ML20052D504
| ML20052D504 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/14/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| IEB-80-04, IEB-80-4, NUDOCS 8205060517 | |
| Download: ML20052D504 (4) | |
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DISTRIBUTION Docket File '
APR 141982 ORB 1 File D. Eisenhut OELD Docket Nos. 50-295 OI&E (1) y and 50-304 D. Wigginton f,
C. Parrish 4
,3 Mr. Louis 0. De1 George J. Heltemes APR 27198b Director of Nuclear Licensing FRC 6-a um muur masa Conemnwealth Edison Company 8 mum memu m 4
Post Office Box 767 Chicago, Illinois 60690 9
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Dear Mr. De1 George:
In our review of the Coniaonwealth Edison Company's Itay 8,1980 lettor in response to IE Bulletin 80-04, Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition, we have identified additional information which we need to complete this action.
Enclosed is the request for additional infonnation which was prepared by Franklin Research Center for the Zion Station, Unit Nos. 1 and 2.
It is requested that Coninonwealth Edison Company provide a response within i
45 days of receipt of this letter.
i Sincerely, i
Steven A. Varga Chief Operating Reactors Branch No.1 l
Division of Licensing
Enclosure:
Request for Additional Infonnation cc w/ enclosure:
See next page l
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r" Mr. Louis 0. DelGeorge Commonwealth Edison Company cc:
Robert J. Vollen, Esquire 109 North Dearborn Street Chicago, Illinois 60602 Dr. Cecil Lue-Hing Director of Research and Development Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Zion-Benton Public Library District 2600 Emmaus Avenue Zion, Illinois 60099 Mr. Phillip P. Steptoe Isham, Lincoln and Beale Counselors at Law One First National Plaza 42nd Floor
'C'hicago, Illinois 60603 Susan N. Sekuler, Esquire Assistant Attorney General Environmental Control Division 188 West Randolph Street, Suite 2315 Chicago, Illinois 60601 U. S. Nuclear Regulatory Commission
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Resident Inspectors Office 105 Shiloh B1id.
Zion, Illinois 60099 James P. Keppler Regional Administrator - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 l
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REQUEST FOR ADDITIONAL INFORMATION l PWR MAIN SYEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION COMMONWEALTH EDISON COMPANY ZION STATION UNITS 1 AND 2
- 2 NRC DOCKET NO. 50-259, 50-304 FRC PROJECT C5506 NRC TAC NO. 46869, 46870 FRC ASSIGNMENT S NRC CONTRACT NO. NRC-03-81 130 FRC TASK 144 Preparedby Franklin Research Center Author: F.Vosbubaizo T. J. De 20th and Race Street Philadelphia, PA 19.103 FRC Group Leader: R. C. Herrick Prepared for Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer:
P. Hearn s
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March 15, 1982 Cortiflod By
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. 0. Franklin Research Center
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A Division of The Frarddin Insdtute The aw rreseen Penr or.PNia.Pa. islas (2:5 Has.ioco e
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BACKGROUND 3
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Evaluation of the information contained in the May 8, 1980 [1] letter from Commonwealth Edison Company (CWE) to the Nuclear Regulatory Commission (NRC) relating to IZ Bulletin 80-04, Analysis of a PWR Main Steam Line Break
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with Continued Feedwater Addition, revealed an item of concern. Additional information relating to this concern is needed before a final evaluation can l
be made regarding the potential for exceeding containment design pressure.
This concern and the additional information needed to resolve the concern i
are identified in this Request for Additional Information.
ITDi CONCERN - CWE's response to Item 1 of IE Bulletin 80-04 stated that auxiliary feedwater (AN) will continue to be injected into the affected steam i
generator following a main steam line break (MSLB) until. isolated by operator action. CNE stated that isolation of the AFW system will occur in 10 minutes and provided justification for the assumption of this time period. In order to complete the evaluation of this matter, additional information is needed.
N REQUEST Please provide the following information concerning containment pressure response to a MSLB with continued feedwater addition:
1.
When will containment design pressure be exceeded (i.e., number of minutes after the start of a MSLB) if no operator action is taken to terminate the accident? This determination should be made for both throttled AN flow and runout AFW flow, since a single active failure (e.g., operator error) could cause an improper throttle setting.
t 2.
Provide the magnitude of the peak pressure and the time at which the peak occurs, for both cases of throttled and runout AFW flow.
REFERENCE 1.
D. L. Peoples (CNE)
Letter to J. G. Esppler (NBC, Region III)
Subjecti Besponse to IE Bulletin 80-04 May'8, 1980.
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