05000272/LER-2015-002-01, Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

ML15188A115
Person / Time
Site:	Salem
Issue date:	07/06/2015
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N15-0138 LER 15-002-01
Download: ML15188A115 (5)

LER-2015-002, Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

Event date:
Report date:
Reporting criterion:	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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2722015002R01 - NRC Website

text

JUL 06 2015 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSEG LR-N15-0138 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

REFERENCE:

Salem Nuclear Generating Station Unit 1 Renewed Facility Operating License No. DPR-70 NRC Docket No. 50-272 Licensee Event Report 272/2015-002-001 PSEG Letter LR-N15-0056, dated April 10, 2015 Licensee Event Report 272/2015-002-000 The Licensee Event Report (LER), 272/2015-002-001, "Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable" is being submitted in accordance with the requirements of 1 O CFR 50. 73(a)(2)(i)(B), "Any operation which was prohibited by the plant's Technical Specifications... " The referenced LER indicated that Salem Nuclear Generating Station would submit a supplement to the LER by July 9, 2015. The results of the causal evaluation are provided in the LER supplement attached to this letter.

Should you have any questions or comments regarding the submittal, please contact David Lafleur of Salem Regulatory Assurance at 856-339-1754.

There are no regulatory commitments contained in this letter.

Sincerely, fe:?-

Site Vice President - Salem Attachments (1)

JUL 0 6 2015 Page 2 LR-N15-0138 cc 10 CFR 50.73 Mr. D. Dorman, Administrator - Region 1, NRC Ms. C. Parker, 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: 01/31/2017 (01-2014)

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.

• • • • • r.J Send comments regarding burden estimate to the FOIA, Privacy and Information Collections LICENSEE EVENT REPORT {LER)

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 NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Salem Generating Station - Unit 1 05000272 1 OF 3

4. TITLE Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

05000 FACILITY NAME DOCKET NUMBER 08 19 2013 2015

- 002

- 001 07 06 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) 0 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) 0 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) 0 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 so.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) 0 OTHER D 20.2203(a)(2)(vi) 12:1 50.73(a)(2)(i)(B)

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

Specify in Abstract below or in required by TS.

This event is reported in accordance with 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 the 11 SG, Channel 2 drifting indication and subsequent failure was due to failure of the 1 L T519 level transmitter. The completion of the past functionality review was delayed and not completed until February 12, 2015 due to lack of timeliness guidance in the past functionality evaluation process.

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. The remaining two 11 SG level protection channels were functional and their SG LO-LO Level protective trip functions remained capable of generating a reactor trip signal during the time in which 1 L T519 was inoperable.

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.

1 L T519 was replaced and tested satisfactorily on March 27, 2015.

2.

The removed 1 L T519 has been sent to the manufacturer for failure analysis.

3.

Guidance will be added to the engineering technical evaluation procedure for past operability and functionality reviews to be completed within 45 days from the discovery date.

COMMITMENTS

This LER contains no regulatory commitments.