ML20010C020
| ML20010C020 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/31/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-15-03, TASK-15-10, TASK-15-3, TASK-RR NUDOCS 8108190010 | |
| Download: ML20010C020 (4) | |
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July 31,1981
,DIJTRIBUTION
(,Uocket NRC PDR Local PDR NSIC Docket No. 50-244 TERA LS05-81-07-096 ORB Reading DCrutch fiel d WRussell DSnaider Mr. John Mater HSmith Vice President EMckenna Electric and Steam Production OELD Rochester Gas & Electric Corporation 0ISE (3) 89 East Avenue ACRS (10)
Rochester, New York 14649
Dear Mr. Maier:
SUBJECT:
SEP TOPICS XV-3 AND XV-10 (CORRECTION) - GINNA PLANT Re: Design Basis Events issued by NRC Letter dated June 29,1981 from D. Crutchfield.
It has been brought to our attention that rme individuals who received our June 29, 1981 letter did not receive the first page to SEP Topic XV-10. Moreover, it has been noted that Reference 3 was inadv <rtently omitted from page 4 of SEP Topic XV-3.
The first page of Topi: XV-10 is being redistributed and page 4 of XV-13 should be replaced with the enclosed page 4.
Thank you for your cooperation.
Sincerely.
. i \\1 Original signed by
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Dennis M. Crutchfield, Chief 7 ; Operating Reactors Branch #5 p7 Division of Licensing 9,*-
Enclosurcs :
1.
XV-10, fir tRpa 2.
XV-3, page 4 % g-cc w/ enclosures:
See next page 8108190010 010731 PDR ADOCK 05000244 W
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Mr. John E. Maier July 31,1981 cc Harry H. 'Yoigt, Esquire Mr. Thomas B. Cochran
' LeBoeuf, Lamb, Leiby and MacRae Natural Resources Defense Council, Inc.
t 1333 New Hampshire Avenue, N. W.
1725 1 Street, N. W.
Suite 1100 Suite 600 Washington, D. C.
20036 Washington, D. C.
20006 Mr. Michael Slade U. S. Environmental Frotection Agency 4
12 Trailwood Circle Region II Office-Rochester, New York 14618 ATTN:
EIS COORDINATOR 26 Federal Plaza Ezra Bialik New York, New York 10007 Assistant Attorney General Environmental Protection Bureau Herbert Grossman, Esq., Chairman New York State Department of Law Atomic Safety and Licensing Board i
2 World Trade Center U. S. Nuclear Regulatory Commission New York, New York 10047 Washington, D. C.
20555 Jeffrey Cohen Dr. Richard F. Cole Nek York State Energy Office Atomic Safety and Licensing Board l
Swan Street Building U. S. Nuclear Regulatory Commission Core 1, Second Floor Washington, D. C.
20,555 Empire State Plaza Albany, New York 12223 Dr. Emmeth A. Luebke Atomic Safety and Licensing' Board Director, Bureau of Nuclear U. S. Nuclear Regulatory Commission Operations Washington, D. C.
20555 State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West
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Ontario, New York 14519 Resident inspector R. E. Ginna Plant c/o U. S. NRC 1503 Lake Road Ontarip, New York 14519 P
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TOPIC XV-10: CHEMICAL AND VOLUME CONTROL SYSTEMS MALFUNCTION THAT.RESULTS IN A DECREASE IN BORON CONCENTRATION IN THE RC.SCTOR COOLANT (PWR)
Introduction The Cher.ical and Volume Control System (CVCS) supplies reactor makeup water to the reactor coolant system via the reactor makeup control system. A boric acid blend. system is provided to permit the operator to match the boron concentration of reactor coolant makeup water to that in the reactor coolant system.' Reacti-vity can, therefore, be added to the reactor coolant if the boron dilution. pro-cess becomes uncontrolled.
l Review Criteria 1
The review criteria for boron dilution events is presented in SRP Section 15.4.6.
Since operator action is. generally relied upon to terminate the event, minimium time intervals of 30 minutes during refueling and 15 c.inutes during other oper-ational modes must be available from the time an alarm alerts the operator to loss of shutdown margin.
t Evaluation The licensee has performed an analysis for an uncontrolled beron dilution event (Ref.1).
The analysis assumes plant medes of refueling, startup-and power operation.
The rate of addition of unborated water makeup is limited to the capacity cf the makeup water pumps at the maximum combi ~ned flow of 120 gpm for i
both pumps.
DILUTION JURING.EFUELING The plant conditions for'tnis event include one residual heat remcval pump eperating, boron concentration of 2000 ppm, all control rods inserted, a min-d imum water volume in the reactor coolant system of 2724 f t (this corresponds to the volume necessary to fill the reactor vessel above the nozzles) and the maximum dilution flow of 120 gpm.
The results of the analysis indicate that the boron concentration must be re-duced from 2000 ppm to approximately 1080 ppm before the reactor will go criti-cal, and it would recuire 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> to reach criticality. The operator, therefore, will have sufficient time to recognize the high neutron count rate alarms in the containment and the control room and isolate the reactor makeup water source by closing valves and stopping the pumps.
DILUTION DURING STARTUP The plant conditions for this event include the reactor coolant system filled with borated water at 2000 ppm, reactor coolant pumps are operating anc the.
d volume of the reactor coolant is approximately 5247 ft which is the reactor i
coolant system excluding the pressurizer. All control rods.are also assumed inserted.
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4-XV-3 REFEREilCES (1) XN-fiF-77-40, " Plant Transient Analysis for the R. E. Ginna, L'11t 1, fiuclear Power Plant," fiovember,1977 (2) Letter from D. Ziemann (tiRC) to L.D. White (RG&E) dated February 25, 1980.
(3) i.etter from L. White (RG&E) to, D. Crutchfield (f RC) dated June 3,1980.
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