ML17345B179

Forwards Addl Info to Util 830415 Response to NUREG-0737, Suppl 1 Re Safety Parameter Display Sys,Detailed Control Room Design Review & Reg Guide 1.97

ML17345B179
Person / Time
Site:	Turkey Point
Issue date:	07/25/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 L-83-421, NUDOCS 8307280098
Download: ML17345B179 (10)

Text

REGULATORY <FORMATION DISTRIBUTION S 'EM '(RIDS)

ACCESSION NBR :8307280098 DOC ~ DATE: 83/07/25 NOTARI'ZED; NO DOCKET FACIL:,50 280 Turkey Point Planti Unit 3i Florida'ower and Light 'C 05000250 50 251 Turkey Point Planti 'Unit 4i Florida Power and Light 'C 05000251 AUTH, NAME AUTHOR AFF'kLIATION UHRIGi R,E ~ F.1 or ida 'Power' Light Co

.~ECIP>> NAME RECIPIENT AFFILIATION VARGAiS ~ A, Operating Reactors Branch 1

SUBJECT:

Forwards addi info to util 830715 response to NUREG 0737i Suppl 1 re safety parameter display sysidetailed control

.room design review 8 Reg Guide 1 '7

'CODE ~ A003S 'COPIES RECEIVED LTR, ENCl, l 'IZE TITLE: OR/iicensing Submi,ttal: Suppl 1 to NUREt:-0737(Generic Ltr'8

'DISTRIBUTION 33)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES IO CODE/NAME NRA ORB1 BC "7 '7 LTTR ENCL ID COOK/NAME LTTR ENCL INTERNAL'E/DEPER/EPB 3 NRR'/DHFS/PSRB 1 NRR/DL/ORA'8 1 NRR/DL/ORB5 '5 5 NRA/DSI/CPB 1 NRR/DS I/ICSB NRA/DSI/METB 1 1 NRR/DSI/RAB i NRA/DSI/RSB i. NRR/T SONiW 3 3 OR&5,PAULSONiW 1 lES RGN2 1 EXTERNALe LPDR 1 1 NRC PDR NS1C 1 NTIS TOTAL NUMBER OF COPIES REQUIRED; LTTR 32 ENCL 32

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Jt'wv~~AW FLORIDA POWER & LIGHT COMPANY July 25, 1983 L-83-421 Of>ice of Nuclear Reactor Regulation Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch 81 Division of Lice'nsing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Varga:

Re: Turkey Po',nt Uni s 3 8t 4 Docke Nos. 50-250 R 50-251 Su lement 1 to NUREG 0737 Per conversations with your staff, attached is additional information to our Supplement 1 to NUREG 0737 response dated April .1'5, 1983 (L-83-237).

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 5 Technology REU/SAY/cab Attachment cc: J. P. O'Rei lly, Region II Harold I=. Reis, Esquire 8307280098 830725 PDR ADOCK 05000250 F PDR PEOPLE... SERVING PEOPLE

"J SAFETY PARAMETER DISPLAY SYSTEM (SPDS)

NUREG-0696 provided the basic requirements for the parameters selected for SPDS.

Florida Power and Light (FPL) Operations personnel and. Engineering personnel, the Architect Engineer, and the consultants and manufacturers of the Safety Assessment System (SAS) determined the final parameter selection. The SPDS js the part of SAS that fulfills the requirements of NUREG4696. The general constraints and considerations used in the parameter selection are listed below.

Regulatory requirements for the SPDS portion must be met.

Wide range values should be used wherever. possible.

Other designs and experience, i e., EPRI/NSAC, W, AIF, should be reviewed and considered for "do's and "don'ts" Consideration must be given to both "event" and "function" approaches to procedural interfaces.

Human factors considerations are of prime importance.

The Functional Design Specifications of SAS address the functional requirements, training, human factors, verification and validation. These specifications have been comp leted.

The manufacturing of the hardware has been completed. The integrated hardware and software testing program has been substantially increased. The testing and delivery of SAS is presently scheduled during August I 983.

The control wiring-diagrams of the SPDS parameters are near ly complete.

The Computer Room which houses the SAS equipment) isolation cabinets and other peripherals will be ready in a few months.

The isolation cabinets for safety related instrumentation signals will be installed during the l 983 Refueling Outage (presently scheduled for completion by December I 983).

Florida Power and .Light plans to submit the parameter selection and definition report along with the implementation plan by May I, l984. These reports will be written to satisfy the reporting requirements of Supplement I to NUREG 0737.

The final installation of the SPDS portion of SAS verified and validated for each unit. The SAS will be utilized for information purposes and operator training before it is declared operational. This period will also be used to locate possible hardware problems or software bugs. Any necessary modifications will be made during the outage before the SAS is declared operational. The SAS will be declared operable and the operators trained after the following outages.

Turkey Point Unit 3 I 985 Refueling Outage Turkey Point Unit 4 1984 Refueling Outage

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Detailed control Room Desi n Review (DCRDR)

The DCRDR for Turkey Point consists of four phases. Phase I was started April I 98l. Florida Power and Light is presently working in Phase IV. The summary report of the completed review, describing the Human Engineering discrepancies review and assessment and proposed implementation schedule will be submitted by November I, 1983. Significant modifications'to the Control Room will be dependent upon NRC review and approval of the summary report.

The four phases of the DCRDR are outlined below.

Phase I Develo Pro ram Plan

'V Florida Power and Light utilized NUREG-0700 to develop the program plan. The details of the program plan have been, documented in our Program Plan report (also referred to us Management Plan) and will be submitted to the NRC by tune I, l983.

The Program Plan report covers the following:

Review of methodologies Review of documentation Personne I qua li fications, and project organization Method of Assessment and prioritization of discrepancies Summary report outline Phase II Control Room Review Considerable data has been collected and analyzed to develop human engineering discrepancy (HED)'eports. The following functions were performed during this phase.

Review of operating experience (2 sub tasks)

Assemb le Control Room documentation Review of system functions and'ask analysis (4 step program)

Control Room surveys (l4 different surveys)

Verify task performance capability (2 sub tasks)

Validate Control Room functions The HED Review Team assessed the discrepancies found Phase III Enhancement and Design Solutions Discrepancies are collated and examined for correction by using the following basic procedure Analysis of correction by enhancement Analysis of correction by design alternatives Assess extent of correction Phase IV Re ortin The DCRDR Summary 'Report will closely follow the outline recommended in Section 5.2 of NUREG -0700. The implementation schedule will be included.

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Re viator Guide l.97 Florida Power and Light has completed the listing of all the existing Accident Monitoring Instrumentation (AMI) at Turkey Point. A summary format of this listing will be incorporated into the Regulatory Guide l.97 Evaluation Report and submitted to the NRC. This report will include the 'following for each instrument-Qualification Information Power Supply Display Location Redundancy The Quality Assurance documentation will be verified for the report. After the summary sheet information is co'mpleted, an evaluation 5f the AMI with respect to the requirements of Regulatory Guide l.97 will be performed. This evaluation will be utilized to determine those items that require modifications and provide justification for those items that Florida Power and Light does not intend to modify-A schedule for making the modification and proving the justifications will be proposed based upon the following.

Safety significance of the deviation Severity of the deviation Engineering and procurement lead time requirements and constraints Overa I I outage schedu les The final Regulatory Guide I-97 Evaluation Report is scheduled for submittal by March I, I 984.

TSC The auxiliary power upgrade program will provide the backup electrical power to the TSC. This upgrade entails connecting existing loads to the new system and changing and modifying the source of power to controls in the control room. These changeovers require a plant shutdown to complete.

Inte ration of SPDS DCRDR REa. Guide 1.97 and erations I

The design of the SPDS displays were based on the proposed draft of NUREG-0835 and other industry standard human factor guide line for contro I systems and considerable operator input as to information needed .to assess normal and emergency plant conditions. The proposed draft to Regulatory Guide I-97 was considered in the design of the SPDS. Information on the SPDS for each unit will be provided, by November 1983, for integration into the DCRDR, developing EOP's,.and operator training. The SPDS will be tested, operated for information purposes, and used for'perator training over a considerable period before it is declared operational- During this time, modifications desired by FPL to integrate any additional requirements due to the Regulatory Guide 1.97 evaluation or the SPDS portion of the CRDR can be made to the SPDS or Control Boards.

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