ML18019B142

Submits Supplemental Info on Human Factors Review of SPDS, Per NUREG-0700.Validation Test Rept 85% complete.Cross-ref to SPDS Safety Functions & Variables to Parameters,Per NUREG-0737,Suppl 1 Encl

ML18019B142
Person / Time
Site:	Harris
Issue date:	09/02/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0700, RTR-NUREG-0737, RTR-NUREG-700, RTR-NUREG-737 NLS-86-327, NUDOCS 8609050099
Download: ML18019B142 (6)

Text

DOCKET 0 05000400

SUBJECT:

Submits supplemental info on human factors review of SPDSi per NUREQ-0700. Validation test rept 85/ complete. Cross-ref to SPDS saf etg functions ff( var iab les to parameters>

per NUREQ-0737> Suppl 1 encl.

DISTRIBUTION CODE:

AOOSD COPIES RECEIVED: LTR i ENCL J SIZE:

TITLE: OR/Licensing Submittal:

Supp l 1 to NUREQ-0737(Qeneric Ltr 82-33)

REQU RY INFORMATION DISTRIBUT SYSTEH (R IDS)

'ACCESSION NBR: 8609050099 DOC. DATE: Bh/09/02 NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Pommer Plant.

Unit i. Carolina AUTH. NAf'fE AUTHOR AFFILIATION ZINNERl'fANiS. R.

Carolina. Potver Cc Light Co.

RECIP. NAI'fE RECIPIENT AFFILIATION DENTONp H, R.

Office of Nuclear Reactor Regulationi Direc tor

< p ost 851125 NOTES: Application for permit renewal filed.

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CRK Carolina Power 8 Light Company SEP oa m86 SERIAL: NLS-86-327 Mr. Harold.R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.

1 - DOCKET NO.50-000 SAFETY PARAMETER DISPLAY SYSTEM

Dear Mr. Denton:

Carolina Power i~r. Light Company (CPRL) submits supplemental information on the human factors review of the Safety Parameter Display System (SPDS).

Carolina Power i':

Light Company has utilized the guidance of NUREG-0700, "Guidelines for Control Room Design Reviews," to review the SPDS terminals, screens, outputs, color coordination, and control board location.

HEDs have been identified and dispositioned under the Detailed Control Room Design Review. This supplements our response to Question 2.g of your Safety Evaluation Report (SER) on the SPDS.

The Validation Test Report is approximately 85 percent complete.

The remainder of the work consists of incorporation of the results of the final acceptance test.

Carolina Power 2 Light Company expects the final report to be complete in early-1987 and willbe available prior to startup following the first refueling outage.

This supplements our response to Question 2.h of your SER on the SPDS.

Based upon discussions with the NRC staff, CPi!cL willadd stack radiation, steamline radiation, and containment isolation (Phase A, Phase B) variables to the SPDS.

The source-range neutron flux, intermediate-range neutron flux, RHR flow, and containment hydrogen concentration variables are, in fact, available from the SPDS.

This supplements our response to Question 0 of your SER on the SPDS.

Attachment 1 provides a cross-reference to the SPDS safety functions and variables to the parameters provided in NUREG-0737, Supplement l. This supplements our response to Question 2.d of your SER on the SPDS.

Carolina Power R Light Company believes this information is sufficient to resolve the outstanding issues on the SPDS. If you have any questions, please contact Mt. Gregg A.

Sinders at (919) 836-8168.

8609050099 860902 PDR ADOCK 05000400 p

PDRj GAS/vaw (0069GAS)

Enclosure cc:

Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. 3. Nelson Grace (NRC-RII)

Dr. S. N. Saba (NRC)

Yours very truly, S. R Zi erman anager Nuclear Licensing Section 411 Fayettevilte Street o P. O. Box 1551

~ Raleigh, N. C. 27602

) 't

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TABLE I: SAFETY FUNCTION VARIABLES S~fF 1.

Subcriticality 2.

Core Cooling 3.

RCS Integrity NUREG-0737 Variable Power-Range Neutron Flux Intermediate-Range Start-Up Rate Source-Range Start-Up Rate Source-Range Energized Core Exit Temperature RCS Subcooling RCS Level Reactor Coolant Pump Status Cold Leg Temperature RCS Pressure Cooldown Rate Parameter~

(i) (iv)

(ii), (iii),(iv)

(iii),(iv), (ii) 0.

Heat Sink Steam Generator Level Steam Generator Pressure Feedwater Flow (ii), (iv) 5.

Containment 6.

RCS Inventory Containment Pressure Containment Sump Level Containment Radiation Containment Hydrogen Pressurizer Level RCS Level (v), (iv)

(iii),(ii), (iv) ',

Steamline Radiation Stack Radiation (iv)

(ii)

(iii)

(iv)

(v)

Reactivity Control Reactor Core Cooling and Heat Removal From the Primary System Reactor Coolant System Integrity Radioactivity Control Containment Conditions NOTE:

The first parameter listed is considered the primary parameter addressed.

(4069GAS/pgp)

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