05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value

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Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value
ML15306A446
Person / Time
Site: Dresden Constellation icon.png
Issue date: 10/29/2015
From: Marik S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
15-0060 LER 15-001-00
Download: ML15306A446 (4)


LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

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)(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)(v), Loss of Safety Function
2492015001R00 - NRC Website

text

f Dresden Generating Station Exe!.oI n Generation° 6500 North Dresden Road Il Morris, IL 60450 www.exeloncorp.com 10 CFR 50.73 SVPLTR # 15-0060 October 29, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Licensee Event Report 249/2015-001-00, Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value Enclosed is Licensee Event Report 249/2015-001-00, "Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value." This is an interim report which describes events which are being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), "any operation or condition which was prohibited by the plant's Technical Specifications".

There are no regulatory commitments contained in this submittal..*

Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.

Respectfully, Shane M. Marik Site Vice President Dresden Nuclear Power Station Enclosure Licensee Event Report 249/20 15-00 1-00 cc:

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

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/311201:

I02-014),*

,,*,,*Estimated

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

/3. PAGE Dresden Nuclear Power Station, Unit 3 05000249]1O 3

4. TITLE Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MONH DAY YER YEAR NUMBEAR NO.

MONTH DAY YEAR FALTYNMDCETUBR FACILITY NAME DOCKET NUMBER 001-o

- 00I 10 29 1
9. OPERATING MODlE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

El 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(c)

El 50.73(a)(2)(vii) 1 E 20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

El 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

LI 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

El 50.73(as)(2)(iv)(A)

El 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71 (a)(4) 10 E 20,2203(a)(2)(iv)

El 50,46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71 (a)(5)

El 20,2203(a)(2)(v)

El 50,73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

[]

50.73(a)(2)(i)(B)

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

Specify in Abstract below or in

______________NR_____oNRCForm66A

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT ITELEFHONE NUMBER (Include Area Code)

Bruce Franzen - Regulatory Assurance Manager J815-416-2800CAS YTM CMOET FACTURER TO EPIX FACTURER TO EPIX X

SB FIS 1024 Y

~P N

N

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DA Y YEAR SUBMISSION

[] YES (If yes, Complete 15. EXPECTED SUBMISSION DATE)

El NO DATE 0

18 16 ABSTRACT (Limit to 1400 spaces, iLe., approximately 15 single-spaced typewritten lines)

During quarterly calibration and functional testing of Main Steam (SB) Line High Flow switches, two switches were found to not meet surveillance requirements of Technical Specification 3.3.6.1.

At 1100 CDT on September 5, 2015, a switch was found to not meet Surveillance Requirement (SR) 3.3.6.1.1. TS 3.3.6.1 Condition A and D completion times were not met and TS 3.0.2 was entered.

Maintenance personnel repaired the affected instrument. No loss of safety function occurred due to this failure.

These events are being reported under 10 CFR 50.73(a)(2)(i)(B) "Any operation or condition which was prohibited by the plant's Technical Specifications...". No loss of safety function occurred due to these events.

The cause of these issues is under investigation. Immediate corrective actions include replacement of the failed components and remediation of the team which failed to identify the Tech Spec condition. These events are considered of very low safety significance.

NRC FORM 366 (02-201 4)

PLANT AND SYSTEM IDENTIFICATION

Dresden Nuclear Power Station (DN PS), Unit 3, is a General Electric Company Boiling Water Reactor with a licensed maximum power level of 2957 megawatts thermal. The Energy Industry Identification System codes used in the text are identified as [XX].

A.

Plant Conditions Prior to Event:

Unit: 03 Reactor Mode: 1 Event Date: 09/05/15 to 09/11/15 Mode Name: Power Operation Event Time: 1100 CDT Power Level: 100 percent B.

Description of Event

During quarterly calibration and functional testing of Main Steam [SB] Line High Flow switches, two switches were found to not meet surveillance requirements of Technical Specification 3.3.6.1. This event is being reported under 10 CFR 50.73(a)(2)(i)(B) "Operation or Condition Prohibited by Technical Specifications" due to multiple test failures of similar components.

Additionally, at approximately 1100 CDT on September 5, 2015, Operations logged the failure of a switch to meet SR 3.3.6.1.1 channel check criteria. September 7, 2015, TS 3.3.6.1 Condition A and D completion times had not been met and Tech Spec 3.0.2 was entered. Maintenance personnel repaired the affected instrument. This event is being reported under 10 CFR 50.73(a)(2)(i)(B) "Any operation or condition which was prohibited by the plant's Technical Specifications...".

No individual failure caused a loss of safety function. The aggregate impact of these events did not result in the loss of safety function.

C.

Cause of Event

The cause of these issues is under investigation.

NRC FORM 365A (02-2014)

D.

Safety Analysis

The automatic isolation closure of the main steam line isolation valves was maintained due to system redundancy. No loss of safety function occurred, therefore these failures are considered of very low safety significance. Further safety analysis will be completed by the investigation.

E.

Corrective Actions

Immediate corrective actions included replacement of the failed components and remediation of the Operations team which failed to identify the Tech Spec condition. Further corrective actions will be determined through the open investigation.

F.

Previous Occurrences

A review of the previous 12 quarterly surveillances, three years, was performed. No previous occurrences were identified. Further occurrences will be determined through the corrective action program.

G.

Component Failure Data

Manufacturer Model SIN Type 1'

1 Meter Movement ITT Barton 288A and 289A TBD for Differential I_

_ pressure switch NRC FORM S66A (02-2014)

f Dresden Generating Station Exe!.oI n Generation° 6500 North Dresden Road Il Morris, IL 60450 www.exeloncorp.com 10 CFR 50.73 SVPLTR # 15-0060 October 29, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Licensee Event Report 249/2015-001-00, Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value Enclosed is Licensee Event Report 249/2015-001-00, "Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value." This is an interim report which describes events which are being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), "any operation or condition which was prohibited by the plant's Technical Specifications".

There are no regulatory commitments contained in this submittal..*

Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.

Respectfully, Shane M. Marik Site Vice President Dresden Nuclear Power Station Enclosure Licensee Event Report 249/20 15-00 1-00 cc:

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

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/311201:

I02-014),*

,,*,,*Estimated

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

/3. PAGE Dresden Nuclear Power Station, Unit 3 05000249]1O 3

4. TITLE Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MONH DAY YER YEAR NUMBEAR NO.

MONTH DAY YEAR FALTYNMDCETUBR FACILITY NAME DOCKET NUMBER 001-o

- 00I 10 29 1
9. OPERATING MODlE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

El 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(c)

El 50.73(a)(2)(vii) 1 E 20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

El 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

LI 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

El 50.73(as)(2)(iv)(A)

El 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71 (a)(4) 10 E 20,2203(a)(2)(iv)

El 50,46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71 (a)(5)

El 20,2203(a)(2)(v)

El 50,73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

[]

50.73(a)(2)(i)(B)

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

Specify in Abstract below or in

______________NR_____oNRCForm66A

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT ITELEFHONE NUMBER (Include Area Code)

Bruce Franzen - Regulatory Assurance Manager J815-416-2800CAS YTM CMOET FACTURER TO EPIX FACTURER TO EPIX X

SB FIS 1024 Y

~P N

N

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DA Y YEAR SUBMISSION

[] YES (If yes, Complete 15. EXPECTED SUBMISSION DATE)

El NO DATE 0

18 16 ABSTRACT (Limit to 1400 spaces, iLe., approximately 15 single-spaced typewritten lines)

During quarterly calibration and functional testing of Main Steam (SB) Line High Flow switches, two switches were found to not meet surveillance requirements of Technical Specification 3.3.6.1.

At 1100 CDT on September 5, 2015, a switch was found to not meet Surveillance Requirement (SR) 3.3.6.1.1. TS 3.3.6.1 Condition A and D completion times were not met and TS 3.0.2 was entered.

Maintenance personnel repaired the affected instrument. No loss of safety function occurred due to this failure.

These events are being reported under 10 CFR 50.73(a)(2)(i)(B) "Any operation or condition which was prohibited by the plant's Technical Specifications...". No loss of safety function occurred due to these events.

The cause of these issues is under investigation. Immediate corrective actions include replacement of the failed components and remediation of the team which failed to identify the Tech Spec condition. These events are considered of very low safety significance.

NRC FORM 366 (02-201 4)

PLANT AND SYSTEM IDENTIFICATION

Dresden Nuclear Power Station (DN PS), Unit 3, is a General Electric Company Boiling Water Reactor with a licensed maximum power level of 2957 megawatts thermal. The Energy Industry Identification System codes used in the text are identified as [XX].

A.

Plant Conditions Prior to Event:

Unit: 03 Reactor Mode: 1 Event Date: 09/05/15 to 09/11/15 Mode Name: Power Operation Event Time: 1100 CDT Power Level: 100 percent B.

Description of Event

During quarterly calibration and functional testing of Main Steam [SB] Line High Flow switches, two switches were found to not meet surveillance requirements of Technical Specification 3.3.6.1. This event is being reported under 10 CFR 50.73(a)(2)(i)(B) "Operation or Condition Prohibited by Technical Specifications" due to multiple test failures of similar components.

Additionally, at approximately 1100 CDT on September 5, 2015, Operations logged the failure of a switch to meet SR 3.3.6.1.1 channel check criteria. September 7, 2015, TS 3.3.6.1 Condition A and D completion times had not been met and Tech Spec 3.0.2 was entered. Maintenance personnel repaired the affected instrument. This event is being reported under 10 CFR 50.73(a)(2)(i)(B) "Any operation or condition which was prohibited by the plant's Technical Specifications...".

No individual failure caused a loss of safety function. The aggregate impact of these events did not result in the loss of safety function.

C.

Cause of Event

The cause of these issues is under investigation.

NRC FORM 365A (02-2014)

D.

Safety Analysis

The automatic isolation closure of the main steam line isolation valves was maintained due to system redundancy. No loss of safety function occurred, therefore these failures are considered of very low safety significance. Further safety analysis will be completed by the investigation.

E.

Corrective Actions

Immediate corrective actions included replacement of the failed components and remediation of the Operations team which failed to identify the Tech Spec condition. Further corrective actions will be determined through the open investigation.

F.

Previous Occurrences

A review of the previous 12 quarterly surveillances, three years, was performed. No previous occurrences were identified. Further occurrences will be determined through the corrective action program.

G.

Component Failure Data

Manufacturer Model SIN Type 1'

1 Meter Movement ITT Barton 288A and 289A TBD for Differential I_

_ pressure switch NRC FORM S66A (02-2014)