ML17345B429

From kanterella
Jump to navigation Jump to search
Forwards Revised Tech Spec Table 3.5-2, ESF Actuation & 3.5-4, ESF Setpoints, Per 820806,830103 & 0325 Submittals Re Adequacy of Station Electric Distribution Voltages
ML17345B429
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/31/1984
From: Williams J
FLORIDA POWER & LIGHT CO.
To: Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML17345B430 List:
References
L-84-25, NUDOCS 8402060466
Download: ML17345B429 (4)


Text

REGULATOR'r, NFORMATION DISTRIBUTION S

'EM (RIDS)

ACCESSION NBR!8402060466 DOC ~ DATE: 84/01/31 NOTARIZED:

NO DOCKET I'-SCIL!50 250 Turkey Point Planti Unit 3r Florida Power and Light C

05000250 50-251 Tur'key Point Plantr Unit 4r Florida Power and Light C

05000?51 AUTH'AME AUTHOR AFFILIATION WILLIAMS'

~ W ~

Flor ida Power L Light Co, NEC'IP, NAME RECIPIENT AFFILIATION VARGAtS ~ Ae Operating Reactors Branch 1

SUBJECT:

Forwards revised Tech Spec Table 3'-2~

"ESF Actuation" 3.5-Il~

'~ESF Setpointsr" per 82080br830103 5 0325 submittals re adequacy of station electric distribution voltages, DISTRIBUTION CODE:

A001S COPIES RECEIVED:LTR ENCL SIZE:

TITLE!

OR Submittal:

General Distribution NOTES!

REC IP IENT ID CODE/NAME NRR ORB 1 BC 01 INTERNAL'LD/HDS4 NRR/DL DIR NRR METB b FI 04 COPIES LTTR ENCL 7

7 1

0 1

1 1

1 1

1 REClP IENT ID CODE/NAME NRR/DE/MTEB NRR/DL/DRAB NRR/DSI/RAB RGN2 COPIES LTTR ENCL 1

1 1

0 1

1 1

1 EXTERNAL,! ACRS NRC PDR NTis 09 02 6

6 1

1 LPDR NSIC 03 05 1

1 1

TOTAL NUMBER OF COPIES REQUIRED!

LTTR 25 ENCL 23

A I

I</ lg t<<h 4'4

)

/ADA,g I

AA AAAK K

I

',DAil ilh,k 'll 1>

Il< lf

$ 1L

.iY

< ~

ff f <<$ '," D q 'A

'14 I II 9<

<<CA< I"

~ 'A<A

$ I,I i

', I

."I g

<f i, jI ll jI j <I '

< A,', '

1 jf il li 4 II

<i vf, K A

j'<"Ag >,I h <ff sA,,

I tf D>i', f ',4 tA fl'<

A'A>>h jI j I',lli'Sk If K l f DIA 4$ <141 I "D<<Th',<, ll A

DA Dc

+q<<<<<<i '<<j$

A/< j f e.')

'>><f<f ~ )fjIg 0

-'j, t jll

~, ff<<3 Jjf<fj t

~ <.> <<

Alg< f $

h /

A < ff

<D f D'I II

<QK'~

<I 1

g 1 A A<A

>>I i \\

if I< <I<

A" ji' Il 1 "

If<

1, iA i

g g<~y<AA<

<<graf<><)f A>>

e g IAD<'k, gn D

g w.m~ee~~r

>pe

<<<<< ~

IIIK I<<<'jI 1

A i

I<

4jl.'ff "fi

<'<l i if

~

'>< 'I /A<<< If AT4tl;"'<<gAy f<<

IA Af<<~g ff ")

<Dg "ff g li A< ',)ADA<

'fitIA

<<.$ if/ J)

~~j~

$ )t'A,

>>jji l J A,fl i)f g 1

Ag'h I(

hk',

1

,l'h,<,i "X l

, 3'( Irl 5 i

,IIi-,

'll ff X llli 1

i.") "'4 if<I'i~)4 Ill AK I

i, Df

<Jhj k XI'<

4

~ 4>>

I<,< 'I<<'

i

<j Il "Il,l' II<<"

ll<

i e/D<<T4 hl

BOX 14000, JUNO BEACH, F L 33408 eg r- ~

FLORIDAPOWER & LIGHTCOMPANY January 31, 1984 L-84-25 Office of Nuclear Reactor Regulation Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch gl Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Varga:

Re:

Turkey Point Units 3

8 4 Docket Nos. 50-250 and 50-251 Distribution S stem Volta es Our letters L-82-334 dated August 6, 1982, L-83-1 dated January 3, 1983, and L-83-179 dated March 25, 1982, provided technical specification changes associated with our review of the adequacy of station electric distribution voltages at Turkey Point Units 3 and 4.

The purpose of this letter is to correct our proposed revisions of Table 3.5-2 (Engineered Safety Features Actuation) and Table 3.5-4 (Engineered Safety Feature Setpoints).

1)

The proposed specification for minimum channels operable in our previous letters could severely restrict operation in that it would not allow maintenance of the undervoltage relays during operation and that cold shutdown would be required if only one of the devices became inoperable.

It is our opinion that this was not the intention of the original June 2, 1977 NRC letter which requested our review of the subject.

In addition to changing the minimum channels operable from 2 to 1, a

feature has been added to the relays to place an inoperable channel in trip, and allowing operation in that condition.

Because of the AND logic of the circuit, this note will ensure that the safety function of the circuit will be available while the relay is being maintained or repaired.

2)

The proposed specification for Engineered Safety Feature Setpoints in our previous letters included relay tag numbers within the Load Centers and their corresponding setpoints.

We have reconsidered the listing of the 480V relays and have determined that listing tag numbers only adds confusion to the understanding of the Technical Specifications while supplying little or no technical content.

84020b04bb 84013i PDR ADQCK 05000250, P

pool

(~

PEOPLE...SERVING PEOPLE

s Office of Nuclear Reactor Regulation Attention:

Mr. Steven A. Varga Page 2

For this reason, we are%revising Table 3.5-4 to only reflect Load Centers and specific instantaneous and delay setpointsQ It is, our opinion that this revision still meets the intent of the original June 2, 1977 NRC letter which requested our review of the subject.

Corrected pages incorporating the changes discussed above are attached.

Should you or your staff have any questions on this information, please contact us.

Very truly yours, 6

J.

W. Williams, Jr.

Vice President Nuclear Energy Department JWW/PLP/js Attachment cc:

Mr. James P. O'Reilly, Region II harold f. Rei s, Esquire PNS-L I-83-719