ML20039E843
| ML20039E843 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/07/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-15-09, TASK-15-9, TASK-RR NUDOCS 8201110535 | |
| Download: ML20039E843 (7) | |
Text
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January 7,1982 Docket No. 50-219 LS05-82-01-012 gy 3
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Mr. I. R. Finfrock, Jr.
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p"3, U,.?? s i-Vice President - Jersey Central j
Power & Light Company Post Office Box 388
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Forked River, New Jersey 08731 N
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Dear Mr. Finfrock:
SUBJECT:
OYSTER CREEK - SEP TOPIC XV-9 STARTdP OF AN INACTIVE LOOP AND FLOWCONTROLLERMALFU'ICTION(INCREASING)
By letter dated May 7,1981, you submitted a safety assessment report for the above topic. The staff has reviewed this assessment and our conclusion are prasented in the enclossd safety evaluation report, which completes this topic for Oyster Creek.
This evaluation will be a basic input to the integrated assessment for your facility. The evaluation may be revised in the future if your facility design is changed or if HRC criteria relating to this topic is modified before the integrated assessment is completed.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing 560Y
Enclosure:
5 As stated
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Mr. I. R. Finfrock cc G. F. Trowbridge, Esquire Resident Inspector Shaw Pittman, Potts and Trowbridge c/o U. S. NRC 1800 M Street, N. W.
Post Office Box 445 Washington, D. C.
20036 Forked River New Jersey 08731 J. B. Lieberman, Esquire Commissioner Berlack, Israels & Lieberman New Jersey Department of Energy 26 Broadway 101 Commerce Street New York, New York 10004 Newark. New Jersey 07102 Natural Resources Defense Council 91715th Street, N. W.
Washington, D. C.
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,J. Knubel BWR Licensing Manager GPU Nuclear 100 Interplace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton. New Jersey 08625 Ms. Phyllis Haefner 101 Washington Street Toms River New Jersey 08753 Mayor Lacey Township 818 Lacey Road Forked River, New Jersey 08731 U. S. Environmental P.rotection Agency Region II Office (ITN: Regional Radiation Representative 26 Federal Plaza New York. New York 10007 Licensing Supervisor Oyster Creek Nuclear Generating Station,
Post Office Box 388 l
Forked River, New Jersey 08731
)
0YSTER CREEK SEP TOPIC XV-9 STARTUP 0F AN INACTIVE LOOP - AND FLOW CONTROLLER MALFUNCTION 1.
Introduction The startup of an inactive or idle recirculation loop at an incorrect temperature and'a flow controller malfunction which causes an increase in core flow rate are abnormal events examined to assure that the consequences of such events are acceptable.
The guidance for the review of these topics is provided by SRP section 15.4.4 and 15.4.5.
These transients are evaluated because they both reduce the voids in the core, which causes an increase in power and reduces thermal margins. The calculated Minimum Critical Power Ratio (MCPR) is compared to the MCPR safety limit to demonstrate that fuel failures will not occur.
II.
Review Criteria Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility, including determination of the margins of safety during normal operations and transients conditions anticipated during the life of the facility.
Section 50.36 of 10 LFR Part 50 requires the Technical Specifications to include safety limits which protect the integrity of the physical barriers which guard against the uncontrolled release of radioactivity.
r
h.c beneral Design Criteria (Appendix A to 10 CFR Part 50) set forth the criteria icr tne design of water-cooled reactors.
GDC 10 " Reactor Design" requires that the core and associated cooling, control and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during normal operation, including the effects of anticipated operational occurrences.
GDC 15 " Reactor Coolant System Design" requires that the reactor coolant and asso-ciated protection systems be designed with sufficient margin to assure that the desi.on conditions of the reactor coolant pressure boundary are not exceeded during normal operation, including the' effects of anticipated operational occurrences.
GDC 20 " Protection System Functions" requires that the protection system be designed to initiate automatically the operation of reactivity control systems to assure.
that specified acceptable fuel design limits are not excee'ded as a result of anti-cipated operational occurrences.
GDC 26 " Reactivity Control System Redundance and Capability" requires that the rractivity control system be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, spe-cified acceptable fuel design limits are not exceeddd.
i GDC 28 " Reactivity Limits" requires that the reactivity control systems be designed with appropriate limits on the potential amount and rate of recctivity increase to l
l ensure that the effects of postulated reactivity accidents can neither (1). result i
l in damage to the reactor cociant pressure boundary greater than limited local yield-i
,ing nor (2) suffic'iently disturb 'the core, its support structures or othc reactor
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,a pressure vessel internals to impair significantly the capability to cool the core.
III Related Safety Topics Vario^us other SEP topics evaluate such items as the reactor protection system.
The effects of single failures on safe shutdown capability are considered under Topic VII-3.
I V.
Review Guidelines The review is conducted in accordance with SRP 15.4.4 and 15.4.5.
The evaluation includes review of the analysis for the event and identification of the features in the plant that mitigate the consequences of the event as a
well as the ability of these systems to function as required. The extent to i
which operator cction is required is also evaluated.
Deviations from the criteria specified in the Standard Review Plan are identified.
V. Evaluation The startup of an idle loop was analyzed for the Oyster Creek plant in reference 1.
Assumptions for this event are:
1) 109% power,100% flow from 4 operating pumps.
- 2) Water in is' lated loop is 100 F.
o 3)
Isolated loop suction, bypass, and discharge valves are opened coincident with pump start.
4)
Scram setting is at 116% power.
These assumptions are conservative compared to SRP requirements with the exception of the power level.
The SRP states that power should be 102% to t
account for rueasuring errors - this 2% increase is judged to not significantiy affect.the outcome of this analysis. Other assumptions used are discussed in reference 2.
Results of the analyses of the startup of an idle loop show tha'.
peak power (and scram) is reached 13 seconds into the transients, or about 7 seconds after the cool water from the idle loop reaches the core. The MCPR is 1.41, which is above the limiting value.
The analysis of a flow controller malfunction causing an increase in core flow rate was an.alyzed in references 3 and 4.
The event assumed a speed controller-failure causing the scoop tube positioner to move at the maximum rate which increases flow 10% per second.
The initial conditions of 63.5% power and 52% flow were chosen to maximize results of the transient.
Results of the analysis show the peak power of 75% of rated power occurs 13 seconds into the transient. The MCPR is 1.7, which is well above the limit.
No scram occurs for this transient, and power and flow stabilize a.t a new equilibrium value.
i Conclusion The staff has reviewed the Oyster Creek submittals on 3EP Topic XV-9, Startup of an Inactive Loop and Flow Contro'11er Malfunction.
The assumptions used in the analysis and results indicates that the Dyster Creek plant is in conformance with SRP section 15.4.4 & 5 requirements and is acceptable.
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RE ERENCES l.
Letter from GPU to NRC dated 2/5/76 2.
Letter from I. Finfrock, GPU, to W. Paulson, NRC dated 5/7/81 3.
Exxon Nuclear Company Report XN-74-41, Revision 2 dated 1/75 4.
Exxon Nuclear Company Report XN-74-43, Revision 2 dated 1/75 h
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