05000266/LER-2017-002

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LER-2017-002, Operation or Condition Prohibited by Technica Specifications
Point Beach Nuclear Plant Unit 1
Event date: 10-29-2017
Report date: 12-13-2017
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2662017002R00 - NRC Website
LER 17-002-00 for Point Beach Nuclear Plant, Unit 1, Regarding Operation or Condition Prohibited by Technical Specifications
ML17347A770
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 12/13/2017
From: Coffey R
Point Beach
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17347A768 List:
References
NRC 2017-0053
Download: ML17347A770 (4)


comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1 FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER 2017 002 00

Description of the Event:

At 1302 on October 29, 2017, Unit 1 entered MODE 3 from MODE 4 without satisfying all of Technical Specification 3.7.5, Auxiliary Feedwater (AFW) Limiting Conditions for Operation (LCO) as required by LCO Applicability 3.0.4.

LCO Applicability 3.0.4 does not permit entry into a MODE of applicability when an LCO is not met, unless the associated actions to be entered permit continued operation in the MODE for an unlimited time or after performance of an acceptable risk assessment and the appropriate risk management actions have been established.

At approximately 1500 on October 29, 2019 after entering MODE 3, it was discovered that components were not operable as required by Technical Specification LCO 3.7.5 to permit entry into MODE 3 per LCO 3.0.4. At 1610 on October 29, 2017 the affected steam supply valves [ISV][BA] to the TDAFW pump [P][BA] were opened, operability was restored and LCO 3.7.5 was met.

This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B), for an operation or condition prohibited by Technical Specifications.

Cause of the Event:

The cause of the operation or condition prohibited by Technical Specifications was less than adequate process interface controls (clearance orders and procedures) to ensure required equipment operability.

Analysis of the Event:

The AFW System consists of one full-capacity motor driven auxiliary feedwater (MDAFW) pump system and one full- capacity TDAFW pump system for each unit that ensures adequate feedwater is supplied to the steam generators for heat removal under all circumstances, including loss of offsite power and normal heat sink. During reactor startup activities after a planned refueling, the steam supply isolation valves to the TDAFW pump were not realigned after refueling maintenance activities due to an identified condition on the steam supply line requiring additional maintenance activities. The less than adequate process controls of the isolation components under the clearance order and operating procedure processes allowed the transition to MODE 3 from MODE 4 without having the TDAFW pump operable as required by LCO Applicability 3.0.4.

Corrective Actions:

The TDAFW steam valves were positioned to the required position for the MODE of operation. Corrective actions have been created to improve the process interface controls to ensure adequate implementation of Technical Specification, and are being tracked in the corrective action program.

Safety Significance:

The event was determined to be of very low safety significance. There is a low probability of an event occurring while the TDAFW pump steam supply valves were not operable. The reactor had been shutdown for several weeks completing refueling operations resulting in a relatively low reactor coolant system decay and residual heat capacity.

While the condition was present, the MDAFW pump was operable with the balance of the engineered safety feature systems, structures or components needed to shut down the reactor, maintain safe shutdown conditions, remove residual heat, control the release of radioactive material or mitigate the consequences of an accident were operable.

Additionally, the standby steam generator (SSG) feedwater pumps were available by manual operator action at the main control boards and local control panels. There was no impact on the health and safety of the public as a result of this condition.

comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

(0) 00 002 2017 Similar Events:

corrective actions of this LER are not the same as this event.

Component Failure Data:

None Point Beach Nuclear Plant Unit 1 05000266