05000272/LER-2016-006-01, Technical Specification for Containment Integrity Not Met
| ML18099A281 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/09/2018 |
| From: | Martino P Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N18-0034 LER 2016-006-01 | |
| Download: ML18099A281 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 2722016006R01 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 April 9, 2018 LR-N18-0034 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Salem Nuclear Generating Station Unit 1 Renewed Facility Operating License No. DPR-70 NRC Docket No. 50-272 LER 272/2016-006-01 0PSEG
.Nudear LLC 10 CFR 50.73 Technical Specification (TS) for Containment Integrity not met Licensee Event Report, 'Technical Specification (TS) for Containment Integrity not met" is submitted pursuant to 10 CFR 50.73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications..... "
Should you have any questions or comments regarding the submittal, please contact Mr. Harry Balian of Regulatory Affairs at (856) 339-2173.
There are no regulatory commitments contained in this letter.
Sincerely,
~ina Plant Manager Salem Generating Station Enclosure-LER 272/2016-006-01
Page2 LR-N18-0034 cc D. Lew, Administrator-Region 1 J. Kim, Licensing Project Manager-Salem P. Finney, USNRC Senior Resident Inspector-Salem P. Mulligan, Manager, IV, Bureau of Nuclear Engineering T. Cachaza, Salem Commitment Coordinator L. Marabella, Corporate Commitment Coordinator 10 CFR 50.73
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (02-2016)
, the NRC may not conduct or sponsor, and a carson is not reaulred to resoond to the information collection.
13.Page Salem Generating Station - Unit 1 05000272 1 OF3
- 4. Title Technical Specification (TS) for Containment Integrity not met
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Sequential Rev Facility Name Docket Number Month Day Year Year Number No.
Month Day Year
~5000 12 08 2016 2016 006 01 04 09 2018 Facility Name Docket Number 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 1 D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201 (d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. Power Level D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71 (a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(ii)
D 20.2203(a)(2)(vi) 181 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(iii)
D 50.73(a)(2)(i)(C)
D Other (Specify in Abstract below or in
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no safety consequences as a result of this event. The alignment supported full operability of the APD.
Prior to the start of the work window administrative controls were established to ensure containment isolation {BD}
could be performed by manual actions if required by the applicable Emergency Operating Procedure (EOP).
SAFETY SYSTEM FUNCTIONAL FAILURE A review of this event determined that a safety system functional failure (SSFF) as defined in NEI 99-02, Regulatory Assessment Performance Indicators Guidelines, did not occur. This event did not prevent the ability of a system to fulfill its safety function to either shutdown the reactor, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident.
PREVIOUS EVENTS A review of Salem licensee event reports for the previous three years identified one similar LER. LER 272/2017-001-000 reported Containment Integrity Inoperable for Longer than Allowed by Technical Specifications caused by human performance error because Operators did not implement LCO tracking as required by OP-SA-1 08-115-1001. The corrective actions taken were specific to that event and would not have prevented this event.
CORRECTIVE ACTIONS
This was a human performance error for which performance management actions will be taken to correct the behavior.
The performance management actions include reinforcement of standards and expectations with the individuals involved, departmental rollouts with the applicable departments involved and some procedure enhancements.
COMMITMENTS
There are no regulatory commitments in this LER.
NRC FORM 3668 (02-201 B)