ML20235G936

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Forwards Revised Figures 1.4-5 & 1.4-6 & Tables 7.1-3 & 7.1-4 to 870722 Rev 5 to Updated Fsar,Reflecting Addition of Steam Line Rupture Detection/Isolation Sys & Environ Qualification Program
ML20235G936
Person / Time
Site: Fort Saint Vrain 
Issue date: 09/21/1987
From: Robert Williams
PUBLIC SERVICE CO. OF COLORADO
To: Calvo J
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
P-87317, NUDOCS 8709300297
Download: ML20235G936 (7)


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September 21, 1987

$.nsr7cEm201a40 Fort St. Vrain Unit No. 1 R.O. WILLIAMS, JR.

P-87317 QP E$

E R PE ONS U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 Attention: Mr. Jose A. Calvo Director, Project Directorate IV a

Docket No.

50-267 ME l

'x

SUBJECT:

Fort St. Vrain Updated $ $

FSAR, Revision 5 g

en e

REFERENCE:

1)

PSC Letter Williamreto i

Calvo dated July 2ika 1987 (P-87255)

Dear Mr. Calvo:

Revision 5 of the Updated Final Safety Analysis Report (Updated FSAR) for the Fort St. Vrain Generating Station was submitted on July 22, 1987 per 10 CFR 50.71(e)

(Reference 1).

In revising the Updated FSAR, substantial changes to the text, tables, and figures were incorporated to reflect the addition of the Steam Line Rupture Detection / Isolation System (SLRDIS) and the Environmental Qualification (EQ) Program. One table and two figures in the Updated FSAR were not updated completely for the changes made by SLRDIS and the EQ Program.

PSC considers that these changes are too substantial to wait until Revision 6 of the Updated FSAR is submitted on July 22, 1988.

Please replace Figures 1.4-5 and 1.4-6 and Tables 7.1-3 and 7.1-4 from the Updated FSAR with the attached figures and tables..

J

$j9] DOCK 05000267 O297 87o923 g

P g

l PDR

P-87317 September 21, 1987 The specific changes made to these tables and figures that are being submitted by this letter are as follows:

Figures 1.4-5 and 1.4 Added values to Relative Humidity (%)

and Time (Min) axes.

Table 7.1 Items 6 and 7 were deleted as they pertained to the Steam Pipe Rupture Detection System which was replaced with SLRDIS.

Item 9 was clarified for Circulators A and B.

Table 7.1 No changes necessary. This table is on the page adjoining Table 7.1-3.

If you have any questions or comments, please contact Mr. M. H.

Holmesat(303)480-6960.

I Very truly yours, s

s l

R. O. Williams, Jr.

Vice President, Nuclear Operations R0W/BRD:bac Attachments:

Updated FSAR Figures 1.4-5 and 1.4-6 Updated FSAR Tables 7.1-3 and 7.1-4 cc: Regional Administrator, Region IV Attention: Mr. J. E. Gagliardo, Chief Reactor Projects Branch (with one copy of Attachments)

Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain (with one copy of Attachments) j i

.4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter Public Service Company of Colorado

)

Docket No. 50-267 Fort St. Vrain Unit No. 1

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AFFIDAVIT R.

O.

Williams, Jr., being first duly sworn, deposes and says:

That he is Vice President, Nuclear Operations, of Public Service Company of Colorado, the Licensee herein, that he has read the foregoing information and knows the contents thereof, and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

R. O. Williams, Jr. f Vice President Nuclear Operations STATE OF 480 a dM' COUNTY OF

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Subscribed and sworn to before me, a Notary Public on this Blat day of (b,n tinrAs d

, 1987.

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$7ntary, && 8022 /

My commission expires OA4anA 2 2,1988 J

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e Table 7*1-4 UPDATED FSAR 4

Revision 5 O )

Primary Coolant Helium Circulator Trip Parameters 5ensed Variable!

Triph Type and humber Detec tor Basic Normal Full Load Absolutaf of input location Logic or Maatsum Value irlp Value

14. Circulator Speed (5 teas Ortve) 5 Pulse Pickup totti la Circulator 2 of 3 9.550 rpm 11.000 rpm Htgn (3 per circulator) lb. Circulator Speed (Water Ortve) W Pulse Pickup Colli In Circulator 2 of 3 7.000 rpm with 12 psia primary 8,800 rpm nigh (3 per circulator) coolant pressure 2.

Circulator 5 peed - Low (use 5

Pulse Pickup Colli In Circulator 2 of 3 9,550 rpm 1.910 rap (201 below only at Power)k (3 per circulator) normal, programed with feedwater flow 3a. Feedwater Flow. Low (use 5

P transmitters!

Turbine Butiding 2 of 3 1001 201 below normal pro-only at Powerli (hote d)

(3 per loop) gramed witn circulator speed Jb. Feedwater Flow - Low (use 5,W P transmitters!

Turbine Building 2 of 3 1005 20%

only at Power)8 (3 per loop) 4.

Bearing Water. Loss 5,W P switches Reactor Butiding 2 of 3 w650 psid 415 psid

)

l3 oer circulator)

?

l 5.

Circulator Seal Malfunction 5.W P transmitters Reactor Butiding 2 of 3 e30* H O l

1 2

(3 per circulator)

a. Bearing water Leakage to 10* H O

(

2 Primary Coolant Hign 1

1 l

b. Labyrinth hetlum Flow-Hig%..

-=

+80* H O 2

6.

Circulator Penetration 5,W P switches Reactor Building 2 of 3 110 psia 810 pstg l

Pressure. Hign (3 per circulator) 7.

Circulator Steam / water Orstn-5 P switcnes Reactor Su11 ding 2 of 3 45 pstd 5 psid Hal func tion (3 per circulator) 6.

Loop 5hutdown (use only at 5

Looo Shutdown Control Room 1 of 2 Loop $rutdown Powe r)5 Logic ( A&8)

(Soard 1 10)

(' A' or ' B' Logic) 9.

Manual (Separate for steam and 5,W Hand switch Control Room I of I

-=

water turntne)

(1 per ctreulator (Board 105) drive) 10a. 5 team Leak Detection 5,W Tempera ture Turbine Butidtng hote g 55'f/ min Turpine 8utIdtng Rate of Rise Loop I (4 per loop) 100. Steam Leak Detection 5,W Reactor Building Note g 55'F/ min Reactor Building Loop i luc. Steam Leak Detection 5,W Tuibtne Sutiding liote g 55*F/ min ivrbine Butiding Loop 2 104. Stese Leat Detection 5,W Reactor 8utiding hote g 55*F/ min.

Reactor 8vtiding Looo 2 I

h0f ts:

8-Notation la parenthesis refers to interlock sequence Switch Positions.

Iladicates trie: 5 = 5 teem Ortve; W = Water Turntne Drive; 5.W. = toth Ortves.

I S e same speed sensors are used for High and Low 5 peed Trip.

ih

  1. ctive only prior to scram.

A IIhe sance aP transmitters see used for both low feedwater flow trips on both circulators in the loop.

I ctual trip setpoints are more conservative to allow for instrument inaccuracy.

A 1

S ensing logic ts 2-out*of*d with a final output trip logic of 1 out-of-2 taken twtCo.

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