05000311/LER-2015-003, Regarding Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure
| ML16027A132 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/22/2016 |
| From: | Jamila Perry Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N16-0009 LER 15-003-00 | |
| Download: ML16027A132 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 3112015003R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 JAN IJ 2016 LR-N16-0009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 PSEG Nurlmr IJ,C 10 CFR 50.73
Subject:
Licensee Event Report 311/2015-003-000, "Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure" In accordance with the requirements of 1 O CFR 50. 73(a)(2)(v)(D), PSEG Nuclear LLC is submitting the enclosed Licensee Event Report (LER) 2015-003-000, "Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure."
If you have any questions or require additional information, please contact Mr. Thomas Cachaza at 856-339-5038.
There are no regulatory commitments contained in this letter.
Sincerely, qrier:
JohnF.Perry r Site Vice President Salem Generating Station Attachment: Licensee Event Report 311/2015-003-000
Page 2 10 CFR 50.73 LR-N 16-0009 cc Mr. D. Dorman, Administrator - Region 1, NRC Ms. C. Sanders, Licensing Project Manager - Salem, NRC Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24)
Mr. P. Mulligan, Manager IV, NJBNE Mr. R. Braun, President and Chief Nuclear Officer - Nuclear Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator
NRC FORM 366 U.S. NUCLEPR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FPCILITY NJWIE
- 2. DOCKET NUMBER
- 3. P/GE Salem Generating Station - Unit 2 05000311 1 OF 3
- 4. TITLE Both Trains of High Head Safety lnjedion Inoperable Due to a Relief Valve Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FPCILITIES INVOLVED I
SEQUENTIAL I REV FACILJTYNAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACIUTY NAME DOCKET NUMBER 11 23 2015 2015 -
003
- - 000 01 22 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)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50. 73(a)(2)(viii)(A) 3 D 20.2201(d)
D 20.2203(a)(3)(ii) n 50. 73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
- 10. POWER LEVEL 0%
D 20.2203(a)(1)
D 20.2203(a)(2)(i)
D 20.2203(a)(2)(ii)
D 20.2203(a)(2)(iii)
D 20.2203(a)(2)(iv)
D 20.2203(a)(2)(v)
D 20.2203(a)(2)(vi)
- 12. I II D 20.2203(a)(4)
D 5o.73(a)(2)(iii)
D 50. 73(a)(2)(ix)(A)
D 50.36(c)(1 )(i)(A)
D 50. 73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
D 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11(a)(4)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 13.77(a)(1)
D 50. 73(a)(2)(i)(A)
- 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
DoTHER Specify in Abstract below or in
CAUSE OF EVENT
APPROVED BY OMB: NO. 3150-0104 01/31/2018 EXPIRES:
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 6. LER NUMBER YEAR I
SEQUENTIAL I REVISION NUMBER NUMBER 2015
- - 003
- - 000
- 3. PAGE 3 OF 3 A cause evaluation is in progress and will be reported in a supplement to this LER.
SAFETY CONSEQUENCES AND IMPLICATIONS
This event did not result in a release of radioactivity or an increase of offsite dose rates, and there were no personnel injured or damage to any other safety related equipment. The excessive unidentified leakage was quickly terminated. TS 3.0.3 was entered and the plant was placed in Mode 5, Cold Shutdown. A further review of the safety consequences will be performed after the cause analysis is completed.
SAFETY SYSTEM FUNCTIONAL FAILURE A review for Safety System Functional Failure (SSFF) as defined in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines, will be performed after the cause analysis is complete.
PREVIOUS OCCURRENCES
A review of Salem Unit 1 and 2 Licensee Event Reports for the previous three years identified a similar event requiring entry into TS 3.0.3 when both trains of intermediate head ECCS were rendered inoperable. That event was reported in LER 272/2014-005 Technical Specification 3.0.3 Entry; Two ECCS Subsystems Inoperable," dated August 27, 2014.
CORRECTIVE ACTIONS
- 1) The 2SJ10 relief valve was replaced and retested with no identified leakage.
- 2) A cause evaluation is in progress. Additional corrective actions will be determined upon completion of the evaluation.
COMMITMENTS
There are no regulatory commitments contained in this LER.
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 JAN IJ 2016 LR-N16-0009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 PSEG Nurlmr IJ,C 10 CFR 50.73
Subject:
Licensee Event Report 311/2015-003-000, "Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure" In accordance with the requirements of 1 O CFR 50. 73(a)(2)(v)(D), PSEG Nuclear LLC is submitting the enclosed Licensee Event Report (LER) 2015-003-000, "Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure."
If you have any questions or require additional information, please contact Mr. Thomas Cachaza at 856-339-5038.
There are no regulatory commitments contained in this letter.
Sincerely, qrier:
JohnF.Perry r Site Vice President Salem Generating Station Attachment: Licensee Event Report 311/2015-003-000
Page 2 10 CFR 50.73 LR-N 16-0009 cc Mr. D. Dorman, Administrator - Region 1, NRC Ms. C. Sanders, Licensing Project Manager - Salem, NRC Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24)
Mr. P. Mulligan, Manager IV, NJBNE Mr. R. Braun, President and Chief Nuclear Officer - Nuclear Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator
NRC FORM 366 U.S. NUCLEPR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FPCILITY NJWIE
- 2. DOCKET NUMBER
- 3. P/GE Salem Generating Station - Unit 2 05000311 1 OF 3
- 4. TITLE Both Trains of High Head Safety lnjedion Inoperable Due to a Relief Valve Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FPCILITIES INVOLVED I
SEQUENTIAL I REV FACILJTYNAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACIUTY NAME DOCKET NUMBER 11 23 2015 2015 -
003
- - 000 01 22 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)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50. 73(a)(2)(viii)(A) 3 D 20.2201(d)
D 20.2203(a)(3)(ii) n 50. 73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
- 10. POWER LEVEL 0%
D 20.2203(a)(1)
D 20.2203(a)(2)(i)
D 20.2203(a)(2)(ii)
D 20.2203(a)(2)(iii)
D 20.2203(a)(2)(iv)
D 20.2203(a)(2)(v)
D 20.2203(a)(2)(vi)
- 12. I II D 20.2203(a)(4)
D 5o.73(a)(2)(iii)
D 50. 73(a)(2)(ix)(A)
D 50.36(c)(1 )(i)(A)
D 50. 73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
D 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11(a)(4)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 13.77(a)(1)
D 50. 73(a)(2)(i)(A)
- 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
DoTHER Specify in Abstract below or in
PLANT AND SYSTEM IDENTIFICATION
Westinghouse - Pressurized Water Reactor {PWR/4}
Emergency Core Cooling System I Relief Valve {BQ/RV}
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2018
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 6. LERNUMBER YEAR I
SEQUENTIAL I REVISION NUMBER NUMBER 2015
- - 003
- - 000
- 3. PAGE 2 OF 3
- Energy Industry Identification System (EllS) codes and component function identifier codes appear as
{SS/CCC}.
IDENTIFICATION OF OCCURRENCE Event Date: November 23, 2015 Discovery Date: November 23, 2015 CONDITIONS PRIOR TO OCCURRENCE Salem Unit 2 was in operational Mode 3, the RCS was at normal operating temperature and pressure.
No additional structures, systems or components were inoperable at the time of the event that contributed to this event.
DESCRIPTION OF OCCURRENCE At 2136 on November 23, 2015, the Boron Injection Tank (BIT) relief valve 2SJ10 lifted during the performance of troubleshooting to determine the cause of low BIT pressure. The lifting of 2SJ10 initiated a Reactor Coolant System (RCS) leak greater than 10 gallons per minute (gpm). Technical Specification (TS) 3.4.7.2.b action b was entered for RCS unidentified leakage greater than 1 gpm.
The BIT was isolated at 2137 and the leakage was stopped. Excessive leakage through 2SJ10 rendered both trains of high head safety injection inoperable, requiring entry into TS 3.0.3.
On November 24, 2015 At 0252 Salem Unit 2 entered Mode 4, and at 0920 Salem Unit 2 achieved Mode 5, Cold Shutdown.
An eight-hour NRC Event Notification was required by 10 CFR 50.72(b)(3)(v)(D) for an event that could have prevented the fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident. EN 51563 was completed on November 23, 2015, at 0446.
This LER is being made pursuant to the reporting requirements of 10 CFR 50.73(a)(2)(v)(D).
CAUSE OF EVENT
APPROVED BY OMB: NO. 3150-0104 01/31/2018 EXPIRES:
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 6. LER NUMBER YEAR I
SEQUENTIAL I REVISION NUMBER NUMBER 2015
- - 003
- - 000
- 3. PAGE 3 OF 3 A cause evaluation is in progress and will be reported in a supplement to this LER.
SAFETY CONSEQUENCES AND IMPLICATIONS
This event did not result in a release of radioactivity or an increase of offsite dose rates, and there were no personnel injured or damage to any other safety related equipment. The excessive unidentified leakage was quickly terminated. TS 3.0.3 was entered and the plant was placed in Mode 5, Cold Shutdown. A further review of the safety consequences will be performed after the cause analysis is completed.
SAFETY SYSTEM FUNCTIONAL FAILURE A review for Safety System Functional Failure (SSFF) as defined in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines, will be performed after the cause analysis is complete.
PREVIOUS OCCURRENCES
A review of Salem Unit 1 and 2 Licensee Event Reports for the previous three years identified a similar event requiring entry into TS 3.0.3 when both trains of intermediate head ECCS were rendered inoperable. That event was reported in LER 272/2014-005 Technical Specification 3.0.3 Entry; Two ECCS Subsystems Inoperable," dated August 27, 2014.
CORRECTIVE ACTIONS
- 1) The 2SJ10 relief valve was replaced and retested with no identified leakage.
- 2) A cause evaluation is in progress. Additional corrective actions will be determined upon completion of the evaluation.
COMMITMENTS
There are no regulatory commitments contained in this LER.