ML20236L082

Notifies of Nrc/Scientific Applications Intl Corp 871130- 1204 Audit of Facility Dcrdr & Spds.Agenda,Attachments Identifying Dcrdr Concerns & SAIC-87/3056, Technical Evaluation Rept for Wisconsin Electric Power Co..., Encl

ML20236L082
Person / Time
Site:	Point Beach
Issue date:	11/02/1987
From:	Wagner D Office of Nuclear Reactor Regulation
To:	Fay C WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20235Y661	List: ML20235Y659 ML20236L082
References
NUDOCS 8711100103
Download: ML20236L082 (11)

Text

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j Movenber 2,1987 j

Docket Nos. 50-266 DISTRIBUTION:

and 50-301 "SDocket Filess DWagner NRC PDR " " 0GC-Bethesda

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local PDR Edordan f

Mr. C. W. Fay, Vice President PDIII-3 r/f JPartlow Nuclear Power Department DWigginton ACRS(10) 3 Wisconsin Electric Power Company GHolahan PDIII-3 Gray File l

231'W. Michigan Street, Room 308 PKreutzer

{

Milwaukee, Wisconsin 53201

SUBJECT:

COMBINED DETAILED CONTROL ROOM DESIGN REVIEW (DCRDR) AND SAFETY PARAMETER DISPLAY SYSTEM (SPDS) AUDIT AT POINT BEACH 1 AND 2 Our review of the Point Beach DCRDR and' SPDS has reached the point where we feel it would be beneficial to conduct a combined DCRDR and'SPDS audit at Point Beach. We and our consultants, Scientific Application International Corporation (SAIC), wish to conduct this audit at Point Beach from Menday, November 30, through Friday, December 4, 1987.

' to this letter provides a tentative agenda for the combined audit.

Attachments 1 and 2 to Enclosure 1 identify DCRDR. concerns to be discussed with your staff. Enclosure 2 to this letter is the SPDS Technical Evaluation Report (TER) prepared by SAIC. We concur with the evaluations and conclusions presented in the TER. Briefly, the TER concludes (1) that the SPDS parameters selected '

a do not include Residual Heat Removal or its equivalent, stack radiation 3

monitoring, containment isolation status and containment hydrogen concentration; (2) that information on verification of the SPDS display data is not provided; l

and (3) that information regarding the existence of a human factors program for the SPDS was not provided. These issues will be discussed during the audit, j

Additionally, we request that approval be granted for our audit team to use a j

camera to take pictures of the centrol room, the remote shutdown panel, and i

any other plant area pertinent to the DCRDR and SPDS.

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Please notify us of the acceptability of the proposed audit dates.

Sincerely, h/

David H. Wagner, Project Manager Project Directorate III-3 i

Division of Reactor Projects

Enclosures:

As stated cc: See next page

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Office:

LA PDJ(zter II-3 PM/PDIII-3 PD/PDIII-3 Surname:

P.

q/87 DWagner/tg DWigginton Date:

1 11/1/87 11/ v/87 8711100103 871102 PDR ADOCK 05000266 P

PDR

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,n Point Beach Nuclear Plant

'Mr. C. W. Fay Wisconsin: Electric. Power Company Units 1 and 2

's cc:

- Mr.. Bruce Churchill. Esq.

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' Shaw,' Pittman, Potts and Trowbridge :

2300 N Street, N.W.

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Washington, DC 20037

' Mr.. James 'J. Zach, Manager

' Point'Bea'ch Nuclear Plant Wisconsin Electric Power. Company 6610 Nuclear Road Two Rivers. Wisconsin 54241 Town Chairman l-l Town of Two Creeks Route 3 Two Rivers, Wisconsin 54241 l

l Chairman Public Service Commission of Wisconsin Hills Farms State Office Building Madison, Wisconsin 53702 Regional Administrator, Region III l

U.S. Nuclear Regulatory Commission Office of Executive Director

.j for Operations 799 Roosevelt Road

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Glen Ellyn, Illinois 60137

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Resident Inspector's Office l

U.S.' Nuclear Regulatory Commission 6612 Nuclear Road R

j Two Rivers, Wisconsin 54241 j

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i ENCLOSURE 1 r

TENTATIVE AGENDA 1

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TENTATIVE AGENDA.LFOR TH'E DCRDR/SPDS AUDITi WISCONSIN.ELECTRICPOWER-COMPANY!S.POINTBEACH1&2-

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4 NOVEMBER 30 THROUGH. DECEMBER 4, 1987-

~i DAY 1 Monday,' November 30, 1987:

n 1:00 p.m.-

-Introduction l.of NRC Audit Team:(NRC)

Pr'esent Chronology of DCRDR Documentation.

Review lDCRDR Requirements of'NUREG-0737. Supplement:1.-

1:15 p.m.

Presentation.of DCRDR Program by' Licensee:

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Co'nfirm Chronology of;DCRDR Documentation.

h Review Team System Function 'and Task Analysis.

Comparison of Display and. Control Requirements :

q Control' Room. Survey

.q Assessment of Human; Engineering Discrepancies-(HEDs) j Selection of Design Improve'ments l

Verification.that. Selected Improvements Provide th'el j

Necessary Correction'

-t Verification that' Selected Improvementswillinot; Introduce'New HEDs-

. Coordination of-Control: Room Improvements-with Changes fromOtherPrograms(SPDS,(0peratorTraining,, Reg.:GuideL

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1.97, Upgraded.EOPs) 2:30 p.m.

Tour of Control Room 3:30 p.m.

Review of Selected HEDs in Moc'kup. Room'

. Proposed resolutions of HEDs.areiunsatisfactory,.u'nclear-

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and undefined '(see. Attachment 1)

HEDs with unsatisfactory justification =for "N0 ACTION"-

(see Attachment 2)-

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t TENTATIVE, AGENDA -(Coritinued)'

DAY 2 Tuesday,' December 1, 1987 1

8:30 a.m.-

Continued' Review of Selected'HEDs in Mockup Room-

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i Noon BREAK FOR' LUNCH'

- 1:00 p.m.

Complete'. Review of Selected 'HEDs in Mock'up Room I

3:00 p.m.

Conduct Sample Survey of the Control Room' Modifications in-I the Control Room Implemented modifications Items of Concern g

SPDS Computer Systems-1 4:30 p.m.

Discussion / Planning-for-Next Day

.SPDS Documentation for Next Day:-

o Plant Specific E0PS o

Functional Requirements o

. Data Requirements o

System / Subsystem Requirements o

Program Specifications o

Emergency Procedure Guidelines o

Detailed Algorithms 5:00 p.m.

Adjourn DAY 3 Wednesday, December 2, 1987 8:30 a.m.

Introduction and Briefing (NRC)

Present Chronology. sf SPDS ' Documentation Review SPDS Requirements of NUREG 0737, Supplement:1 2'

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TENTATIVE AGENDA (Continued);

9:15 a.m.

Overview of:SPDS Implementation (Licensee)_,

m Confirm Chronology of SPDS Documentation'

-DefinitionofSPDS.(Scope)

Parameter Selection. Process Human Factors ~ Engineering Program.

Reliability Verification'and Validation Program i

Implementation Program o

Project' Milestones-4 Noon.

BREAK FOR LONCH 1:00 p.m.

Critical' Safety Function / Parameter Selection (Licensee)i

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Parameter Selection Cr,itical Safety Functions (vs.' NUREG-0737)

Critical Safety Functions / Parameter Relationships Range of. Events /Conditi ms covered by parameters' 4

Technical r-aluation Report (TER) Concerns.

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'.(see Enclosure 2, TER, dated October 16,1987) 2:30 p.m.

BREAK 2:45 p.m.

System Design

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System Description

Display Configuration Data Validity Security

• System. Verification and Validation -

Verification Test Plan Validation t

Maintenance and Configuration Control n

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.TENTATIVEAGENDA(Continued)

'l 4:30'p.m.

. Discussion / Planning for'Next Day i

5:00 p.m.

Adjourn

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DAY.4 Thursday, December 3, 1987 ~

1 8:30 a.m.

Visit.Centrol: Room 1(CR)/ Technical Support. Center (TSC)-

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4 SPDS Demonstration (Licensee) j l

Human. Factors Engineering Review (NRC)<

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. Display Location (CR) l

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Display Format (TSC)

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o Display Techniques (TSC)

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-TER Concerns of October 16, 1987

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Operations Review (NRC)

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Concise Display o

Parameters Identified.in SAR on SPDS (TSC)-

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Critical Safety Functions (0737 and Plant) (TSC)

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o Reliability.. (Hardware /Sof tware). (CR) l l

o Respon'se Times (Display. Call-up_ and. Screen Update)-

(CR)'

o Integ' rated into Emergency Operations _(CR)-'

o SPDS Parameter Values vs. Fixed Panel Values 1

i (Comparison)'(CR) o Procedures and Training'(Licensee requested.to have matdrials available) l Electrical Isolation 4

t Noon BREAK FOR LUNCH i

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TENTATIVEAGENDA.:(Continued)l

'1:00'p.m.

Operator-Interviews; Shift 1Su'ervisor

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p Reactor Operator Shift Technical ~ Advisor

.Remaini.ng Document'ation Review-

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00p.m.'

jAdjourn-l DAY 5 Friday, ' December ' 4,'/1987-

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8:30 a.m.

Review Remaining DCRDR/SPDS, Concerns-Noon BREAK FOR LUHCH'-

1:00 p.m.

Audit Team' Caucus 3:00 p.m.

Exit Briefing

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,-ATTACHMENT 1-l i

.J HEDsforwhichthe:proposedresolutionsare' unsatisfactory,uncie'arand'

-indefinite fall'into the following categor_ies.

' Missing Information.

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HED-399, 614, 647, 667 and 809

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Range'and' Accuracy Problems HED-350,'438.484, 569,^and'608.

n-Control DisplayLProblems.

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HED-584, 597 and 612

.j Coordination'with Upgraded E0Ps.

HED-384, 418,.425, 457, 472, 485, 540,.551, 568,,619-and 634 j

i Setpoint Problem's HED-497 and 758 j

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1 ATTACHMENT.2; N,

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HEDs with unsatisfactory justification'.for'"No Actiion falllintd[the 'following; categories',;

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._ Missing Information

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HED EHED HED 354 3657 710

~505 672 716 541 675 724 615 693 736 633-703-745-653 708

761

1. j Range and-Accuracy Problems-

.i HED-440 and 759 i

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Control Display Problems

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HED-566 Coordination withLUpgraded E0Ps HED-HED HED' 427 502 638 441 548

'642 a

447 565

-777 450 622 800' 496 632 Unusual Technical Problems HED-258, 353, 365 and 376 1

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i ENCLOSURE ~2 TECHNICAL EVALUATION REPORT I

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