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UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, DC 20555-0001

January 21, 1998

**Addressees**

All holders of operating licenses for nuclear power reactors.

**Purpose**

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert addressees to potentialcommon-cause failure mechanisms of safety-related systems and systems important to safety caused by extremely coldweather. It is expected that recipients will review the information for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRCrequirements; therefore, no specific action or written response is required.

**Description of Circumstances**

Wolf Creek

IN 96-36, "Degradation of Cooling Water Systems Due to Icing," described the effects of icing on intake trash racks andtraveling screens which resulted in a manual reactor/turbine trip on January 30, 1996, at Wolf Creek. In addition to thedegradation of the circulating water and essential service water systems, the turbine-driven auxiliary feedwater pump wasdegraded during this event. The NRC identified the event as a precursor within the framework of the NRC's accidentsequence precursor program, and calculated a conditional core-damage probability of 2.1 x 10-4.

Circulating water system degradation was initially attributed to water from the spray-wash system freezing on the travelingscreens, making them inoperable. To improve the reliability of the circulating water system, the licensee revised plantprocedures (1) to eliminate the requirement to operate traveling screens continuously in slow manual mode during coldweather or under unusual icing conditions and (2) to allow the screens to be operated in the automatic mode in which thescreens remained stationary without sprays until the system was started either by a timer or a high differential level. Thetraveling screens were also enclosed in a heated environment.

After IN 96-36 was issued, more information became available about the degradation of the circulating water system.Specifically, on August 5, 1997, the licensee reported that during the event, two of three air release valves on thecirculating water warming line had been plugged.

Failure of these valves caused air binding in the piping and caused the warming flow to be nearly zero.

The effect of the resultant air binding was demonstrated during a 5-day test in January 1997 with 2.8 �C (37 �F) lake water,when warming line flow was reduced from 1388 liters per second (22,000 gpm) to approximately 347 liters per second(5,500 gpm). This warming flow degradation would have been more pronounced during the event because the temperatureof the lake water was approximately 0 �C (32 �F) during the event and, therefore, contained more air in solution. Althoughair removal by the water box venting system should have significantly reduced the potential for air binding, approximatelyone-half of the water box air release valves had been isolated during the January 1996 event.

In response to these findings, the three air release valves on the warming line were replaced and incorporated into thepreventive maintenance program. The licensee also revised procedures to ensure (1) manual venting of the circulatingwater warming line when the inlet temperature fell below 1.1 �C (34 �F), and (2) verification of the presence of circulatingwater warming flow and the passing of air from the air release valves when the warming line valve was opened in the fall.A procedural step was also added to verify that the water box air release valves were not isolated.

Millstone Unit 2

On January 8, 1996, with the plant at 100-percent power, an ice plug formed in a horizontal, common, service water (SW)strainer backwash drain line that ran through the intake wall in a trough toward a fish basket. This would have preventedautomatic backwash of the SW strainers. This pipe had been welded onto the end of the original vertical discharge leg in amodification that had not undergone a formal engineering review. Minor leakage through the strainer backwash isolationvalves and an unusually long period of subfreezing temperatures created the conditions needed to form the ice plug.Removal of the ice plug restored the SW strainer backwash capability and operators backwashed the strainers every 4 hoursto ensure that another ice plug would not form until the horizontal pipe was eliminated. Nonetheless, the open end of theline was still susceptible to ice buildup. The licensee later reported that the operators had failed to recognize that the iceplug that made the backwash functions of the SW strainers inoperable also made both SW system trains inoperable. Thelicensee should have declared the SW system inoperable during the event and entered Technical Specification LimitingCondition for Operation 3.0.3, which required a plant shutdown.

On February 29, 1996, the licensee reported that the SW strainer backwash system was also susceptible to a common-modefailure if the intake structure's nonvital heating system failed to operate. The licensee changed an operating procedure torequire (1) monitoring of the intake structure temperature when temperature fell below 4.4 C (40 F) and (2) usingportable space heaters or manual operation of the strainers to prevent freezing. The licensee also proposed replacing thecommon line with three independent backwash lines, locating the discharge points to minimize the effect of outdoorweather conditions, and protecting differential pressure instrumentation from freezing.

LaSalle Unit 2

On February 4, 1996, operators shut the plant down manually when the oil temperature in the main transformer could notbe maintained within design limits because of the loss of the transformer cooling fan and cooling pump. Ice severed thetransformer cooling logic cable in its conduit where it entered the underground cable trough. Licensee corrective actionsincluded inspecting other transformer conduits, clearing water and ice from conduits, and sealing the conduits.

McGuire Unit 2

On February 8, 1996, with the plant at 100 percent power, two of three refueling water storage tank (RWST) leveltransmitters were found to be inoperable because of frozen impulse lines. The lines froze because thermostat setpoints forthe strip heaters were set too low for cold weather conditions. The frozen impulse lines affected control room RWST levelindication and the ability to automatically switch to the emergency core cooling system sump. To correct this problem, thelicensee increased the thermostat setpoint and added inspection of the level transmitter panels to its cold weather preventivemaintenance procedure.

**Discussion**

The January 1996 event at Wolf Creek, described above, led the NRC Office for the Analysis and Evaluation ofOperational Data (AEOD) to review the extent of cold weather-related problems at U.S. nuclear power plants over the past6 years. The results of this study are given in Engineering Evaluation Report AEOD/E97-03, "Nuclear Power Plant ColdWeather Problems and Protective Measures." It contains a compendium of recent cold weather-related events andcorrective actions, as well as design, operations, and training lessons learned by the nuclear industry and the U.S. ArmyCorps of Engineers Cold Regions Research and Engineering Laboratory. The report noted 37 cold weather related events at23 different sites between 1991 and 1997. The study also reported an increasing trend in the number of these events.

Licensees continue to find that icing and freezing from extreme cold weather conditions is a common-cause failuremechanism that can quickly affect a variety of systems unless mitigating actions are taken in a timely manner. The recentoperating experience described in this study suggests that, despite NRC and industry communications on this subject, somelicensees have not effectively protected components whose failure could degrade safety-related systems and systemsimportant to safety. Extreme cold weather conditions continued to affect intake structures; process lines; instrument lines;emergency diesel generator oil and grease viscosities; essential chillers; electrical systems; and heating, ventilation, and airconditioning systems. Lack of design oversight, incomplete review of operating experience, and insufficient attention tocold weather preparations were responsible for most of the events.

This information notice requires no specific action or written response. However, recipients are reminded that they arerequired by 10 CFR 50.65 to take industry-wide operating experience (including information presented in NRC informationnotices) into consideration, where practical, when setting goals and performing periodic evaluations. If you have anyquestions about the information in this notice, please contact one of the technical contacts listed below or the appropriateOffice of Nuclear Reactor Regulation project manager.

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