ML20154D585
| ML20154D585 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 09/06/1988 |
| From: | Haynes H, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| MP-12211, NUDOCS 8809150348 | |
| Download: ML20154D585 (2) | |
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(203) 665-5000 September 6, 1988 MP-12211 Docket No.: 50-423 U.S. Nuclear Reguintory Commission Document Control Desk Washington, D. C. 20555 Centlemen:
Insufficient Documentation Retrievable to Substantiate Compliance With NRC Rep,ulatory Guide 1.106 for Two Service Water Pump Discharge Valves Thermni Overload Devices This event is being submitted as a Special Report because no definitive report-ing requirements per the guidelines of 10CFR50.73 could be identified. However, this information is considered of sufficient interest to submit this Special Report as documentation of the event.
On August 4, 1988 at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> while operating in Mode 1 at 100% power, 585 degrees Fahrenheit and 2250 psia it was determined that the initial documenta-tion on record was insufficient to assure that two (2) of the four (4) Service Water pump discharge valves (specifically 3SWP*MOV102A and C) were in compliance with NRC Regulatory (Reg.) Guide 1.106.
The valves were required to have their thermal overload protection devices bypassed either continuously or under accident conditions or be sized with all uncertainties resolved in favor of completing the safety action.
Upon identification of the Service Water pump discharge valves potential non-compliance with Reg. Guide 1.106, the subject thermal overloads were irmedi-ately declared inoperabic and the appropriate Limiting Condition of Operation wel et.t e red.
The thermal overload protection devices were then continuously bypassed in accordance with position 1(a) of the Reg. Guide and the valves were returned to operabic status.
There were no adverse safety consequences resulting from this incident.
An Engineering calculation was perforre.] to verify that the trip setpoint of the thermal overload protection devices was established in favor of completing the safety related actions as specified in Reg. Cuide 1.106.
The root cause of this event is personnel error in that the calculation used to ensure compliance with the NRC Reg. Guide was not properly documented or retrievable.
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After the Engineering calcul.lon was performed to verify that the thermal overload protection devices selected for the Service Water pump discharge valves met the requirenents of the Reg. Guide, the bypasses vers removed.
Engineering personnel have performed a complete review of Technical Specifica-tion table 3.8-2a, "Motor Operated Valves Thermal Overload Protection Bypassed Only Under Accident Conditions", and table 3.8-2b, "Motor Operated Valves Thermal Overload Protection Not Bypassed" for similar discrepancies.
None were identified.
The licensee contact for this Special Report will be Lawrence E. Locais, who may be contacted at (203) 447-1791, ext. 5468 Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: Stephen E. Scace Station Superintendent Millstone Nuclear Power Station f
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Station ervices Super ntendent Millstone Nuclear Power Station SES/LEL:mo cc:
W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit Nos. 2 & 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, a 3