ML19247B183
| ML19247B183 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/10/1979 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7908080143 | |
| Download: ML19247B183 (7) | |
Text
&p'gg' Commonwealth Eciison b
One first National Plaza. Chicago Illinois Address Reply to: Post Office Box 767 M4 Chicago, Ilhnois 60690 July 10, 1979 Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III
~
U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Zion Station Units 1 and 2 Additional Information on IE Bulletin No. 79-07, "Saismic Stress Analysis of Safety-Related Piping" NRC Docket Nos. 50-295 and 50-304 Reference (a):
April 24, 1979 letter from C. Reed to J. G.
Keppler responding to IE Bulletin No. 79-07
Dear Mr. Keppler:
Per Reference (a), Commonwealth Edison Company responded to IE Bulletin No. 79-07, " Seismic Stress Analys1=
of Safety-Related Piping," for Zion Station.
In early June 1979, the 5".,C Licensing Staf f requested the following additional information with regard to commonwealth Edison's response in Reference (a) :
1.
Which Zion piping systems were analyzed by Westinghouse?
2.
Summarize the maximum stresses con uted using both methods and compare to the al]'awable stresses.
3.
Summarize the support loadings and compare to the allowable for both methods, n
In response to IE Bulletin No. 79-07, Westinghouse has performed a complete reanalysis for DBC for the Zion reactor coolant loop.
The original analysis utilized an algebraic sumnation of intramodal respons~es for the Zion loop.
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Commonwealth Edison NRC Docket Nos. 50-295/304 Mr. James G. Keppler: July 10, 1979 reanalysis used the absolute summation for this cambination.
fo]iewing additional information Attachment I contains th~e (five tables) from this reanalysis:
- 1) Comparison of original and new pipe stresses;
- 2) Comparison of the original and revised stresses as a fraction of allowables; and
- 3) Comparison of the original and new nozzle loads in the primary loop and revised stresses compared to allowables.
From Attachment I it is clear that piping stresses, nozzle loads and stresses and support loads and stresses are essentially identical to those obtained for the original case and are well below allowable values.
Please address any questians Trou may have concerning this matter to this office.
Very truly yours, I
G.
G o d\\
Cordell Reed Assistant Vice-Preside:n attachment cc:
Director, Divisior. of Reactor Operations Inspection 500 i?-
NRC Docket Nos. 50-295/304 ATTACHMENT I TABLE 1 PIPE STRESSES (SEISMIC ONLY)
STRESSES (KSI)
ORIGINAL SEI5MIC REVISED SEISMIC LOCATION RUN RU'i RPV Outlet 4.3 4.3 SG Inlet Elbow 3.8 3.8 SG Inlet 6.5 6.5 SG Outlet 2.4 2.4 SG Outlet Elbow
-1.8 1.8 Crossover Leg Elbow (SG Side) 1.2 1.2 RCP Inlet 1.7 1.7 RCP Outlet 2.0 2.0 Cold Leg Elbow 1.3 1.3 RPV Inlet 1.6 1.6 Cold Leg (Near LSV) 2.6 2.6 NOIE: Allowable seismic DBE piping stresses:
Hot Leg:
7.4 ksi Crossover Leg:
14.7 ksi Cold Leg:
14.5 ksi 500 tE
e TABLE 2 SUPPORT LOADS (SEISMIC ONLY)
(kips)
(in-kips)
Support Analysis Fx Fy F:
Mx My M2 SG Lower:
Original:
0 418 213 16879 2522 55878 Revised:
0 417 231 16892 2636 55883 i
SG Upper:
Original:
931 0
707 0
0 0
Revised:
931 0
712 0
0 0
t RCP:
Original:
20 146 78 3047 2143 3719 Revised:
21 157 79 3089 2144 3719 O
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TABLE 3
, SUPPORT STRESSES f
SUPPORT MAXIMUM STRESS (7. OF ALLOWABLE)
- 1) SG Lower A.
Lateral Frame 13.
B.
Columns 46.
- 2) SG Upper 19.
3)
RCP A.
Columns 24.
B.
Tie Rods 5.
C.
Column Support Frame 28.
1 Allowable based on most highly loaded component of support system.
Deadweight loads included. Values listed are for revised analysis.
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TAB 1E 4 PRIMARY EQUIR4EN'T N0ZZLE IDADS (SEISMIC ONLY)
(kips)
(in-kips)
Nozzle Analysis Fx Fy Fz Mx My M2 RPVIN Original:
58 33 63 2607 459 2485 Revised:
61 33 61 2566 460 2566 RPVON Original:
147 91 27 1016 3141 7764 Revised:
158 91 28 1017 3287 7773 1
SGIN Original:
158 166 25 2310 2276 12895 Revised:
166 174 26 2385 2339 12904 i
SGON Original:
47 47 32 4208 4577 4137 i
Revised:
48 48 32 4205 4578 4277 RCPIN Original:
33 33 36 2732 3466 2782 Revised:
33 28 38~
2733 3448 2017 i
RCFON Original:
68 28 47 4236 594 6187 Revised:
68 28 52 4671 595 6174 a
LSV Original:
147 91 27 1016 732 1772 (P c 14 )
Revised:
158 91 28 1017 741 1782 LSV Original:
63 28 26 2338 594 5730 (Cold Leg)
Revised:
63 28 26 2340 595 5734 NOTE:
Each load component is the maximum of the x-y or z-y shock. g d g
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1 TABLE 5 PRIMARY N0ZZLE STRESSR CAILUIATEDU)
AL1LMABLE N0ZZLE STRESS I!TTENSITY STRESS INTENSITY RPVIN 15.O ksi 20.9 ks1 RPVON 15.4 ksi 20.9 ksi SGIN 13.6 ksi
'23.2 ksi SCON 13.5 ksi 23.2 ksi RCPIN 12.7 ksi 18.4 ksi RCPON 13.9 ksi 18.4 ksi LSV (IIot Leg) 14.3 ksi 18.4 ksi LSV (Cold Leg) 13.8 ksi 18.4 ksi (1)
Calculated stress intensities are for revised analysis and include internal pressure, deadweight, and seismic loads.
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