ML20126A813
| ML20126A813 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 01/30/1980 |
| From: | Szechowycz A SARGENT & LUNDY, INC. |
| To: | Halapatz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20126A811 | List: |
| References | |
| NUDOCS 8002260264 | |
| Download: ML20126A813 (2) | |
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3.\\ E D E m 3: L L':. DY z s m m r: m.s re s =c te s* racco c= sAmog wr e es 5 5 EAST W C*aA C E 2 7 2 C Cf C,46CAGO. lLINCIS 60003
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- 312 2 6 9 2 C 0 0 OAeLE accats? - Sam a.,ma-c mcaco January 30, 1950 Project 4120-00 The Cincinnati Gas & Electric Ccmpan"1 Wm.
H.
Zimmer 'iuclear Power Station - Unit 1 Pressure Inspection Program Plan AS"E Section XI, 1974 Edition :*.'3 1220b (1)
Exemption frcm *lciumetric Ex:c:ination Mr. J.
Halapat:
Materials of Engineering Branch Office of Nuclear Rec';1ation Nuclear Regulatory Cc= mission Washington, DC 20555
Dear Mr. Halapat:
The calculation for the exemption diameter by make-up capacity as permitted by ASME Boiler and Pressure 'lessel Code Section e::,
1974 Edition, Article 2, IM3-12 20 b (1) is based en the GE dec=.en:
22A2756, Revision 2, Section 3. 2. 2.
The normal reactor ecclan:
make-up system is defined as includinc the feedwater, condensate /
feedwater transfer, centrol r:d drive re: urn and the reacter cere isolation cooling system.
"Onsite" power (see no te 5, Article lW3-1220, 1974 Edition) is defined as electric power normally available ensite during nc =al Operation including startup, het standby, cperation ecol dcwn or shut dcwn of the plant.
This includes power available from outside lines.
Licuif lines are defined as those lines which oenetrate the reactor tressure vessel belov the normal water level and ste.m lines are these wnich penetra:e reactor pressure vessel abcve the nc =al water leve*_.
"tr -= ' -"' ation purocses, the water flew rates frcm a 1.c;id line ':reak is taken 3.-
3,000 pounds /
second/fcet2 a: 1000 psi.
The stear ficw races frc= a s:s:=
line bre::, are ta :en as 2.00 cunds/seccnd/fced at 1200 psi.
The make-up water zeighs 3. 32 lbs. cer gallen at. 70"7.
8002260 M
SARGENT & LUNCY ENGINEERS OMICAGQ Mr. J.
Halapat:
January 30, 1990 Nuclear Regulatory Ccmmission Page 2 The cctbined flew rate from the Reactor Core Isolation Ccoling system, Centrol Red Drive system and the Feedwater syster are used to determine normal make-up capability.
The Condensate /
Feedwater gravity feed capacity is used rather than the Feed-water pump capacity because the hotwell volume is limited to a few minutes of feedwater pump operation at maximum ficw.
The condensate storage water supplied by the condensate /foedwater cravi:';
flow will be required to maintain feedwater pump sucticn head in the hotwell until the reactor pressure vessel is brought down to atmospheric ccndition.
The formula provided by GI for the IME-1220b (1) exempted inside diameter for water is D..r (inches) =V:1.'17. 3.
The e::empted inside diameter for steam is 2Dw, where !! is the total normal make-up fl,ow rate in gallons of water per minute (GPM).
The normal make-up capacity is based on CRD Flow rate of 58.6 gym, RCIC flow rate at 400 gym, and condensate /feedwater gravity feed rate of 970 gpm.
Based on the above, the exempted inside diameter for water is 2.12 inches and for steam it is 4.24 inches.
The Mm.
H.
Zimmer Nuclear Power Station pre-service inspection plan has been developed using the above exemption diameters and are referred to in Table 3-1 of the Preservice Inspection Precrar 1
Plan.
We would sopreciate a prompt reply en the acceptance of the above calculation methods, especially since the definition cf the exemption diameter is continually being modified in later editions of the code.
Yours very truly, 1
/ /'
I A.
N.
S:echewyc:
Mechanical Engineer AW3:1gk In duplicate Attachment Ccpies:
E. A. Borgmann (2/0)
W.
N.
Schwiers (1/0*)
H. C. Brinkmann (1/0)
I D.
F. Frederich (1/0)
R. J.
Pruski (1/0) r
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