ML20153F079

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Forwards Suppl to Author ,Correcting Final Draft Tech Specs Covering Fire Detection Instruments.Error Identified as Category 1 Error
ML20153F079
Person / Time
Site: Catawba  
Issue date: 02/18/1986
From: Tucker H
DUKE POWER CO.
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
NUDOCS 8602250305
Download: ML20153F079 (2)


Text

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,,.>lre DUKE POWER GOMPANY P.O. Itox 33180 CIMRLOTTE, N.C. 28242 HALB. TUCKER TELEPHONE vum ramenoung (704)a m sag smaan emosextson February 18, 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 No. 50-413 and 50-414 Final Draft Technical Specifications

Dear Mr. Denton:

As a Supplement to my February 10, 1986 letter attached is a correction to the Final Draft Technical Specifications.

This error is of a kind that can be placed into Category (1) as identified in my previous letter.

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

Very truly yours, h

  • w Hal B. Tucker RWO:slb Attachment cc:

Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident-Inspector g8[f Catawba Nuclear Station

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TA8LE 3.3-11 (Continued)

-4 FIRE DETECTION INSTRUMENTS I

g FIRE MINIMUM INSTRUMENTS OPERA 8LE*

E ZONE DESCRIPTION LOCATION SMOKE FLAME HEAT FUNCTION **

69 Cable Room CC-59 E1.577 + 0 18 0

15 A

71 Elect Pene. Room CC-51 E1.594 + 0 10 0

0 A

72 Control Room CC-56 E1.594 + 0 23 0

6 A

73 Vent. Equip. Room FF-56 E1.594 + 0 9

0 0

A 74 Aisles / Cables LL-56 E1.594 + 0 25 0

25 A

76 Aisles / Cables PP-54 E1.594 + 0 15 0

15 A

79 Elect. Pene. Room 88-63 E1.594 + 0 11 0

0 A

80 Control Room 88-59 E1.594 + 0 0

6 A

81 Ven. Equip. Room FF-58 E1.594 + 0 12

,0 0

hA 82 Aisles / Cables KK-58 E1.594 + 0 1

0

  1. 2A A 84 Afsles/ Cables NN-58 E1.594 + 0 0

A 89 Fuel Pool Area #1 PP-50 E1.605 + 10 19 7

19 A

90 Fuel Pool Area (Unit 2)

PP-64 E1.605 + 10 19 7

19 A

R 128 UNI 81dg.

HH-44 E1.550 + 0 2

3 2

A 129 Fuel Pool Purge Room (Unit 1)

NN-50 E1.631 + 6 6

0

'6 A

Y 130 UNI 81dg. (Unit 2) -

.HH-71 E1.594 + 0 2

3 2

A M

D!

131 Reactor 81dg.

0*-45*

8el. E1.565 + 3 4

0 0

A f

132 Reactor 81dg.

45'-90*

Be1. E1.565 + 3 3

0 0

A 133 Reactor 81dg.

90*-135' Be1. E1.565 + 3 4

0 0

A g

134 Reactor 81dg.

135*-180 8el. E1.565 + 3 5

0 0

A 135 Reactor 81dg.

180*-225' 8el. E1.565 + 3 4

0 0

A N

136 Reactor 81dg.

270*-315*

Be1. E1.565 + 3 3

0 0

A

$g 137 Reactor 81dg.

315'-0*

8el. E1.565 + 3 8

0 0

A smy 138 Reactor 81dg.

0*-45' Be1. E1.586 + 3 6

0 0

A g

139 Reactor 81dg.

45*-90*

Be1. E1.586 + 3 4

0 0-A 140

. Reactor 81dg.

90*-135' 8el. E1.565 + 3 3

0 0

A 141 Reactor 81dg.

135*-180 8el. E1.586 + 3 8

0 0

A 142 Reactor 81dg.

180*-225*

8el. E1.586 + 3 5

0 0

A 143 Reactor Bldg.

315*-0*

8el. E1.586 + 3 5

0 0

A 144 Reactor 81dg.

0*-45' 8el. EI.593 + 2 14 0

0 A

$g cs 145 Reactor 81dg.

45*-90*

8el. E1.593 + 2 17 0

0 A

146 Reactor 81dg.90-135' Be1. E1.593 + 24 11 0

0 A

a

-a a

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