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LER-2015-010, Regarding Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure
Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function; 10 CFR 50.73(a)(2)(i); 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability; 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded; 10 CFR 50.73(a)(2)(viii)(A); 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition; 10 CFR 50.73(a)(2)(viii)(B); 10 CFR 50.73(a)(2)(iii); 10 CFR 50.73(a)(2)(ix)(A); 10 CFR 50.73(a)(2)(iv)(A), System Actuation; 10 CFR 50.73(a)(2)(x); 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor; 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat; 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
	2542015010R00 - NRC Website
	v • d • e

Regarding Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure
	ML16053A068
Person / Time
Site:	Quad Cities
Issue date:	02/05/2016
From:	Darin S; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVP-16-005 LER 15-010-00
	Download: ML16053A068 (5)
	v • d • e

~Exeton Generation SVP-1 6-005 10 CFR 50.73 February 5, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Licensee Event Report (LER) 254/2015-010-00, "Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure" Enclosed is Licensee Event Report (LER) 254/2015-010-00, "Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure," for Quad Cities Nuclear Power Station, Unit 1.

This report is submitted in accordance with 10 CFR 50.73 (a)(2)(v)(D) which requires the reporting of any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

There are no regulatory commitments contained in this letter.

Should you have any questions concerning this report, please contact Mr. W. J. Beck at (309) 227-2800.

Respecfully, M Scott D a/n)

Site Vic* President Quad Cities Nuclear Power Station cc:

Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station

NRC FORM 368 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 01131/2017 (02-2014)

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

13. PAGE Quad Cities Nuclear Power Station Unit 1 05000254 1 OF 4

4. TITLE Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED YER NUMBER NO.

MONTH DAY YEAR Quad Cities Nuclear Power Station Unit 2 05000265 TFACILITY NAME DOCKET NUMBER 12j 0O 201 2015 -

010

- 001 02 I

5 01 N/A N/A

9. OPERATING MODE 11, THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) o] 20.2201(b)

[] 20.2203(a)(3)(i)

[] 50.73(a)(2)(i)(C) 0] 50.73(a)(2)(vii) o] 20.2201(d) 0] 20.2203(a)(3)(ii) 0] 50.73(a)(2)(ii)(A) 0] 50.73(a)(2)(viii)(A) o] 20.2203(a)(1) 0] 20.2203(a)(4) 0] 50.73(a)(2)(ii)(B) 0] 50.73(a)(2)(viii)(B) o] 20.2203(a)(2)(i) 0] 50.36(c)(1 )(i)(A) 0] 50.73(a)(2)(iii) 0] 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0] 20.2203(a)(2)(ii) 0] 50.36(c)(1)(ii)(A) 0] 50.73(a)(2)(iv)(A)

Q] 50.73(a)(2)(x) o] 20.2203(a)(2)(iii) 0] 50.36(c)(2) 0] 50.73(a)(2)(v)(A) 0] 73.71 (a)(4) o] 20.2203(a)(2)(iv) 0] 50.46(a)(3)(ii) 0] 50.73(a)(2)(v)(B) 0] 73.71 (a)(5) 100 o] 20.2203(a)(2)(v) 0] 50.73(a)(2)(i)(A) 0] 50.73(a)(2)(v)(C) 0] OTHER

[]

2.223(a(2)vi)[]

5.73a)()(i(B)[]

5.73a)()(v(D)Specify in Abstract below or in O

20220(e)2)(v) 050.3(a(2)()(B

~

0.73a)()(v(D)

D.

SAFETY ANALYSIS

System Design

Habitability systems are provided to ensure that control room operators are able to remain in the Main Control Room (MCR) [NA] and operate the plant safely under normal conditions and to maintain the plant in a safe condition under accident conditions. The worst-case design basis accident (DBA) for habitability considerations is postulated as a loss of coolant accident (LOCA) with main steam [SB] isolation valve [ISV] leakage at TS limits.

Per Updated Final Safety Analysis Report (UFSAR) Section 6.4.2, the Control Room HVAC systems are capable of maintaining the control room atmosphere suitable for occupancy throughout the duration of a OBA.

The HVAC systems are capable of both automatic and manual transfer from the normal operating mode to the isolation mode.

Transfer of the Control Room HVAC systems to the emergency (pressurization) mode of operation is not a fully automatic operation, since some Control Room HVAC system components must be manually started to operate the Control Room HVAC systems in the emergency (pressurization) mode. The manual actions required when placing the Control Room HVAC system into the pressurization mode following an accident include: (1) starting the refrigeration compressor unit; and (2) starting one Air Filtration Unit (AFU) booster fan.

Per UFSAR Section 6.4.2.1, the Control Room Emergency Zone (Control Room Envelope) is defined as the following areas: the main control room, the cable spreading room, the auxiliary electrical equipment room, which surrounds the old computer room; and the Train "B" HVAC equipment room.

The Control Room Envelope boundary is the combination of walls, floor, roof, ducting, doors, penetrations and equipment that physically form the Control Room Envelope. The operability of the Control Room Envelope boundary must be maintained to ensure that the in-leakage of unfiltered air into the Control Room Envelope will not exceed the in-leakage assumed in the DBA analysis for the main control room occupants.

UFSAR Section 6.4.2.4 provides that potential adverse interactions between the Control Room Emergency Zone and adjacent zones that may allow the transfer of toxic or radioactive gases into the control room are minimized by maintaining the control room at a slightly positive pressure with respect to adjacent areas during normal conditions.

Safety Impact The primary purpose of the CREV train "B" system is to provide a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals or smoke.

The CREV function was restored when the differential pressure switch was replaced and the CREV system ran when called upon. Since the differential pressure switch had failed and one of its functions is to allow the CREV train "B" system to operate, a safety system functional failure occurred.

Per TS Bases 3.7.4, the CREV train "B" system is considered operable when the train "B" air handling unit is operable along with the AFU and the outside air ventilation intake. Since the train "B" Control Room HVAC system would not start, the system was inoperable and TS 3.7.4 Condition A was entered.

Per TS Bases 3.7.5, the CREV AC system is considered operable when the individual components necessary to maintain the Control Room Emergency Zone temperature are operable. The CREV train "B" air handling unit is necessary to deliver the conditioned air to the Control Room Emergency Zone. Since the train "B" CREV system would not start to all the condition air to be delivered, the CREV AC system was inoperable and TS 3.7.5 Condition A was entered.

m

Risk Insights The plant Probabilistic Risk Assessment (PRA) model gives no credit to the Control Room Envelope (CRE) and does not include it in the model; hence, the CREV train "B" Fan failing to operate did not contribute to an increase in risk.

In conclusion, the overall safety significance and impact on risk of this event were minimal.

E.

CORRECTIVE ACTIONS

Immediate:

The differential pressure switch was replaced.

Follow-up:

The differential pressure switch will be relocated to a non-vibration susceptible area. The failed switch had been in service for 5 years with no issues prior to the failure.

F.

PREVIOUS OCCURRENCES

The station events database, LERs, and INPO Consolidated Event System (ICES) were reviewed for similar events at the Quad Cities Nuclear Power Station. This event was attributed to incorrect installation location of the differential pressure switch. Based on the cause of this event and the associated corrective actions, the events listed below, although similar in topic, are not considered significant station experiences that would have directly contributed to preventing this event.

Station Issue Report (IR) 01067025, "0-9400-1 05 A-3 Invalid Alarm AFU Post HEPA Filter OP Hi," (05/08/201 0)

- the local panel for the B Train of Control Room HVAC had tile A-3 lit on panel 0-9400-1 05 for "AFU Post HEPA Filter OP Hi." The alarm was present when the B Train of Control Room HVAC was not running and differential pressure indication switch DPIS 0-5795-311 was reading 0 inches of water column. The cause of the alarm was a degraded differential pressure indication switch, which was replaced.

This previous event, although similar to this LER event was caused by a different failure mode. Both switches were manufactured by the same vendor, but DPIS 0-5795-311 was installed at a location free from excessive vibrations. This is not considered a significant station experience that would have directly contributed to preventing the event of this current LER based on the different failure modes.

LER 254/2007-003-00, 01/18/08, Safety Function Not Met Due to Control Room Emergency Ventilation System Air Filtration Unit Heater Flow Switch Failure (11/20/07) - Operation's surveillances determined that the CREV Air Filtration Unit (AFU) heaters were not operating as required. Troubleshooting of the AFU heater found that a flow switch had an open contact that was preventing the heater from energizing as required. The previous event was caused by infant mortality of the flow switch, whereas this current LER was caused by improper mounting location of the differential pressure switch.

G.

COMPONENT FAILURE DATA

Failed Equipment: Control Room HVAC Differential Pressure Switch (DPS 0-5795-50)

Component Manufacturer: Dwyer Instrument Inc.

Component Model Number: 191 0-1 Component Part Number': N/A This event has been reported to ICES as Failure Report No. 320582 NIRC

PLANT AND SYSTEM IDENTIFICATION

General Electric - Boiling Water Reactor, 2957 Megawatts Thermal Rated Core Power Energy Industry Identification System (EllS) codes are identified in the text as [XX].

EVENT IDENTIFICATION The Control Room Emergency Ventilation (CREV) system failed to start due to a failed differential pressure switch.

A.

CONDITION PRIOR TO EVENT

Unit: 1 / 2 Event Date: December 7, 2015 Event Time: 0825 hours0.00955 days 0.229 hours 0.00136 weeks 3.139125e-4 months Reactor Mode: 1 / 1 Mode Name: Power Operation / Power Operation Power Level: 100%/i 100%

B.

DESCRIPTION OF EVENT

On December 7, 2015, at 0825 hours0.00955 days 0.229 hours 0.00136 weeks 3.139125e-4 months , Operations attempted to start the safety related Control Room Emergency Ventilation (CREV) [VI] system train "B" in support of planned maintenance on the non-safety related train "A". The CREV train "B" did not start. Once the CREV train "B" system failed to start, the non-safety related train "A" was restarted. Proper operation of the CREV train "B" system and CREV train "B" air conditioning (A/C) system could not be ensured, so both CREV and CREV AC system were declared inoperable.

As a result, Technical Specification 3.7.4, Condition A, and Technical Specification 3.7.5, Condition A were entered.

On December 7, 2015, at 1402 hours0.0162 days 0.389 hours 0.00232 weeks 5.33461e-4 months , ENS#51589 was made to the NRC under 10 CFR 50.72(b)(3)(v)(D) to report this event as an event or condition that could have prevented the fulfillment of the safety function.

Operations restarted the Train "A" Control Room HVAC system and began troubleshooting.

Differential Pressure Switch [PDS] 0-5795-50 and Relay [RLY] 0-9400-1 05-CR51SO were replaced and sent to Powerlabs for further analysis. On December 8, 2015, at 2201 hours0.0255 days 0.611 hours 0.00364 weeks 8.374805e-4 months , Operations successfully completed the Post Maintenance Testing on the CREV and CREV AC Systems and exited TS 3.7.4, Condition A and TS 3.7.5 Condition A.

Given the impact on the CREV system, which is common to both Units, this report is submitted (for Units 1 and 2) in accordance with the requirements of 10 CFR 50.73 (a)(2)(v)(D), which requires the reporting of any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

C..

CAUSE OF EVENT

The apparent cause for the CREV train "B" system failure to start was identified as the differential pressure switch, which is installed on a vibration susceptible location of the ductwork [DUCT]. This differential pressure switch makes up the interlock between the CREV train "B" system and the non-safety related Control Room HVAC train "A". The differential pressure switch was susceptible to vibrations and was installed on the air handling unit ductwork. These vibrations caused the differential pressure switch's normally open contacts to temporarily weld together, which did not allow the CREV train "B" system to automatically start or manually start either locally or remotely.