05000311/LER-2015-001, Unit 2, Regarding Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable

Unit 2, Regarding Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable

ML15079A007
Person / Time
Site:	Salem
Issue date:	03/19/2015
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N15-0040 LER 15-001-00
Download: ML15079A007 (5)

LER-2015-001, Unit 2, Regarding Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable

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) 10 CFR 50.73(a)(2)(ix)(A) 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)(v), Loss of Safety Function
3112015001R00 - NRC Website

text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSE:CI MAR 19 2015 LR-N15-0040 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LER 311 /2015-001-00 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 J,/J:

SUBJECT:

Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable The Licensee Event Report, "Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable" is being submitted pursuant to 10 CFR 50.73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications... "

The attached LER contains no commitments. Should you have any questions or comments regarding the submittal, please contact David Lafleur of Salem Regulatory Assurance at 856-339-1754.

Sincerely, 1n£r****

John F. Perry U

Site Vice President - Salem Attachments (1)

MAR 19 2015 Page 2 LR-N15-0040 cc 10 CFR 50.73 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 Mr. D. Lafleur, Salem Regulatory Assurance

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0113112017 (01-2014)

1. '

Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

Reported lessons learned are incorporated into the licensing process and fed back to industry.

• • • • • X LICENSEE EVENT REPORT (LER)

Send comments regarding burden estimate to the FOIA, Prtvacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by (See Page 2 for required number of internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC digits/characters for each block) 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

I

. PAGE Salem Generating Station - Unit 2 05000311 1 OF 3

4. TITLE Condition Prohibited by Technical Specification for One Channel of Overtemperature Delta-T Inoperable

5. EVENT DATE

6. LER NUMBER

7. RE PORT DATE

8. OTHER FACILITIES INVOLVE D MONTH DAY YEAR YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

05000 FACILITY NAME DOCKET NUMBER 01 20 2015 2015

- 001

- 000 03 19 2015 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)(i)(C)

D 50.73(a)(2)(vii)

D 20.2201{d)

D 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

10. POWER LEVEL D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2){viii)(B)

D 20.2203(a)(2)(i)

D 50.36(c)(1)(i)(A)

D 50.73{a)(2){iii)

D 50.73(a)(2)(ix)(A) 100%

D 20.2203(a)(2)(ii)

D 50.36(c)(1 )(ii)(A)

D 50. 73( a )(2)(iv)(A)

D 50. 73(a)(2)(x)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

D 50.73(a)(2)(v)(A)

D 73.71(a)(4)

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

D 50.73(a)(2)(v)(B)

D 73.71(a)(5)

D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(C) 00THER D 20.2203(a)(2)(vi) 9 50.73(a)(2)(i)(B)

D 50. 73(a)(2)(v)(D)

Specify in Abstract below or in requirements of 10 CFR 50. 73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications...

CAUSE OF EVENT

The cause of Channel 4 OT Delta-T inoperability was due to a failed voltage isolator from PR NI 2N44.

SAFETY CONSEQUENCES AND IMPLICATIONS

The safety significance of this event is minimal. This event did not result in any offsite release of radioactivity or increase of offsite dose rates, and there were no personnel injuries or damage to any other safety-related equipment. Existing plant conditions during this event did not challenge the OT Delta-T trip setpoint and the remaining three channels of OT Delta-T remained operable and capable of generating an OT Delta-T trip signal for all appropriate plant conditions.

SAFETY SYSTEM FUNCTIONAL FAILURE A review of this event determined that a Safety System Functional Failure (SSFF) as defined in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline, 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 OCCURRENCES

A review of Salem Unit 1 and 2 Licensee Event Reports for the previous three years identified no other

CORRECTIVE ACTIONS

1.

A new 2N44 isolator was installed, tested satisfactorily and returned to service.

2. A failure analysis will be performed for the failed 2N44 isolator card.

3. A causal evaluation will address control room channel check and monitoring practices for detection of channel failures.

COMMITMENTS

This LER contains no regulatory commitments.