ML20052E687
| ML20052E687 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/30/1982 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| MP-1-2060, NUDOCS 8205110350 | |
| Download: ML20052E687 (2) | |
Text
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L L TJ :::::C;;;2"O"!l l April 30,1982 MP 2060 Mr. Ronald C. Haynes
/ /,y Regional Administrator, Region I c) g e, s,
s Office of Inspection and Enforcement
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U.S. Nuclear Regulatory Commission b
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631 Park Avenue N/
King of Prussia, Pennsylvania 19406 7
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Reference:
Facility Operating License No. DPR-21
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Docket No. 50-245
Dear Mr. Haynes:
Attached is an informational letter regarding the discovery of pressure and level instrumentation setpoints above specification during Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip / Alternate Rod Calibration Test, on March 22,1982.
Yours truly, NORTHEAST NUCLEAR ENERGY COMPAlY f
E./d. Mroczka Station Superintendent Millstone Nuclar Power Station EJM/TST:mo i
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Attachment:
Pressure and Level Instrumentation Setpoints above Specification cc:
Director, Office of Inspection and Enforcement, Washington, D.C. (30)
Director, Office of Management Information and Program Control, l
Washington, D. C. (3) l U.S. Nuclear Regulatory Commission, c.o Document Management Branch, i
Washington, D.C.
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ATTACHMENT NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION PROVISIONAL LICENSE NUMBER DPR-21 DOCKET NUMBER 50-245 On March 22,1982, at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, while performing Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip / Alternate Rod Insertion Calibration Test, the setpoints for pressure transmitter PT 265A, 265B, 265C, 265D and level transmitters LT 266A and 266C were found to be above specification limits. The maximum deviation between the as-found setpoints and specification setpoints was 1.6%, occurring in pressure transmitter PT 265A.
Failure of the transmitters to trip at their desired setpoints was attributable to setpoint drift.
The ATWS system provides a redundant safety grade control system to the reactor protection system.
This system will trip the recirculation pumps and insert the control rods on high reactor pressure and/or lo reactor water level.
Failure of the transmitters did not result in a condition that had not been previously analyzed.
The reactor protection system was available and would had initiated the required action had an actual high reactor pressure /lo reactor level existed.
The transmitters were recalibrated to within their acceptable setpoint range and satisfactorily tested.
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