ML17319B614
| ML17319B614 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/04/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17319B615 | List: |
| References | |
| GL-81-14, NUDOCS 8211010407 | |
| Download: ML17319B614 (5) | |
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OCT 4 >982 Docket Nos. 50-315 and 50-316 11r. John Dolan, Vice President Indiana and tiichigan Electric Company Post Office Box 18 Bowling Green Station New York.,New York 10004
Dear Nr. Dolan:
DISTRIBUTION Docket Files NRC PDR Local PDR ORB 1 File D. Eisenhut C. Parrish D. Higginton OELD I8E (1)
The Commission has completed its review of the seismic qualification of the auxiliary feedwater system for the D. C, Cook Unit Nos.
1 and 2.
Our Safety Evaluation Report and our contractor Technical Evaluation Report are enclosed for your information.
Ite have concluded in our review that the D. C. Cook auxiliary feedwater systems have sufficient capability to withstand a safe shutdown earthquake and accomplish its safety function.
Accordingly, we are not contemplating any seismic upgrading of these systems and this item is complete.
Sincerely, Encl osur e:
As stated cc w/enclosure:
See next page LO/18ina1 Signing bye P. ~ ke Vary'teven A. Var ga, Chief Operating Reactors Branch No.
1 Division of Licensing 8211010407 821004 PDR ADOCK 0500031 5 PDR ORB 1
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DATE Q NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY
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~ 0 Mr. John Dolan Indiana and Michigan Electric Company cc:
Mr. Robert W. Jurgensen 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 W.
G. Smith, Jr., Plant Manager Donald C. Cook Nuclear Plant P. 0.
Box 458 Bridgman, Michigan 49106 U. S. Nuclear Regulatory Commission Resident Inspectors 0ffice 7700 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 James G. Keppler Regional Administrator - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El.lyn, Illinois 60137
EN CLOSURE
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SAFETY EVALUATION REPOR'F D.C.
COOK UNITS 1
AND 2 SEISMIC UALIFICATION OF THE AUXILIARY FEEDWATER SYSTEM Introduction Since the accident at Three Mile Island attention has been focused on the ability of pressurized water reactors to provide reliable decay heat removal.
While it is recognized that alternate methods may be available to remove decay heat following transients or accidents, heat removal via the steam generators is the first choice for accomplishing a safe shut-down of the plant.
Therefore, there should be reasonable assurance that the auxiliary feedwater system (AFW) can withstand the postulated Safe Shutdown Earthquake (SSE), consistent with other safety-related systems in the plant.
To address this concern, the NRC developed and initiated Multiplant Action C-14, "Seismic gualification of Auxiliary Feedwater Systems."
The objec-tive of this plan is to increase, to the extent practicable, the capability of those plants without seismically qualified AFW to withstand earthquakes up to the SSE level.
This program was implemented with the issuance of NRC Generic Letter 81-14, dated February 10, 1981.
Our review of the licensee's responses to this letter is the subject of this evaluation.
Evaluation The enclosed report was prepared for us by our consultant, Lawrence Livermore National Laboratory, as part of our technical assistance contract program.
The report provides their technical evaluation of the licensee's conformance to the requirements of Generic Letter 81-14.
We have reviewed the consultant's report.
In his Technical Evaluation Report, the consultant concludes that the AFW system is seismically qualified f'r the safe shutdown earthquake, with two exceptions.
The two exceptions involve:
(1) the section of the main feed-water (MFW) piping, at the interface with the AFW system, between the first check valve and the automatically-actuated motor operated valve, and'(2) a fabricated sheet-metal structure that encloses the first valve and about three feet of piping downstream of the condensate storage tank (CST), toward the suction of the AFW pumps.
Subsequent to the consultant's
- review, we have confirmed with the licensee that the failure of the section of the MFW pi'ping in question is 5ounded Gy the licensee's previous analysis of a main feedwater line break accident and further, is protected by the seismic class 1 check valve.
Similarly, we have confirmed with the licensee that a
failure of the sheet-metal structure near the CST is not likely to have a
significant impact on the enclosed Class 1 piping and further will not have any adverse effect upon the alternate source of cooling water - i.e., the essential service water system.
Conclusion Based upon our review of the consultant's technical evaluation report and the confirmations we have received from the licensee, we conclude that there is reasonable assurance that the auxiliary feedwater system has sufficient capability to withstand a safe shutdown earthquake and accomplish its safety function.
Accordingly, we are not contemplating requiring any seismic upgrading of this system under the NRC Nultiplant Action C-14 program.
We consider the consultant's report to be final, in that no further tech-nical effort is required..
This safety eyaluqtion was. prepared by.'Hp, J'.T; Beard, Engineering Section, Operating', Reactors Assessment
- Eranch, Di;yiSion of.Licensing.