ML20205G764
| ML20205G764 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/05/1985 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8511130332 | |
| Download: ML20205G764 (6) | |
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DUKE POWER GOMPANY P.O. BOX 33189 i
CHARLOTrE. N.C. 28242 HAL B. TUCKER ap,,a
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November 5, 1985 Mr. Harold'R. Denton, Director
..' Office of Nuclear Reactor Regulation
- U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Ms..E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear. Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Duke-Power Company's response to NUREG-0588,-Rev. 6 identifies all safety-related equipment located in a harsh environment. The equipment listed is applicable to both Units 1 and 2.
Attached are NUREG-0588 EQ aummary sheets for specific Unit 2 equipment different from Unit 1.
These summary sheets will be included in Rev. 7 of the response. Additionally, all harsh environments listed in the response are ' worse case' for that equipment for both units.
It should be.noted that electrical enclosures were identified as Unit 1 specific (i.e., IEATC9,.1TBOX0001, etc.).
The same enclosure identifying number is applicable to Unit 2 enclosures with the first number changed from a.1 to a 2, (i.e., 2EATC9, 2TBOX0001, etc.).
Furthermore, the follow-ing Unit 1 enclosures have no Unit 2 counter 1. art:
1ELCP0243 ITBOX0345 ITBOX0346
's This information and clarification will also be included in Rev. 7 of the response.
-Very truly yours, s
gp f
Hal B. Tucker
..ROS: sib
Attachment:
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8511130332 851105 T
DR ADOCR 05000413 p
Mr. Harald R; Denten,1DirIctsr
- November,5,'1985-
-Page'A o
- 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
. Cat.awba Nuclear' Station t
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C v
y CATAWBA-NUCLEAR' STATION - UNITS.1 AND 2'.
Page 3a
.SUMARY OF-ENVIRONMENTAL QUALIFICATION 0F CLASS'1E EQUIPMENT Rev. 4-
. LOCATED INSIDE CONTAINMENT' EQUIPMENT ID: ' Transmitter -
MANUFACTURER:
Rosemount.
MODEL #:
1153HD5PB-(1)
RCS Flow-(LgwgrCggtainment)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCUn.:.'Y -
- ENVIRONMENT T0 WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED.
.(2)
. QUALIFIED ACCIDENT
(% OF SPAN)
(% OF. SPAN)
ENVIRONMENT The RCS Flow signalstare not required for accidents.that cause a change in the normal coricainment operating environment.
Further, failure of these transmitters as a resulttof exposure to a harsh environment will'not preclude the safety function of other. equipment claimed in the accident. analysis. Additionally, the information provided by these transmitters is not employed as a post accident monitoring parameter forfoperator. action.
SUBMERGENCE:
N/A QUALIFICATION REPORT:
N/A METHOD:
N/A REPLACEMENT INTERVAL:
N/A MDIC
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CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 18c
SUMMARY
OF ENVIRONMENTAL QUALIFICATION OF. CLASS 1E EQUIPMENT Rev. O LOCATED.INSIDE CONTAINMENT EQUIPMENT ID:
Valve Solenoid Operators -
MANUFACTURER:
ASCO MODEL #:
NP8316E36E/E34E (1)
Prescurizer PORVs - Unit 2 (Lower Containment)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)
QUALIFIED ACCIDENT
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT Temp:
327 F Temp:
346 F
<30 days 30 days N/A N/A Press:
14.4 psig Press:
100%psig post DBE post DBE 110 RH:
100%
RH:
Rad:
1X10 R Rad:
0.2X10sg 8
Chem Spray: Boric Chem Spray: Boric acid and sodium acid, and sodium tetraborate soln.
thio-sulfate and sodium hydroxide soln.
3000 ppm 10 pH SUBMERGENCE:
No QUALIFICATION REPORT:
ASCO Report AQS21678/TR Rev. A (CNM-1705.02-0499)
METHOD: Test REPLACEMENT INTERVAL:
4 yrs. for coils & elastomeric materials.
MDIC
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v.,
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A
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CATAWBA NUCLEAR STATION
- UNITS l'AND 2~.
.Page la-SUt91ARY OF ENVIRONMENTAL: QUALIFICATION OF CLASS 1E EQUIPMENT-:
Rev. 0
~ LOCATED IN THE. ANNULUS EQUIPMENT ID:
Transmitter -
MANUFACTURER:
Rosemount' MODEL #:
1153HD4PB Steam Generator Level.-(N/R)
(Unit 2)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ~
. ACCURACY
. ACCURACY-ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED.
REQUIRED DEMONSTRATED (1)
-QUALIFIED ACCIDENT (2)-
-(% OF SPAN)
.(% OF SPAN)
ENVIRONMENT Function:
< 5% (5 min)
-3 Temp:
IS0*F Temp:
350 F Reactor Trip 4 months Trip (5 min) 15%
RH:
100%
RH:
100%
(<5 minutes) post DBE Rad:
1.7x107
' Rad:
.5X10 R plus 4 months' 7
- Max Error < 15% '
25% (4 mo)
QUALIFICATION-REPORT:.Wyle Report 45592-3
. METHOD: Test REPLACEMENT INTERVAL:
10< Years MDIC
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-CATAWBA NUCLEAR STATION - UNITS 1 AND 2. -
SUNIARY.0F ENVIRONMENTAL QUALIFICATION 0F CLASS 1E EQUIPMENT.
Page:la-Rev.: 0.
LOCATED OUTSIDE CONTAINMENT AND dXPOSED TO PIPE RUPTURE ENVIRONMENT-l EQUIPMENT ID: Transmitter -
"f3H5ACTURER:
Rosemount MODEL #:
1153DB6PB Main Feedwater Flow (Doghouse) (Unit 2)
PIPE RUPTURE ENVIRONMENT OPERABILITY OPERABILITY.
. ACCURACY.
ACCURACY' ENVIRONMENT
'TO WHICH
' REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)
QUALIFIED iPIPE RUPTURE
'(%.0F SPAN)
(% OF SPAN)
ENVIRONMENT (2) y The Main Feedwater Flow signals are not required for pipe ruptures that cause a change in the normal Auxiliary Building (Doghouse)' operating environment.
Further, failure of this equipment as a result of exposure to a harsh environment will not preclude the safety function of.other equipment claimed _in the accident post' accident analysis.
Additionally,-
the information provided by this equipment is not employed as a post accident monitoring parameter for operator action.
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ij QUALIFICATION REPORT:
N/A METHOD:
N/A REPLACEMENT INTERVAL:
N/A MDIC