05000272/LER-1916-006, Regarding Technical Specification (TS) for Containment Integrity Not Met
| ML18011A658 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/11/2018 |
| From: | Mcfeaters C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N18-0007 LER 16-006-00 | |
| Download: ML18011A658 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 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 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 2721916006R00 - NRC Website | |
text
JAN 11 2018 LR-N 18-0007 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 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 272/2016-006-00 Technical Specification (TS) for Containment Integrity not met 10 CFR 50.73 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. Thomas Cachaza of Regulatory Affairs at 856-339-5038.
There are no regulatory commitments contained in this letter.
Sincerely, Charles V. McFeaters Site Vice President Salem Generating Station Enclosure - LER 272/2016-006-00
Page 2 LR-N 18-0007 cc D. Dorman, Administrator-Region 1 C. Parker, 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 FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017)
, the NRC may not conduct or sponsor, and a person is not required to httQ://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1 022/r3/)
respond to, the information collection.
- 3. PAGE Salem Generating Station-Unit 1 05000272 1 OF 2
- 4. TITLE Technical Specification (TS) for Containment Integrity not met
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 12 08 2016 2016 -
006 00 01 12 2018 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
D 20.2201 (b)
D 20.2203(a)(3)(i)
D 50. 73(a)(2)(ii)(A)
- 50. 73(a)(2)(viii)(A) n 20.2201 (d) 20.2203( a)(3)(ii)
- 50. 73(a)(2)(ii)(B)
- 50. 73( a)(2)(viii)(B) 1 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii)
- 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) 50.36(c)(2)
D 50.73(a)(2)(v)(B) 73.71 (a)(5) 100%
20.2203(a)(2)(iv) 50.46(a)(3)(ii)
- 50. 73(a)(2)(v)(C) 73.77(a)(1)
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
- 50. 73(a)(2)(v)(D)
- 73. 77( a)(2)(i)
D 20.2203(a)(2)(vi)
E2J 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
- 50. 73(a)(2)(i)(C)
OTHER Specify in Abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)
Thomas J. Cachaza, Senior Regulatory Compliance Engineer 856 - 339 - 5038 MANU-REPORTABLE '.
MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
- 14. SUPPLEMENTAl-REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR
[?]YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
NO SUBMISSION DATE 04 12 2018 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On December 8, 2016 the Containment {CTMT) Air Particulate Detector (APD), Normal Containment Isolation Valves (ClV) were closed to support a planned maintenance activity and the Back Up (B/U) manual isolation valves were opened under administrative controls to support continued operation of the APD. The normal isolation valves and the backup isolation valves were restored to their normal positions on January 4, 2017 following completion of the maintenance activity. The B/U isolation valves were open for 27 days.
On November 14,2017 NRC Integrated Inspection Report 05000272/2017003 was issued documenting a Green Non-Cited Violation (NCV) of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.1, Containment Integrity. The report states that having the B/U manual ClV's open for 27 days constituted a violation of TS LCO 3.6.1.1, Containment Integrity in that the valves were not operated in an intermittent manner as specified by the TS.
This issue is under review and the results of the review will be published in a supplement to this LER.
NRC FORM 366 (11-2015)
PLANT AND SYSTEM IDENTIFICATION
Westinghouse-Pressurized Water Reactor {PWR/4}
Containment Leakage Control System {BD}
IDENTIFICATION OF OCCURRENCE Discovery Date: 11/14/2017 Event Date: 12/08/16 CONDITIONS PRIOR TO OCCURRENCE
- 2. DOCKET 05000272 Salem Unit 1 was in Mode 1, 100 percent rated thermal power (RTP).
DESCRIPTION OF OCCURRRENCE
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. LERNUMBER YEAR SEQUENTIAL REVISION NUMBER NUMBER 2016 006 00 On December 8, 2016 the Containment (CTMT) Air Particulate Detector (APD), Normal Containment Isolation Valves (CIV) were closed to support a planned maintenance activity and the Back Up (B/U) manuc:11 isolation valves were opened under administrative controls to support continued operation of the APD. The normal isolation valves and the backup isolation valves were restored to their normal positions on January 4, 2017 following completion of the maintenance activity. The B/U isolation valves were open for 27 days.
On November 14,2017 NRC Integrated Inspection Report 05000272/2017003 was issued documenting a Green Non-Cited Violation (NCV) of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.1, Containment Integrity. The report states that having the B/U manual CIV's open for 27 days constituted a violation of TS LCO 3.6.1.1, Containment Integrity in that the valves were not operated in an intermittent manner as specified by the TS.
The December 8, 2016 event date is based on the NRC determination that the activity on that date constituted a violation of TS 3.6.1.1
CAUSE OF EVENT
This issue is under review and the results of the review will be published in a supplement to this LER.
SAFETY CONSEQUENCES AND IMPLICATIONS
This issue is under review and the results of the review will be published in a supplement to this LER.
SAFETY SYSTEM FUNCTIONAL FAILURE This issue is under review and the results of the review will be published in a supplement to this LER.
PREVIOUS EVENTS This issue is under review and the results of the review will be published in a supplement to this LER.
CORRECTIVE ACTIONS
This issue is under review and the results of the review will be published in a supplement to this LER.
COMMITMENTS
There are no regulatory commitments contained in this LER. Page 2 of 2