ML20042A574
| ML20042A574 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/12/1982 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S NRC |
| References | |
| REF-SSINS-6820 IEB-80-04, IEB-80-4, NUDOCS 8203230571 | |
| Download: ML20042A574 (5) | |
Text
e M:lling Addr:ss Alabama Power Company 600 North 18th Street Post Office Box 2641 B.rmingham, Alabama 35291 Telepnone 205 783-6081 F. L Clayton, Jr.
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Director of Nuclear Reactor Regulation 2,1 S
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U. S. Nuclear Regulatory Commission
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Mr.
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,7, Joseph M. Farley Nuclear Plant - Units 1*& J2' Response to Questions Related to I. E.Bulletin 80-04 Gentlemen:
Alabama Power Company submits the following response to the request for additional information conce rni ng I.E.Bulletin 80-04, " Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition," for Joseph M. Farley Nuclear Plant Units 1 and 2.
The request for additional information was from Mr. Ed Reeves, the NRC FNP Project Manager.
Request Alabama Power Company's response concerning the MSLB analysis for Farley Units 1 and 2 indicated that main feedwater (MFW) was isolated automatically following a MSLB.
In order to complete the evaluation of the potential for exceeding containment design pressure, fu rther i nformation is required regarding the design of the MFW system.
Please provide the following information concerning the design of the steam and feedwater systems:
1.
Verification that the steam line and feedwater isolation systems meet the requi rements of IEEE Std 279-1971.
2.
Verification that the MFW isolation valves are Seismic Category I and safety grade (e.g., Quality Group B in accordance with Regulatory Guide 1.26, and envi ronment ally quali fied).
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Director of Nuclear Reactor Regulation March 12, 1982 U. S. Nuclear Regulatory Commission Page 2
Response
1.
The main steam isolation system meets the requirements of IEEE Std 279-1971 as shown in the attached table.
The main feedwater isolation system does not meet the requirements of IEEE Std 279-1971 since that standard was not a design basis for the feedwater system at the Farley Nuclear Plant.
The attached table shows which portions of IEEE Std 279-1971 are met by the Farley Nuclear Plant main feedwater isolation system.
2.
The main feedwater isolation. valves are Seismi c Ca tegory I.
The main feedwater stop-check val ves are Quality Group B and the main feedwater flow control and mini-flow control val ves are Quality Group C.
All of the main feedwater isolation valves are environmentally qualified.
If you have any further questions concerning this response, please contact us.
You rs very truly,
OCfan W F.' L. Clayton, r.
FLCJr/GGY: Jc Attachment cc:
Mr.
R. A. Thomas Mr.
G. F. Trowbridge Mr. J.
P.
O'Reilly Mr. E. A. Reeves Mr.
W. H. Bradford
ATTACHMENT ALABAMA POWER COMPANY RESPONSE TO ADDIT 10hAL INFORMATION CONCERNING 1.E. BULLETIN 80-04 COMPLIANCE WITH IEEE-279 Farley Nuclear Plant MAIN STEAM LINE ISOLATION (Note 1)
MAIN FEEDWATER ISOLATION (Note 1)
SYSTEMS System Components System Components YZED g
g DESIGN g
Main Steam Isolation Valves Main Steam Bypass Valves O
Main Feedwater Flow Feedwater Mini-Flow Main Feedwater Stop-CRITERIA Control Valves Control Valves Check Valves 1
2 3
4 5
6 7
8 General Function-Yes Yes Yes Yes al Requirement (IEEE-279-4.1)
Single Failure No n (IEEE-Yes
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Quality of Compo-nents and Modules Yes Yes Yes Yes (IEEE-279-4.3)
Equipment Qualif t-c-tion (IEEE-279-
}
Yes Yes Yes Yes 4.4) l (Note 2)
Cha..ei !.7tegrity tnd Independence Yes Yes Yes Yes (IEEE-279-4.5 &
o 4.6) i Control and Protec-tection System Yes Yes Yes Yes Interaction (IEEE-279-4.7)
Derivation of Sy-I stem Inputs Yes Yes Yes.
Yes (IEEE-279-4.8) i e
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ALABAMA POWER CO W ANY RESPONSE TO A00lT10hAL INFORMATION CONCERNING 1.E. BULLE M t10-04 Main Steam Line Isslation and Main Feedwat:r Isslation - Page 3 1
1 2
3 4
5 6
7 8
Identification Yes Yes Yes Yes (Note 2)
(IEEE-279-4.22)
NOTES:
1.
Main Steam Line Isolation and Main Feedwater Isolation are functions initiated by the Engineered Safety Features Actuation System.
A detailed evaluation of compliance with IEEE-279-1971 of the Engineered Safety Features Actuattor. System is given in the FSAR-Section 7.3.2.1.
2.
All three Main Feedwater Stop-Check Valves are train B oriented and supplied power from Class IE MCC IV, which is backed-up by a train 8 Diesel Generator. Each valve receives a closing signal when both Main Feedwater Pumps trip. Neither the equipment initiating the closing signals, nor the circuitry associated with those signals is Class IE.
3.
Although the Main Feedwater Isolation System does not meet the Single Failure Criterion, due to the fact that the closing signals of the Main Feedwater Stop-Check Valves are non Class IE, each Stop-Check Valve should be considered redundant to its series Flow-Control Valve so that, if one valve fails, the other one will perform the isolation function. In addition, each Flow Control Valve and its associated Mint-Flow Valve are provided with two redundant solenoids such that a single electrical failure will at prevent those valves from performing their intended function.
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