ML20137A543

Forwards Addl Changes to Catawba Unit 2 Proof & Review Tech Specs.No Significant Hazards Evaluation Required

ML20137A543
Person / Time
Site:	Catawba
Issue date:	01/02/1986
From:	Tucker H DUKE POWER CO.
To:	Harold Denton, Youngblood B Office of Nuclear Reactor Regulation
References
NUDOCS 8601140406
Download: ML20137A543 (3)

Text

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DUKE POWER GoxnuT P.O. HOX 33180 citA14LOTTE, N.C. uB242 HALB. TUCKER Teternoxe vaca emenment (704) 073-4531 str.a. man emontyvion E

January 2, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 -

Attention: Mr. B. J. Youngblood, Project Director ,

PWR Project Directorate No. 4 ,

Re: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Proof and Review Technical Spec'ifications

Dear Mr. Denton:

In response to your October 10, 1985 letter which transmitted the Proof and Review Technical Specifications for Catawba Units 1 and 2 and as a supplement to my letters of October 30, 1985, November-7, 1985, and December 17, 1985, attached are additional corrections found by our ongoing review. These additions are Unit 2 specific changes therefore, no significant hazards evaluation is required.

If you have any questions regarding this response please contact Mr. Roger W. Ouellette at (704)373-7530.

Very truly yours,

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E. dead A .

Hal B. Tucker RWO:slb Attachment O cc: Dr. J. Nelson Grace, Regional Administrator l

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r U. S. Nuclear Regulatory Commission

! Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 j, Lggft "*' *"b' 3

E1CSB (ROSA)

NRC Resident Inspector Catawba Nuclear Station I* lS8 g " j ,3 ros tennon)

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8601140406 860102 PDR P ADOCM 05000413 PDR )

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TABLE 3.3-4 (Continued) 9 '

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

~

h SENSOR '

, TOTAL ERROR i

c- FUNCTIONAL UNIT ALLOWANCE (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE z

j Q 8. Auxiliary Feedwater (Continued)

, v, j g c. Steam Generator Water 1

> Level - Low-Low

! I 1) Unit 1 17 14.2 1. 5 > 17% of span > 15.3% of N Trom 0% to 'ipan from 0% to 30% RTP 30% RTP increasing increasing linearly to

linearly to > 53.2% of span i > 54.9% of Trom 30% to 100%

i ipan from 30% RTP I

to 100% RTP

$ 2) Unit 2 17 14.2 1.5 2 17% of narrow range 1 15.3% of narrow range instrument

w  !

j J, span span .

d. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

i e. Loss-of-Offsite Power N.A. N.A. N.A. 1 3500 V 2 3200 V

f. Trip of All Main Feedwater Pumps N.A. N.A. N.A. N.A. N.A. 20 .

! g. Auxiliary Feedwater Suction Q Pressure-Low  %

l 1) CAPS 5220, 5221, 5222 N.A. N.A. N.A. 1 10.5 psig 1 9.5 psig 2

2) CAPS 5230, 5231, 5232 N.A. N.A. N.A. t 6.2 psig 3 5.2 psig -

o 9. Containment Sump Recirculation .

o O a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. O l

and Actuation Relays 4 j m b. Refueling Water Storage N.A. N.A. N.A. 1 177.15 inches 1,162.4 inches

! 3 Tank Level-Low .

1 Coincident With Safety j Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

l IJ.nM i j D Wib Z- N . A. Al . A , A).A. B G O et :2: 5.o esig

- 183 Rel bl b4C3=mOlnd2) WN-/oi El (o31+6 & o G A , , .

TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS E

FIRE MINIMUM INSTRUMENTS OPERABLE *

{ E ZONE DESCRIPTION LOCATION SM0KE FLAME HEAT FUNCTION **

w 180 Filter Bed Unit 28 Reactor 81dg.Be1. E1.565 + 3 2 0 2 A 181a Annulus E1.561 + 0 0 0 1 A R 181b Annulus E1.583 + 0 0 0 1 A 181c Annulus E1.604 + 0 0 0 1 A 181d Annulus E1.629 + 5 0 0 1 A 181e Annulus E1.649 + 5 0 0 1 A 181f Annulus E1.664 + 0 0 0 1 A 182a Annulus E1.561 + 0 0 0 1 A

, 182b Annulus E1.583 + 0 0 0 1 A l 182c Annulus E1.604 + 0 0 0 1 A w 182d Annulus E1.629 + 5 0 0 1 A i 182e Annulus E1.649 + 5 0 0 1 A w

182f Annulus E1.664 + 0 0 0 1 A_  ;

, 12 Aisles / Cables GG-57 E1.522 + 0 2 0 2 A-213 Aux. Batt. Room AA-55 E1.554 + 0 4 0 4 A 214 Aux. Cont. Pwr. Batt. AA-59 E1.560 + 0 4 0 4 A 215 0/G Corridor BB-45 E1.556 + 0 3 0 3 A 216 D/G Corridor AA-45 E1.556 + 0 2 0 2 A 217 D/G Corridor (Unit 2) CC-71 E1.560 + 0 3 0 3 A 218 D/G Corridor (Unit 2) 88-71 E1.560 + 0 2 0 2 A 219 Hech. Pene. Room HH-52 E1.577 + 0 6 0 6 A n 220 Hech. Pene. Room JJ-62 E1.577 + 0 6 0 6 A 2 222 Airlock Access JJ-51 E1.605 + 10 1 0 1 A mo 224 Airlock Access (Unit 2) JJ-63 E1.605 + 10 1 0 1 A Q 225 RN Pump Structure West Section E1.600 + 0 8 0 8 A 226 RN Pump Structure East Section E1.600 + 0 8 0 8 A -

c3 231 Reactor Bldg. (Unit 3) 260*-303* E1.668 + 10 10 0 0 A. O S 232 Reactor Bldg. (Unit 2) 260 -303* Be1. E1.668 + 10 10 0 ,

O A O

o 184 HVAC Duct for Rooms 331 and 332 FF-53 E1.543 + 0 1(Ouct) 0 0 A -<

n 185 HVAC Duct for Rooms 203, 205 FM-60 E1.543 + 0 1(Duct) 0 0 A j

gm 205A, 206A, 2068, 207 and

209A .

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