05000387/LER-2016-012, Regarding Secondary Containment Declared Inoperable Due to Loss of Differential Pressure as a Result of a Solenoid Valve

Regarding Secondary Containment Declared Inoperable Due to Loss of Differential Pressure as a Result of a Solenoid Valve

ML16147A075
Person / Time
Site:	Susquehanna
Issue date:	05/26/2016
From:	Franke J Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7478 LER 2016-012-00
Download: ML16147A075 (4)

LER-2016-012, Regarding Secondary Containment Declared Inoperable Due to Loss of Differential Pressure as a Result of a Solenoid Valve

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)
3872016012R00 - NRC Website

text

MAY 2 6 2015 Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon. Franke@TalenEnergy.com U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387(388)/2016-012-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF -22 PLA-7478 TALEN ~

ENERGY 10 CFR 50.73 Docket No. 50-387 50-388 Attached is Licensee Event Report (LER) 50-387(388)/2016-012-00. The LER repmis a loss of secondary containment differential pressure that occmred due to failure of a solenoid valve. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(C) as an event that could have prevented fulfillment of a safety function required to control the release of radioactive material.

There were no actual consequences to the health and safety of the public as a result of this event.

This letter contains no new regulatory commitments.

J. A. Franke Attachment: LER 50-387(388)/2016-012-00 Copy:

NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (1 1-2015)

"..yf..l.r4"~..

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

r* PAGE Susquehanna Steam Electric Station Unit 1 05000387 1 of 3

4. TITLE Secondary Containment declared inoperable due to loss of differential pressure as a result of a solenoid failure.

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED YEAR / SEQUENTIALJ REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

MONTH DAY YEAR Susquehanna Steam Electric Station Unit 2 05000388 05 ~to FACILITY NAME DOCKET NUMBER 03 29 2016 2016

- 012

- 00 2016 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 5 D 20.22o1(d}

0 20.2203(a)(3}(ii)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B)

D 20.2203(a)(1) 0 20.2203(a)(4)

D 50.73(a)(2)(iii)

D 50.73(a)(2)(ix)(A)

D 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a}(2}(v)(A) 0 73.71(a)(4) 000 D 20.2203(a)(2)(iii) 0 50.36(c)(2)

D 50.73(a}(2)(v)(B)

D 73.71(a}(5)

D 20.2203(a)(2)(iv) 0 50.46(a}(3}(ii)

~ 50.73(a}(2)(v)(C)

D 73.77(a)(1)

D 20.2203(a)(2)(v) 0 50.73(a}(2)(i)(A)

D 50.73(a)(2)(v)(D)

D 73.77(a)(2)(i) 0 20.2203(a)(2)(vi) 0 50.73(a}(2)(i)(B) 0 50.73(a)(2)(vii)

D 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 00THER Specify in Abstract below or in

ANALYSIS/SAFETY SIGNIFICANCE

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

2. DOCKET NUMBER

3. LER NUMBER YEAR I

SEQUENTIAL I REV NUMBER NO.

05000387 2016

- 012

- 00 Technical Specification 3.6.4.1 Surveillance Requirement 3.6.4.1.1 requires that secondary containment vacuum is maintained greater than or equal to 0.25 in. w.g. This event is being reported pursuant to 10 CFR 50.73(a)(2)(v)(C), as a loss of Secondary Containment differential pressure results in a condition that could have prevented fulfillment of a safety function to mitigate the consequences of an accident by controlling the release of radioactive material.

There was no actual safety consequence as a result of this event. Engineering analysis of this event has determined that secondary containment could have performed its safety function of isolating, as assumed in the accident analysis, and also of re-establishing 0.25 in. w.g. vacuum (drawdown) within the assumed accident analysis time ( 10 minutes). Therefore, the subject event did not cause a loss of safety function.

This event will not be counted as a safety system functional failure (SSFF) for the NRC performance indicator based on the Engineering analysis supporting the system's ability to fulfill the safety function.

CORRECTIVE ACTIONS

Corrective actions for this event include revision of the PM scope for Reactor Building HVAC solenoid valves and evaluation of a more robust solenoid valve for Reactor Building HVAC system.

COMPONENT INFORMATION Manufacturer:

Type:

Process Fluid:

Model:

Voltage:

ASCO Services 3-way electrical solenoid valve Air ASCO 8320 Solenoid Valve, General Use Model 8320G003 120 VAC

PREVIOUS SIMILAR EVENTS

Docket No. 50-387, PLA 7437, LER 2015-013-00 "Loss of Differential Pressure in Zone I of Secondary Containment Due to Solenoid Valve Failure." Dated February 2, 2016.

Docket No. 50-387, PLA 7329, LER 2015-002-00 "Secondary Containment lnoperability Due to Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1." Dated June 10, 2015.

NRC FORM 366 (11-2015)

MAY 2 6 2015 Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon. Franke@TalenEnergy.com U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387(388)/2016-012-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF -22 PLA-7478 TALEN ~

ENERGY 10 CFR 50.73 Docket No. 50-387 50-388 Attached is Licensee Event Report (LER) 50-387(388)/2016-012-00. The LER repmis a loss of secondary containment differential pressure that occmred due to failure of a solenoid valve. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(C) as an event that could have prevented fulfillment of a safety function required to control the release of radioactive material.

There were no actual consequences to the health and safety of the public as a result of this event.

This letter contains no new regulatory commitments.

J. A. Franke Attachment: LER 50-387(388)/2016-012-00 Copy:

NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (1 1-2015)

"..yf..l.r4"~..

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

r* PAGE Susquehanna Steam Electric Station Unit 1 05000387 1 of 3

4. TITLE Secondary Containment declared inoperable due to loss of differential pressure as a result of a solenoid failure.

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED YEAR / SEQUENTIALJ REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

MONTH DAY YEAR Susquehanna Steam Electric Station Unit 2 05000388 05 ~to FACILITY NAME DOCKET NUMBER 03 29 2016 2016

- 012

- 00 2016 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 5 D 20.22o1(d}

0 20.2203(a)(3}(ii)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B)

D 20.2203(a)(1) 0 20.2203(a)(4)

D 50.73(a)(2)(iii)

D 50.73(a)(2)(ix)(A)

D 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a}(2}(v)(A) 0 73.71(a)(4) 000 D 20.2203(a)(2)(iii) 0 50.36(c)(2)

D 50.73(a}(2)(v)(B)

D 73.71(a}(5)

D 20.2203(a)(2)(iv) 0 50.46(a}(3}(ii)

~ 50.73(a}(2)(v)(C)

D 73.77(a)(1)

D 20.2203(a)(2)(v) 0 50.73(a}(2)(i)(A)

D 50.73(a)(2)(v)(D)

D 73.77(a)(2)(i) 0 20.2203(a)(2)(vi) 0 50.73(a}(2)(i)(B) 0 50.73(a)(2)(vii)

D 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 00THER Specify in Abstract below or in

CONDITIONS PRIOR TO EVENT

Unit 1 - Mode 5, 0 percent Rated Thermal Power Unit 2 - Mode 1, 1 00 percent Rated Thermal Power

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

2. DOCKET NUMBER

3. LERNUMBER YEAR I

SEQUENTIAL I

REV NUMBER NO.

05000387 2016

- 012

- 00 There were no other structures, systems, or components that were inoperable at the start of the event that contributed to the event.

EVENT DESCRIPTION

On March 29, 2016 at approximately 2256 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.58408e-4 months <br />, SSES Unit 2 Zone II Secondary Containment [EllS System Code: VA] dP was not maintained above the TS SR required value of 0.25 in. w.g. as a result of the "B" Equipment Compartment Exhaust Fan Discharge Damper, HD27521 B, [EllS Component Code: DMP] closure and subsequent trip of the reactor building exhaust fan, 2V206B [EllS Component Code: FAN]. The Unit 1 and Unit 2 Secondary Containment systems were declared inoperable and Action Statement forTS 3.6.4.1 was entered. Secondary Containment dP was restored to greater than 0.25 in. w.g. at approximately 2321 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.831405e-4 months <br />, following the start of the "A" reactor building exhaust fan, 2V206A.

On March 30, 2016, at 0213 hours0.00247 days <br />0.0592 hours <br />3.521825e-4 weeks <br />8.10465e-5 months <br />, this condition was reported (ENS#51830) in accordance with 10 CFR 50.72(b)(3)(v)(C) for an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function. SSES has no redundant Secondary Containment System.

In accordance with 10 CFR 50.73(a)(2)(v)(C), this LER is being submitted for an event that could have prevented the fulfillment of the safety function of Secondary Containment to control the release of radioactive material.

CAUSE OF EVENT

The cause of the event was failure of solenoid valve, SV27521 B, [EllS Component Code: SOL] which controls the "B" Equipment Compartment Exhaust Fan Discharge Damper. The failed valve was disassembled, inspected, and found to be damaged. Failure analysis of the solenoid valve determined the issue to be related to vendor parts quality.

NRC FORM 366 (11-2015)

ANALYSIS/SAFETY SIGNIFICANCE

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

2. DOCKET NUMBER

3. LER NUMBER YEAR I

SEQUENTIAL I REV NUMBER NO.

05000387 2016

- 012

- 00 Technical Specification 3.6.4.1 Surveillance Requirement 3.6.4.1.1 requires that secondary containment vacuum is maintained greater than or equal to 0.25 in. w.g. This event is being reported pursuant to 10 CFR 50.73(a)(2)(v)(C), as a loss of Secondary Containment differential pressure results in a condition that could have prevented fulfillment of a safety function to mitigate the consequences of an accident by controlling the release of radioactive material.

There was no actual safety consequence as a result of this event. Engineering analysis of this event has determined that secondary containment could have performed its safety function of isolating, as assumed in the accident analysis, and also of re-establishing 0.25 in. w.g. vacuum (drawdown) within the assumed accident analysis time ( 10 minutes). Therefore, the subject event did not cause a loss of safety function.

This event will not be counted as a safety system functional failure (SSFF) for the NRC performance indicator based on the Engineering analysis supporting the system's ability to fulfill the safety function.

CORRECTIVE ACTIONS

Corrective actions for this event include revision of the PM scope for Reactor Building HVAC solenoid valves and evaluation of a more robust solenoid valve for Reactor Building HVAC system.

COMPONENT INFORMATION Manufacturer:

Type:

Process Fluid:

Model:

Voltage:

ASCO Services 3-way electrical solenoid valve Air ASCO 8320 Solenoid Valve, General Use Model 8320G003 120 VAC

PREVIOUS SIMILAR EVENTS

Docket No. 50-387, PLA 7437, LER 2015-013-00 "Loss of Differential Pressure in Zone I of Secondary Containment Due to Solenoid Valve Failure." Dated February 2, 2016.

Docket No. 50-387, PLA 7329, LER 2015-002-00 "Secondary Containment lnoperability Due to Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1." Dated June 10, 2015.

NRC FORM 366 (11-2015)