05000354/LER-2012-002, Regarding High Pressure Coolant Injection System Inoperable

Regarding High Pressure Coolant Injection System Inoperable

ML12144A090
Person / Time
Site:	Hope Creek
Issue date:	05/14/2012
From:	Doris Lewis Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N12-0149 LER 12-002-00
Download: ML12144A090 (5)

LER-2012-002, Regarding High Pressure Coolant Injection System Inoperable

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3542012002R00 - NRC Website

text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 P

PSEG Nuclear LLC MAY 1 4 2012 LR-N 12-0149 1 0CFR50.73 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Unit 1 Facility Operating License No. NPF-57 Docket No. 50-354

Subject:

Licensee Event Report 2012-002 In accordance with 10 CFR 50.73(a)(2)(v)(D), PSEG Nuclear LLC is submitting Licensee Event Report (LER) Number 2012-002 Should you have any questions concerning this letter, please contact Mr. Paul Bonnett at (856) 339-1923.

No regulatory commitments are contained in the LER.

Sincerely, David P. Lewis Plant Manager Hope Creek Generating Station Attachment: Licensee Event Report 2012-002

Page 2 LR-N12-0149 Document Control Desk cc:

Mr. W. Dean, Regional Administrator - Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. Hughey, Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B1A 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Hope Creek (X24)

P. Mulligan, Manager Bureau of Nuclear Engineering\\

New Jersey Department of Environmental Protection PO Box 420 Trenton, NJ 08625 Hope Creek Commitment Tracking Coordinator (H02)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 110-2010)

, the NRC may sfor each block)inot conduct or sponsor, and a person is not required to respond to, the digits/characters frecblk)information collection.

13. PAGE Hope Creek Generating Station 05000354 1 OF 3

4. TITLE High Pressure Coolant Injection System Inoperable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACII NAME DOCKET NUMBERDY E

NUMBER NO.

/

FACILITY NAME DOCKET NUMBER 03 14 2012 2012 - 002 - 000 05 14 2012 N/A

9. OPERATING MODE

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)

[E 50.73(a)(2)(vii)

[1 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)

[3 20.2203(a)(4) 0l 50.73(a)(2)(ii)(B)

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

_E 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(a)(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)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

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

El 73.71(a)(5) 100 El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

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

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

El 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)

Specify in Abstract below or in

CAUSE OF EVENT

The cause of the event was an unexpected response of the HPCI turbine governor control valve that is most likely due to a potential internal malfunction of the EGR. The cause will be determined once the manufacturer's failure analysis results are received and reviewed. A supplemental report will be submitted once the failure analysis has been review and the causal evaluation has been approved.

SAFETY CONSEQUENCES AND IMPLICATIONS

HPCI was declared inoperable. Based on the HPCI system being inoperable, a Safety System Functional Failure (SSFF) occurred as defined in Nuclear Energy Institute (NEI) 99-02.

PREVIOUS OCCURRENCES

A review of Licensee Event Reports for the past three years at Hope Creek was performed to determine if a similar event had occurred. No similar events were noted.

CORRECTIVE ACTIONS

1.

2.

3.

The EGR and remote servo was replaced.

The EGR and remote servo was sent to Woodward for failure analysis and refurbishment.

An apparent cause evaluation is being conducted.

COMMITMENTS

This LER contains no regulatory commitments.

NRC FORM 366 (10-201 0)

PRINTED ON RECYCLED PAPER NRC FORM 366 (10-2010)

PRINTED ON RECYCLED PAPER