosed (Enclosure 2).

The INEL contractors asked a number of questions of a technical nature to become better familiarized with the status of the licensee's project.

The meeting then concluded, though several of the licensee's technical representatives remained to more thoroughly answer some of the questions posed to them by the staff and INEL contractors.

Original signed by William H. Dean, Sr. Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/enclosures:

See next page Office Name Date LA:PD III-1 HShuttleworth PH: P I I-1 WDe n/v b sw D PDIII-1 LHars 930503032k 930426 PDR ADOCK 050003i5 P

PDR

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DISTRIBUTION LIST FOR MEETING

SUMMARY

April 7, 1993 Docket File w/encls.

NRC 5 Local PDRs PDIII-1 RDG File T. Hurley F. Hiraglia J. Partlow J.

Roe J. Zwolinski L. Harsh W.

Dean OGC E. Jordan, HNBB 3701 J.

Wermiel 10/0/24 J.

Hauck 8/H/3 S.

Rhow 8/H/3 ACRS (10)

G. Grant, EDO W. Shafer, RIII E. Schweibinz, RIII B. Jorgensen, RIII

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Indiana Michigan Power Company CC:

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street

Lansing, Michigan 48913 Township Supervisor Lake Township Hall post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.

Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.

W.

Washington DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1

State Capitol

-'Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0.

Box 30195

Lansing, Michigan 48909 Donald C.

Cook Nuclear Plant Mr. S. Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216 E.

E. Fitzpatrick Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

ril 993 D.

C.

Cook Units 1 and 2

RPS Modification Meetin List of Attendees ENCLOSURE 1

Name Bill Dean Ed Schweibinz Joe Joyce Sang Rhow Paul Loeser Jim Stewart Jeb Kingseed Bill Sotos Doug Malin Hal Hoffman Robert Carruth Mark Wilken James Keiper Jeff Hansen Bob Richards Or anization Senior Project Manager, PDIII-1/NRC Senior Project Engineer, RIII/NRC HICB/NRR HICB/NRR HICB/NRR HICB/NRR AEPSC AEPSC AEPSC AEPSC AEPSC AEPSC Foxboro EG&G/INEL EG&G/INEL

COOK NUCLEAR PLANT Bridgman, Michigan

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PROJECT HISTORY, SCOPE AND STATUS................. W. G. SOTOS TECHNICALDESCRIPTION AND COMPARISON WITHCONNECTICUTYANKEEAPP LIGATION................W.G. SOTOS OVERVIEWOF FOXBORO INSTRUMENTATION.............J.T. KEIPER SOFTWARE VERIFICATIONANDVALIDATION......... H. H. HOFFMAN OVERVIEW OF SUBMITTAL..........~............................

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PROJECT HISTORY, SCOPE AND STATUS W. G. SOTOS

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EQUIPMENT INITIALSTUDY (INITIATED1988)

H-LINE EQUIPMENT END OF LIFE DECLININGVENDOR SUPPORT DECLINING ELECTRONIC PIECE/PART LEVEL SUPPORT DESIGN PHILOSOPHY USE MATURE PRODUCT LINES NO FUNCTION CHANGES NO CHANGES IN SEPARATION NO CHANGE IN DIVERSITY NO DIGITALCOMMUNICATIONNETWORKS USE EXISTING FIELD WIRING MINIMIZEIMPACT ON TECHNICIANS AND OPERATORS MINIMIZEIMPACT ON PLANT PROCEDURES MAXIMIZEPRE-INSTALLATIONTESTING

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COMBUSTION ENGINEERING CONTRACT (OCTOBER 1989)

SCOPE REACTOR PROTECTION SETS CONTROL GROUP PROCESS INSTRUMENTATION CONTROL PANEL HARDWARE WATER SYSTEMS INSTRUMENTATION FABRICATION START (NOVEMBER 1990)

FACTORY ACCEPTANCE TEST START (SEPTEMBER 1991)

C E REACTOR PROTECTION SET INVOLVEMENTENDED (MARCH 1992)

NO INVOLVEMENTON SAFETY RELATED WORK TAYLOR EQUIPMENT IS KEPT IN NON-SAFETY WORK FOXBORO CONTRACT (APRIL 1992)

SCOPE REACTOR PROTECTION SETS

CURRENT PROJECT FOXBORO REACTOR PROTECTION SYSTEM TAYLOR CONTROL GROUP PROCESS INSTRUMENTATION WATER SYSTEMS INSTRUMENTATION CONTROL PANEL HARDWARE AMSAC (CHANGED FROM FOXBORO TO MAINTAIN DIVERSITY'

SCOPE OF WORK REPLACE EXISTING ANALOG FOXBORO H-LINE EQUIPMENT WITH NEW FOXBORO SPEC 200 AND SPEC 200 MICRO HARDWARE IMPACTS 13 REACTOR PROTECTION PROCESS INSTRUMENTATIONCABINETS EACH UNIT

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TECHNICALAREAS OF INTEREST

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ENVIRONMENTALQUALIFICATION

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SEISMIC QUALIFICATION

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EMI/RFI SUSCEPTIBILITY

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POWER

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INDEPENDENCE/DIVERSITY

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FAILURE MODES AND EFFECTS

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RELIABILITY

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FUNCTIONALITY

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VERIFICATION AND VALIDATION

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TESTING

PROJECT ORGANIZATIONAND MANAGEMENT

,AEPNO DEDICATED PROJECT TEAM MANAGEMENT LEAD ENGINEER SUPPORTING I&C ENGINEERS CONTRACTING CONSULTING ENGINEERS MECHANICALAND ELECTRICAL DESIGNERS PLANT PROJECT ENGINEER PLANT I&C PERSONNEL QUALITYASSURANCE NUCLEAR SAFETY AND LICENSING CURRENT STAFFING 17 FULLTIME PERSONNEL 28 PART TIME (GREATER THAN 25% OF AVAILABLE TIME)

FORMAL STATUS AND ACTION ITEM LISTS REGULARLY UPDATED

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PROJECT SCHEDUL'E (UNIT 2 UNLESS NOTED)

RPS DOCUMENTATION COMPLETE VENDOR DRAWING/DESIGN FACTORY ACCEPTANCE TEST COMP LETION COMPLETE MAY1993 AEP DRAWING/DESIGN COMPLETION JULY 1993 PRE-INSTALLATIONTEST COMPLETION AUGUST. 'I 993 r

PLANT PROCEDURE COMPLETION DECEMBER 1993 UNIT 1 INSTALLATION FEBRUARY 1994

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEEAPPLICATION W. G. SOTOS

TECHNICAL DESCRIPTION AND COMPARISON WITH CONNECTICuT YANKEE (C.Y.) APPLICATION FUNCTIONAL HARDNARE/HARDWARE APP LICATIONS SOFTWARE/SOFTWARE APP LICATIONS

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TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEEAPPLICATION FUNCTIONAL-REACTOR PROTECTION AND ESF CONNE Ti UT YANKEE D.. COOK PRESSURIZER LEVEL PRESSURIZER LEVEL PRESSURIZER PRESSURE PRESSURIZER PRESSURE REACTOR COOLANT FLOW REACTOR COOLANT FLOW S/G NARROW RANGE LEVEL S/G NARROW RANGE LEVEL S/G STEAM FLOW S/G STEAM FLOW

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

FUNCTIONAL-REACTOR PROTECTION AND ESF GONNE I

KE S/G PRESSURE S/G PRESSURE FEEDWATER FLOW FEEDWATER FLOW Tavo~ ~T (THOT, TCOLD) avo aT (THOT, TCOLD)

CONTAINMENTPRESSURE TURBINE FIRST STAGE PRESSURE CONTAINMENTPRESSURE TURBINE IMPVLSE PRESSURE

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

FUNCTIONAL-OTHER SAFETY RELATED APPLICATIONS CONNECTICU Y NKEE WIDE RANGE RCS TEMPERATURE WIDE RANGE RCS PRESSURE COO NUCLEAR PLANT WIDE RANGE RCS TEMPERATURE WIDE RANGE RCS PRESSURE RWST LEVEL CONTAINMENTLEVEL AUXIIIARY FEEDWATER FLOW TSAT INPUT SELECT CONDENSATE STORAGE TANK,LEVEL

TECHNICAL DESCRIPTION AND COMPARISON NITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

FUNCTIONALDIFFERENCES REACTOR PROTECTION AND ESF - NONE OTHER SAFETY RELATED - ADDITIONALAPPLICATIONS FOR REG GUIDE 1.97

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

HARDWARE CONNE I

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N-2AO-L2C-R D

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N-2AO-V2H (CUSTOM)

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N-2AO-L2C-R

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

HARDWARE CONNEC ICU YAN E DIGITAL MODULES'-2CCA-S N-2CCA-D D..

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N-2AX+DP11 N-2ARPS05-A6 N-ARPS-A6 POWER SUPPLIES/DISTRIBUTION:

N-2AX+DP11 N-2AX+DP10-E N-2ARP505-A6 P0300CQ

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED).

HARDWARE CONNEC NESTS:

N-2ANU-DM D

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N-2ANU-DM RACKS NEW N-2ES SERIES RACKS:

EXISTING AMCO FX78 SERIES

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

HARDWARE DIFFERENCES ANALOG INPUT MODULES 50 - MA VS 4 - 20 MA ANALOG OUTPUT MODULES - N - 2AO-V2H MODIFIEDTO PROVIDE ISOLATION CONTACT OUTPUT MODULES - NONE DIGITALMODULES - NONE POWER SUPPLIES/ DISTRIBUTION MINOR FUSING DIFFERENCES IN POWER DISTRIBUTION MODULES USED 75 VDC POWER SUPPLY REQUIRED NESTS - NONE RACKS - EXISTING VS NEW

TECHNICALDESCRIPTION AND COMPARISON WITH CONNECTICUT YANKEE APPLICATION (CONTINUED)

SOFTWARE CONNECTI YA KE D.

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CALC ALRM LLAG GATE SOFTWARE BLOCKS USED:

CALC ALRM LLAG GATE RAMP SSEL

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OUTPUT PROCESSING GATHER OUTPUTS FROM BLOCKS CONDITION OUTPUTS CHECK FOR BAD OUTPUTS WRITE OUTPUTS SPEC 200 MICRO CONTROL CYCLE

CONFIGURABLE BLOCK TYPES CONTROL:

PID TUNE NONL INT AMB RTIO P R 0 P 0 RT I0 MAL/INTEG RAL/DE R IVATIVE CONTROLLER EXACT-TUNINGEXTENDER (P ID)

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SWCH SSEL ALRM RAMP TIMR ACUM CALC SWITCH SIGNAL SELECTOR ALARMAND LIMITER UNIVERSALRAMP GENERATOR TIMER ACCUMULATOR CALCULATOR

FIELD INPUTS SPEC INPUTPROCESSING RTD mVolt mAmp CCI 200 INPUT MODULE 2 INPUTS per Module Oto1 OVdc (4)

Logic Level (2or10)

Bl 84 BLOCKPROCESSING 82 B5 B3 86 Oto10Vdc (2)

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SPEC 200 mAmp CCO OUTPUT PROCESSING

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PB-455A High Pressurizer Pressure H-Line.

PB-455A PBY-455A High Pressurizer Pressure SPEC 200!SPEC 200 MICRO,

TY-411 B TY-412A TY-411 M TB-41 1H/G NY-41 1 TY-41 1L TB-411 D/C PQ-455 Over Power Delta T Over Temperature Delta T H-Line

TY-411C TY-412A TY-411 M TB-41 1H/6 TBX-41 16 TBX-41 1H NY-41 1 TY-411 L TB-41 1D/C TBX-411 C TBX-41 1D Over Power Delta T Over Temperature Delta T SPEC 200/SPEC 200 MICRO

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20 59 15 41 9

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PRODUCT EXP.ERIENCE N-SPEC 200

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> 50,000 NUCLEAR MODULES N-SPEC 200 MICRO 30 NUCLEAR PLANTS

> 1000 NUCLEAR MODULES SPEC 200 MICRO

> 400 USERS

> 14,700 MODULES

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VERIFl ATlON A PROCESS THAT GOES ON DURING THE ENTIRE LIFE CYCLE.

THE PROCESS IS THATOF DETERMININGWHETHER OR NOTTHE PRODUCT OF AGIVEN PHASE OF THE SOFTWARE DEVELOPMENT CYCLE FULFILLS THE REQUIREMENTS IMPOSED BY THE PREVIOUS PHASE.

VALIDATION THE TEST AND EVALUATIONOF COMPLETED SOFTWARE TO ENSURE CORRECTNESS AND COMPLIANCE WITH SOFTWARE REQUIREMENTS AND APPLICABLE STANDARDS, RULES, AND CONVENTIONS. FOR EXAMPLE, SOFTWARE MAYBE VALIDATED EITHER: (1) MANUALLY(A NON-PROGRAMMABLECALCULATOR IS CONSIDERED MANUAL),(2) BY BENCHMARKINGAGAINST ANOTHER CONTROLLEDANDVALIDATEDSOFTWARE PROGRAM, (3) BY COMPARING THE SOFTWARE OUTPUT TO EXPERIMENTAL DATA, OR (4) BY BENCHMARKINGAGAINSTA TEST CASE WITH KNOWN RESULTS.

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IEEE 603-1980 STANDARD CRITERIA FOR SAFETY SYSTEMS FOR-NUCLEAR POWER GENERATING STATIONS.

IEEE 344-1 975 RECOMMENDED PRACTICES FOR SEISMIC QUALIFICATIONOF ClASS 1E EQUIPMENT FOR NUCLEAR POWER GENERATING STATIONS.

ANSI/IEEE ANS-7%.3.2-5982, APPLICATION CRITERIA FOR

'ROGRAMMABLE DIGITALCOMPUTER SYSTEMS IN SAFETY SYSTEMS OF NUCLEAR POWER GENERATING STATIONS.

SOFTWARE VERIFICATION 8c VALIDATION PLAN

IEEE -730.'I - 1989 PLAN USED FOR SOFTWARE DEVELOPMENT AND MAINTENANCE SECTION 3.3 MANAGEMENT 3A DOCUMENTATION 3A.1 GOVERNING DOCUMENTATION 3.4.2 MINIMUMDOCUMENTATION REQUIREMENTS 3.6 STANDARDS PRACTICES AND CONVENTIONS 3.8 PROBLEM REPORTING AND CORRECTIVE ACTiON 3.9 TOOLS TECHNIQUES AND METHODOLOGIES 3.1 0 CODE CONTROL 3.11 MEDIACONTROL 3.12 SUPPLIER CONTROL 3.13 RECORDS COLLECTION MAINTENANCEAND RETENTION

SOFTWARE VERIFICATION& VALIDATION REPORT

COMPLIANCETO ANSI/IEEE - ANS 4.3.2

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HARDWARE REQUIREMENTS INPUT/OUTPUT

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- INITIALIZATIONREQUIREMENTS

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- INTERRUPT FEATURES

COMPLIANCE TO ANSI/IEEE - ANS 4.3.2 Continued

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- PROCESS INPUTS

- OPERATING SYSTEM, UTILlTYROUTINES, OTHER AUXlLIARYPROGRAMS

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- IN-SERVICE TEST FEATURES

- TIMING REQUIREMENTS

- PROCESSING IDLE TIME

- SECURITY REQUIREMENTS

- CONFIGURATOR

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COMPLIANCETO ANSI/IEEE - ANS 4.32 Continued

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HARDWARE/SOFTWARE INTEGRATION

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HARDWARE/SOFTWARE INTEGRATION

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COMPUTER SYSTEM VALIDATION

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OVERVIEW OF SUBMI'ITAL M. A. WILKEN

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OBJ ECTIVE

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DESCRIBE HOW NRC CONCERNS HAVE BEEN ADDRESSED

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CE/TAYLOR EQUIPMENT AUDITS DURING THE AUDITOF THE PROPOSED CE/TAYLOR EQUIPMENT THE NRC REQUESTED EXTENSIVE AMOUNTS OF DOCUMENTATIONAND ASKED US TO RESPOND TO NUMEROUS QUESTIONS.

REQUESTS WERE WRITTEN IN OUR AUDITNOTES AND IN INFORMALINFORMATIONEXCHANGES BETWEEN AEPNO AND THE NRC.

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NRC MEETINGS

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APRIL 1992 NRC REQUESTED US TO ADDRESS THE ISSUES RAISED DURING THEIR REVlEN OF THE CE/TAYLOR EQUIPMENT.

NRC IDENTIFIEDOTHER AREAS OF INTEREST, E.G., FUNCTIONALDIVERSITY INFORMATIONTO BE DOCKETED.

~

DECEMBER 1992 PROVIDED STATUS ON THE RPS PROJECT TO THE NCR SINCE THE APRIL 1992 MEETING DETERMINETHE FORMAT OF THE LICENSING SUBMITTALDATED DECEMBER 15, 1992

ACTIONS TAKEN TO RESPOND TO NRC

'NFORMATION REQUESTS

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COMPILED OUR NOTES AND LISTS OF QUESTIONS.

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DELETED QUESTIONS NOT RELEVANTTO THE FOXBORO EQUIPMENT, I.E., THOSE SPECIFIC TO THE CE/TAYLOR EQUIPMENT.

CREATED A FILING SYSTEM TO IDENTIFYTHE SPECIFIC ISSUES THAT NEEDED TO BE ADDRESSED.

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PROVIDED SPECIFIC RESPONSES TO THE APPLICABLEQUESTIONS (APPROXIMATELY150)

IN OUR ENGINEERING DOCUMENTATION.

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PREPARED A"ROADMAP"TO FACILITATENRC REVIEW OF OUR ENGINEERING DOCUMENTATION.

As of 12/15/92 DOCUMENTATIONTRACKINGLIST The following items are those that the NRC expects to be available for review (alter November 30, 1992). These items were identified during the April21, 1992 meeting at NRR. The items, primary responsible group, and due date are as follows:

1.

Background Information A.

Functional Drawings 1.

Existing - (AEPSC l8 C - CMPLT) 2-98501 thru 2-98516 2.

New - (Foxboro - CMPLT)

See'Append/x 8

'<-"~.~'!

Functional Requfremerit:;Sumr'nary.";. (AEPSC,'l&C".-,:CMPL'T)

Report No.-'2985-'DPS4'1,'.

B.

System Architecture Description 1.

Existing a.

Instruction Manuals - (AEPSC I&C - CMPLT)

Foxboro Manuals Volumes l thru /V b.

Simple Block Diagram - (AEPSC I&C-CMPLT)

No Document No.

2.

New a.

b.

C.

Ust ofApplicable Instruction Manuals - (Foxboro - CMPLT) bio Document no. - Attached as Appendix A Applicable Instruction Manuals - (AEPSC l&C-CMPLT)

See Appendix A Write General System Description - (Foxboro - CMPLT) 03104120 page 1 of 22 12/15/ 92

ISSUES 1

LIST FILE NO 1 ~

BACKGROUND I NFORHATION A. FUNCTIONAL ORANINGS 1.

For any "functional" or "logic" changes, provide diagrams and an explanation.

1A2 - Functional Drawings 182d-General

System Description

2.

Provide the loop diagrams, and functional diagrams for the RPS channels including the current revision of the codification package.

Exi sting t 1-D-1, 1-A-1 New:

1A2, 1D2 3.

Provide rack Internal and external arrangement drawings.

4.

Provide plant one-line power drawings (120v) feeding cabinets (new and existing).

1G Exist Ing:

1E1 New:

1E2 7.

Provide the existing etementary drawings - RPS only.

8.

Provide the new elementary drawings - RPS only.

9.

Provide rack asseebty drawings.

1-D.1 1.D-2 1-0 B.

System Architectural Descriptions 1.

Oetalted drawings of the Foxboro Spec 200/Spec 200 Ittcro Etectrontcs.

1-8-2b, drawings contatned in Instruct ton Manuals 2.

Provide Foxboro RPS equipment Information inctuding the Factory Acceptance Tests, Service Bulletins, trouble reports/maintenance I equests

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Available at Foxboro 3.

Provide assurance that the system, when Installed, witt meet the requirements of the plant design basis, Including the FSAR and licensing coami tments.

- Origin of functional requirements 1-81-8 existing 1-82-E new

- Provide functional btock diagrams before/after the upgrade VEV report In file 24A5, figures 1 and 2, and Section 2.2.

- Demonstrate equivalency, are there differences in the functional requirements.

4.

Provide setpoints, gains, constants,

resets, etc., traceable to design basis.

1. 50.59 review

2. 4/21/92 presentation 24.G.2 Page 1 o(

17 12/15/92

DOCUMENTATIONTRACKINGLIST (CONT)

G.

Approved U2 Set 1 Foxboro Drawingsl Complete Set - (AEPSC I&C-CMPLT)

SeeAppendixF8 G

Approved U2 Set 1 Sys Decripl Config Data Base- (AEPSC l&C-CMPLT)

'oxboro Doc No. TP-150

'oxboro Doc No. DB-151 Reg'Guides and Standards applicable A.

Provide summary in revised RFC packet - (AEPSC l&C-See Item 36.C)

RFC 2985 Rev 1 packet Explain how we comply with each and any differences that apply.

1.

Explain existing variances - (AEPSC l8 C - CMPLT)

Report No. 2985-NCF41 2.

Explain any new equipment variances - (Foxboro - None Identified/No Specific Action)

C.

Describe any special conditions to our license and impact on standards compliance - (AEPSC NS - CMPLT)

See'RFC DG 12-.2985':picket'Safety.'Revje j,:Meriio.":file;36:C;.:

3.

Provide a specific comparison to Haddam Neck for both hardware and software A.

Update information provided at April21, 1992 NRC meeting - (AEPSC I&C-CMPLT)

No document number B.

Provide applicable Ml's as references (see Item 1.B,2.b) page 3 of 22 12/15/92

FILE NO.

- Outputs; isolation, separation and barriers 1.

VJV report In file 24A5, Sect.

2 and sect.

3.1.3, discussion on IEEE-603-1980.

2.

281, pages 8 and 9 of 13

- Independence of safety/non-safety signals; isolation separation and barriers 1.

VXV report In file 24A5, Sect.

2 and Sect.

3.1.3, discussion on IEEE-603-1980.

2.

281, pages 8 and 9 of 13 C.

Oetails on how we meet all of the Reg. Guide, IEEE Standards, etc.,

referenced in our purchase order specification.

24A5 and 2B1 3.

Specific Comparison to Haddam Heck for Both Hardware and Software 3-A 4.

Teeperature and Huaidl ty A.

Provide the evaluation that established the design teeperature limits 4B page 2 of 4 to be experienced within the enclosure for the new Instrunentation.

Speci fles equipment requirements The overall envlronnental report will not be written until February 1993.

B.

Provide thermal test reports end plans.

4A 48-reviews 4A 4C-add'I plan 40-appv'l for 4C plan Items 4C and 40 are test procedures which will be performed to demonstrate that the heat rise In the circuit cards Is acceptable.

C.

Oescribe any anomalies that may have occurred during all of the Foxboro testing and how they were resolved.

An additional heat rise test will be done in January 1993.

Page 3 of 1/

12/15/92

CONCLUSIONS

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NRC STATED CONCERNS HAVE BEEN ADDRESSED IN ENGINEERING DOCUMENTATION

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LICENSE AMENDMENTPER 10 CFR 50.59 {b){3){c) HAS BEEN SUBMITTED FOR DOCKETING WITH ENGINEERING DOCUMENTATION.