ML17319B178
| ML17319B178 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/15/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| IEB-80-04, IEB-80-4, NUDOCS 8202080130 | |
| Download: ML17319B178 (9) | |
Text
yo SAN l5 $ 82 Docket Nos. 50-315 and 60-316 o/
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+/P Ih. John Dolan, Vice President
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Indiana and Hfchfgan Electric Company Post Offfce Box 18 Bowling Green Station New York, New Yor k 10004
Dear Hr. Dolan:
DISTRIBUTION Dockets NRC PDR L PDR TERA" NSIC ORBIII1 Rdg DFi senhut OELD IE-3 ACRS-10 CParrish NGrotenhuis Gray File lie have completed our preliminary review of your letter. dated April 8, 1980 regarding Bulletin 80-04, I'lain Steam Line Break with Continuing Feedwater Addition, for the D. C. Cook Nuclear Plant Unit Nos.
1 and 2.
>Ie find that we need the additional information outlined fn the enclosure to this letter.
Please provide this information within 46 days of the receipt of this letter.
Sincerely,
~iginal signed bV:
S. A. Varga Steven A. Yarga, Chfef Operatfng Reactors Branch 81 Division of Licensing Enclosure.:
Request for Addftfonal Informatfon cc w/enclosure:
See fnbxt page
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OFFICIAL RECORD COPY USGPO. 1981 339.990
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Mr. John Dolan Indiana and Michigan Electric Company cc:
Mr. Robert W. Jut gensen Chief Nuclear Engineer American Electric Power "Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C.
20036 Maude Preston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Mr. D. Shaller, Plant Manager Donald C.
Cook Nuclear Plant P. 0.
Box 458 Bridgman, Michigan 49106 U. S. Nuclear Regulatory Commission Resident Inspectors Office 770 Red Arrow Highway Stevensville, Michigan 49127 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.
20515
REQUEST FOR ADDITIONALINFORMATION PWR MAIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDITION INDIANA AND NICHIGAN ELECTRIC CONPANY DONALD C COOK NUCLEAR PLANT UNITS j. AND 2 NRC OOCKET NO.
50-315, 50-316 NRC TAG NO.
- 46829, 46830 Franklin Research Center A Division of The Frankiin Institute The Benjamin Frankrin Patkway. Phila.. Pa. 19103 (215) 448.1000
BACKGROUND Evaluation of the information contained in the April 8, 1980 letter
[1]
from Indiana and Michigan Electric Company (IMEC) to the U.S. Nuclear Regulatory Commission (NRC) relating to IE Bulletin 80-04, "Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition," revealed an item of concern.
Additional information relating to this concern is needed before a
final evaluation can be made regarding the potential for exceeding containment design pressure or worsening of reactor return-to<<power response.
This concern and the additional information needed to resolve it are identified in this Request for Additional Information.
Supplemental information now held by FRC relating to this matter is noted in the bibliography included in this request.
ITEM CONCERN IE Bulletin 80-04 directs the Licensee to review containment pressure response to a main steam line break (MSLB) accident to determine the impact of runout flow frora the auxiliary feedwater (AFW) system and other energy sources.
1 IMEC's response concerning the MSLB analysis for the Donald C.
Cook Nuclear Plant Units 1 and 2 indicated that the AFW system was assumed to be manually isolated by operator action 10 minutes after the initiation of the accident.
IMEC's response is not sufficient to allow FRC to complete the evaluation of the potential for exceeding containment design pressure.
The analysis takes credit for operator action to identify the affected steam generator and isolate AFW flow to that generator within 10 minutes after the start of th'e accident.
In the light of studies performed on operator response to stressful situations, this time may be unrealistic.
REQUEST Please provide the following information concerning your analysis of containment pressure response to a MSLB with continued feedwater additions
()tl Franklin Research Center h olvsno or The FfsnkÃn Instance
l.
An evaluation of the potential for exceeding containment design pressure<
assuming no operator action.
2.
The time after the start of a MSLB when containment design pressure will be exceeded if no operator action is taken to terminate the accident.
If the containment design pressure will be exceeded in less than 30 minutes, provide the magnitude of the peak pressure and the time at which the peak occurs.
- 3. If operator action is required to terminate the accident, provide justification for the time at which credit is taken for operator action.
The criteria gitren in draft ANSI N660, "Time Response Design Criteria for Safety-Related Operator Actions," March 1981, should be addressed and any differences between the time taken for operator action and the ANSI N660 criteria should be justified.
4.
A verification that the steam line and feedwater isolation systems meet the requirements of IEEE Std 279-1971.
5.
A verification that the MFW isolation valves are Seismic Category I and safety grade (Quality Group B in accordance with Regulatory Guide
- 1. 26, and environmentally qualified).
6.
A schedule for the proposed corrective actions< if any corrective actions are required due to the above evaluations, and for appropriate actions taken during the interim period until corrective actions are completed.
Franklin Research Center AOvtsen d The F ranldng hs8utc
REPERENCE 1.
J.
E.
Dolan (IMEC)
Letter to J.
G. Keppler (NRC)
April 8, 1980 BIBLIOGRAPHY 1.
D.
C.
Cook Units 1 and 2
Pinal Safety Analysis Report Section 14.2.5 Questions
- 22. 9, 212.7, 212. 23, 212. 24, 212. 25, 212. 34, and 212. 35 09 Franklin Research Center h Dtvlsen ot 1be FrankSn Insane
y 4