L-83-236, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capability (NUREG-0737,Suppl 1).Status & Proposed Implementing Schedule Submitted

Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capability (NUREG-0737,Suppl 1).Status & Proposed Implementing Schedule Submitted

ML17213B285
Person / Time
Site:	Saint Lucie
Issue date:	04/15/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, L-83-236, NUDOCS 8304210398
Download: ML17213B285 (9)

Text

REGULA kY INFORMATION DISTRIBUTI(

SYSTEM (RIDS)

ACCESSION NBR:8304210398 DOC ~ DATE: 83/04/15 NOTARIZED:

YES "FACIL:50-335 St. Lucie Planti Uni,t 1< Flor ida Power 3 Light Co, AUTH ~ NAME AUTHOR AFFII IATION UHRIGiR ~ E, Florida, Power 8 Light Co REC IP ~ NAME RECIPIENT AFFILIATION EISENHUTgD,G, Division of Licensing DOCKET ¹ 05000335

SUBJECT:

Responds to Generic Ltr 82 33 re requinements.for emergency response capability (NUREG"0737iSuppl 1),"Status

&;proposed implementing schedule submitted.

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TITLE: OR/Licensing Submittal:

Suppl 1 to NUREG-0737(Generic Ltr 82-33)

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+tb'eg FLORIDA POWER 5 LIGHTCOMPANY April 15, 1983 L-83-236 Office of Nuclear Reactor Regulation Attention:

Mr. Darrell G. Eisenhut, Director Division of Licensing U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Eisenhut:

Re:

St.

Luci e Unit 1

Docket No. 50-335 Supplement 1 to NUREG 0737 Generic Letter 82-33 Your letter dated December 17, 1982 transmitted Supplement 1 to NUREG 0737 (Generic 'Letter No. 82-33).

This Supplement distilled the basic requirements for

.five NUREG 0737 items regardi ng Requirements for Emergency

Response

Capability. It also requested that we develop our own plant specific schedule for integrating these items and implementing whatever modifications are deemed necessary.

We have participated continually in the Nuclear Utility Task Action Committee (NUTAC) on Emergency

Response

Capabilities, which includes over 4 0 utilities and is administratively supported by INPO.

We have factored into our schedule the guidance developed by the NUTAC on integrating these initiatives.

Since we have already accomplished a significant amount of work on these, as well as other NUREG 0737 items, we were forced to deviate somewhat fran the "idealized" integration

scheme, but -have generally followed its outline.

The following are.our status and proposed implementing schedules for the items in Supplement 1 to NUREG 0737:

SAFETY PARAMETER DISPLAY SYSTEM SPDS 1.

Current Status The parameter selection in accordance with NUREG-0696 and the functional design specification has been completed.

The hardware has Deen factory tested and delivered to the site for installation.

The computer system nas been installed and powered from vital AC systems, and the software is being tested at the factory.

The safety signal cables are being terminated in the i solation cabinets.

83042i0398 8304i5 PDR ADOCK 05000335 PDR PEOPLE SERVING PEOPLE

W V

Office of Nuclear Rea r Regulation Attention:

Mr. Darrel i G. Eisenhut, Director Page 2

2.

Submittal of Parameter Selection Basis and SPDS Implementation Plan Report.

The reports describing the parameter selection and definition along with tne implementation plan will be submitted by March 1, 1984.

3.

Date When SPDS will be 0 erable and Operators Trained The SPDS will be operational prior to startup from the fall 1984 Refueling Outage.

The verification and validation of the SPDS and operator training will be canpleted prior to the SPDS beccming operational.

DETAILED CONTROL ROOM DESIGN REVIEW DCRDR) 1.

Current Status 2.

We have already begun completion by May 3D, submi t a program plan sup'erceded.

With the requirements, we will Submittals our DCRDR for St. Lucie Unit 1.

We anticipate 1983.

Therefore, the requirement of Supplement 1 to within two months of the start of DCRDR has been issuance of the Supplement and the finalization of NRC now prepare the required documentation.

The management plan describing our DCRDR program will oe submi tted oy June 1,

1983.

A summary report of the completed review, describing the Human Engineering discrepancies review and assessment, and proposed implementation schedule will be submitted by November 1,

1983.

Actual modifications to the control roan will be dependent upon NRC review and approval of the summary report.

REGULATORY GUIDE 1,.97 REV.

2 1.

Current status We have reviewed our existing accident monitori ng 'instrumentation and control systems agai nst the requir ements of Regulatory Guide 1.97, Rev. 2.

We are presently assessing the deviations found and. are developing the schedule for required modifications, if any.

2.

Submi ttal s The ev'aluation report of the plant instrumentation, schedule for any required modifications, and justification of any deviations not requiring modi fications will be submitted by January 1,

1984.

Actual modifications will be dependent upon review and approval by the NRC.

~,

Office of Nuclear Rea Regulation Attention:

Mr. Darrell G. Eisenhut, Director Page 3

UPGRADE EMERGENCY OPERATING PROCEDURES EOPs Current Status 2.

We have been active participants in the Combustion Engineering Owners Group (CEOG) efforts regarding the upgrading and reformating of the EOPs.

Our plant specific procedure generation will be based upon the generic Technical Guidelines submitted to the NRC by the GEOG.

Submi ttals We will submit a plant specific procedures generation package by November 1, 1983.

The upgraded EOPs will be implemented by July 1,

1984, and will include inclusion of the SPDS and control rocm upgrades.

EMERGENCY RESPONSE FACILITIES ERF Supplement 1 requires that we provide the operational dates for the ERFs.

2.

3.

Technical Support Center (TSC) - The TSC is currently operational except for extensive construction activi ty.

These activities are preparatory to-installing the SPDS and will be completed prior to the end of the current refueling outage.

Operational Support Center (OSC) - The OSC is currently operational.

Emergency Operation Facility (EOF) - The EOF is currently under construction and will be canpleted and operational by October 1, 1983.

It should be noted, as stated in the SPDS discussion, the SPDS will not be

,operational prior to startup from the Fall 1984 Refueling Outage.

The SPDS will be provided in the EOF and TSC at that time.

However, we consider the SPDS an additional aid to emergency recovery and not a requirement for the ERFs to be operational.

We look forward to discussing these schedules with our Project Manager to arrive at a mutually acceptable schedule.

FPL has devoted considerable time and effort

'in the past to implementing NUREG-0737 requirements.

It is our opinion that with these previous modifications and upgraded plant operations, the continued

N

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,>> Office of Nuclear Rea r Regul ation Attention:

Mr. Darrell G. Eisenhut Page 4

operation of the plant should pose no,threat to the health and safety of the public with consideration of our implementation schedule for Supplement I to NUREG 0737.

Very truly yours, Robert E. Uhrig Vice President Advanced System 8 Technology REU/JEM/j s cc:

Mr. James P. O'Reilly, Region II Harold F.

Rei s, Esquire

~

~

H STATE OF FLORIDA

)

)

ss.

COUNTY OF PALM BEACH )

Robert E. Uhri being first duly sworn, deposes and says:

That he is Vice President Licensee herein; of Florida Power & Light Company, the That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.

Robert E. Uhrig

. Subscribed and sworn to before me this P

J. il/'f

/5, '~day,of I98+.

"'"','~~~riNOTA'pY BLIC, in and for the County

'"'of'Palm Beach, State of Florida.

My commission expires:

Notary u

ic p blic State of Flonda at Large 30

~1983 My Cornrni~ion Expirea October

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