ML17206A605

Request to Amend App a of License DPR-67.Revises Setpoint for Reactor Trip on High Containment Pressure to Current Applicable Value of Less That 3.3 Psig.W/Safety Evaluation, Certificate of Svc & Amend Fee

ML17206A605
Person / Time
Site:	Saint Lucie
Issue date:	01/08/1979
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Stello V Office of Nuclear Reactor Regulation
References
L-79-5, NUDOCS 7901120143
Download: ML17206A605 (9)

Text

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~ YSTEI'5 (RI DS) 0 A(.CESS ON NBB-7901120143 DOC.DATE.: 79/01/08 NOTARIZED-YES DOCKET 4g FACIL: 0-335 SAINT LUCIE PI, FLORIDA PONER 8

LIGHT CO..

05000335 AUTH-NAME AUTHOR AFF ILIATI ON UHRIG, R.E.

FLORIDA POI'IEB 8

LIGHT CO ~

BECIP-NAMF'ECIPIENT AFFILIATION STELLO,V.

• DIV. OF OPERATING REACTORS 0

SUBJECT:

Request to amend aop A of Facility Operating License DPB-67.Bevises setpoint for reactor trip on high containment 0

pressure tocurrent applicable value of less than 3.3 psig.

I'I/Safety Evaluation, Certificate of Svc 8, amend fee.

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. BOX 529100, MIAMI,FL 33152 I-CULgPR( DOCKET F~"E FLORIDA POWER & LIGHT COMPANY Office of Nuclear Reactor Regulation Attention:

Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission washington, D.

C.

20555

Dear Mr. Stello:

'anuary 8, 1979 L-79-5 Re:

St.

Lucie Unit No.

1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 8 Light Company herewith submits three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License DPR-67.

The proposed amendment is being submitted to revise the setpoint for the reactor trip on high containment pressure to the current applicable value of

< 3.3 psig.

This proposal will complete the corrective action reported in Licensee Event Report 335-78-16, dated June 9, 1978.

The proposed amendment is shown on the attached Technical Specification page bearing the date of this letter in the lower right hand corner.

~Pe e 2-4 The proposed revision to Table 2.2-1, Reactor Protective Instrumenta-tion Trip Setpoint Limits, changes the Trip Setpoint and Allowable Values of Containment Pressure-High to

< 3.3 psig.

A written Safety Evaluation is attached.

FPL has determined that this is a

Class II amendment in accordance with 10 CFR 170.22.

A check in the amount of $1,200 is enclosed.

The proposed amendment has been reviewed'y the St. Lucie Plant Facility Review Group and the Florida Power 5 Light Company Nuclear Review Board.

They have determined that the proposed change does not involve an unreviewed safety question.

Very t

ours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/MAK/cpc Enclosures cc:

Mr. James P. O'ei lly, Region II Harold F. Reis, Esquire 74IM.L2oI0 3 dQ PEOPLE... SERVING PEOPLE

TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT 1.

Manual Reactor Trip 2.

Power Level - High (1)

Four Reactor Coolant Pumps Operating 3.

Reactor Coolant Flow - Low (1)

TRIP SETPOINT Not Applicable

< 9.61K above THERMAL POWER, with a minimum setpoint of 15K of RATED THERMAL POWER, and a

maximum of < 107.0X of RATED THERMAL POWER.

ALLOWBLE VALUES Not Applicable

< 9.61K above THERMAL POHER, and a m1n1mom setpo(nt of 15K of AATEO ~

THERMAL POWER and a maximum of

< 107.0X of RATED THERMAL POWER; Four Reactor Coolant Pumps Operating 4.

Pressurizer Pressure

- High

> 95$ of design reactor coolant 71ow with 4 pumps operating*

< 2400 psia 5.'ontainment Pressure - High

< 3.3 psig 6.

Steam Generator Pressure - Low (2)

> 485 psig 7.

Steam Generator Mater Level -Low

> 37.0X Mater Level

'- each steam generator

> 95K of design reactor coolant 71ow with 4 pumps operating"

< 2400 psia 3.3 psig

> 485 psig

> 37.0$ Mater Level - each

-steam-generator-

. 8.

Local Power Density - High (3)

Trip setpoint adjusted to not exceed the limit lines of Figures 2.2-1 and 2.2-2 Trip set point adjusted to not exceed the limit lines of Figures 2.2-1 and 2.2-2.

• Design reactor:coolant flow with 4 pumps operating is 370,000 gpm.

1/8/79

s,

Re:

St.

Lucie Unit 1

Docket No. 50-335 Reactor Trip Setpoint Containment Pressure-Hi h

SAFETY EVALUATION I.

INTRODUCTION Shortly after Cycle 1 shutdown, the NSSS vendor noted (in a letter regarding core Cycle 2 Specifications) that the reactor protective instrumentation trip setpoint for "containment pressure high" (T.S

~ Table 2.2-1) appeared to be. in error.

During the refueling outage, records were reviewed and it was found that the vendor had recoranended a setpoint change shortly before St. Lucie Unit 1 was licensed.

The setpoint change was incorporated into the Final Safety Analysis Report, but was inadvertently omitted from the Technical Specifications.

The setpoint in Table 2.2-1 is

< 3.9 psig, and the actual Cycle 1 operating setpoint was "conservatively" set at

< 3.5 psig.

The vendor was requested to provide fut ther information, and, as a

precaution before Cycle 2 reactor startup after refueling, the actual operating setpoint was reduced to

< 3.3 psig (as recomnended by the vendor).

On Nay 26, 1978, the vendor confirmed that the required setpoint is

< 3.3 psig.

II.

EVALUATION The NSSS vendor has confirmed that the correct reactor protective instru-mentation trip setpoint for "containment pressure

- high" is

< 3 ~ 3 psig.

The value of the setpoint was generated in accordance with the vendor's setpoint methodology document (CEN (P) D-199), and is discussed in Section 15.1.3 of the Final Safety Analysis Report.

The proposed. amendment will revise the reactor protective instrumentation trip setpoint for "containment pressure

- high" to the current applicable val ue of < 3. 3 ps i g.

I.II.

CONCLUS IONS We have concluded, based on the considerations discussed above, that:

( 1) because the proposed amendments do not involve a si gnificant increase in the probabi lity or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments

, do not involve a si gnificant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security 'or to the health and safety of the public.

a STATE OF FLORIDA

)

)

COUNTY OF DADE

)

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

That he is a Vice President of Florida Power s Li.ght Company,.-

the Licensee herein; That he has executed the'oregoing document; that the state-ments made in this said 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

~~day of NOTARY PUBLIC, 'n and for the county of Dade, State of Florida My commission expires:

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tRjRUC /TATE OF FLORIDA at tARGE MY COhthRGS~OH

~ gREG htARCH 27,

'I032,i 4~4 BONDED THRV MAYHARD BOHDDJG AGENCY,'

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REGULATO Y XNFORMATION DISTRXBUTION'SYSTEM DOCKET NBR:

50-335 ST LUCIE 1 RECIPIENT:

ORXGINATOR:

UHRIG,R.E.

COMPANY:

FL'VR '&'IGHT' DOC DATE:

ACCESSION NBR:

7811240209 COPIES RECEIVED:

LTR ENCL

SUBJECT:

SIZE:

8 Forwards proposed amend to Append A of Facil Oper Lict'IDPR-67 to support extension of safety injection tanksi sample room during Apr 1979 refueling.

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