05000311/LER-2019-001, Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage

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Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage
ML19091A260
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/01/2019
From: Martino P
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N19-0043 LER 2019-001-00
Download: ML19091A260 (4)
v • d • e


LER-2019-001, Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
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
3112019001R00 - NRC Website
v • d • e

text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 R O 1 2019 LR-N19-0043 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 LER 311/2019-001-00 10 CFR 50.73 Salem Unit 2 Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage This Licensee Event Report, " Salem Unit 2 Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage," is being submitted pursuant to the requirements of the Code of Federal Regulations 1 0CFR50. 73(a)(2)(iv)(A).

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, Patrick. Martino Salem Plant Manager Enclosure - LER 311/2019-001-00 cc:

USNRC Regional Administrator - Region 1 USNRC NRR Project Manager - Salem USNRC Senior Resident Inspector - Salem NJ Department of Environmental Protection, Bureau of Nuclear Engineering Commitment Coordinator, Salem Generating Station Corporate Commitment Coordinator, PSEG Nuclear, LLC

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

, the NRC may not conduct or sponsor, and a person is not required to htt12://www.nrc.gov/reading-rm/doc-colfections/nuregs/staff/sr1022/r3!)

respond to, the information collection.

3. PAGE Salem Generating Station - Unit 2 05000311 1 OF 3
4. TITLE Salem Unit 2 Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage
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 NUMBER NO.

MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 01 31 2019 2019 -

001 00 04 01 2019 05000

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

[" 20.2201(b)

[" 20.2203(a)(3)(i)

50. 73( a)(2)(ii)(A)
50. 73(a)(2)(viii)(A) 20.2201 (d) r 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)

C 20.2203(a)(2)(i) r 50.36(c)(1 )(i)(A)

P: 50.73(a)(2)(iv)(A) r: 50.73(a)(2)(x)

10. POWER LEVEL 20.2203(a)(2)(ii)

C 50.36(c)(1 )(ii)(A) r 50. 73( a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 100%

20.2203(a)(2)(iv) 50.46(a)(3)(ii)

C 50.73(a)(2)(v)(C) 73.77(a)(1) 20.2203(a)(2)(v)

50. 73(a)(2)(i)(A) 50.73(a)(2)(v)(D)
73. 77( a)(2)(i) 20.2203(a)(2)(vi)
50. 73( a)(2)(i)(B)
50. 73( a)(2)(vii) 73.77(a)(2)(ii)
50. 73(a)(2)(i)(C)

LOTHER Specify in Abstract below or in NRC Fom1 366A

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)

Thomas J. Cachaza, Senior Regulatory Compliance Engineer 856-339-5038 CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX C

KE N

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR L YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

[? NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On January 31, 2019 at 0301, Salem Unit 2 Reactor was manually tripped when four of six circulators were manually tripped on high traveling water screen differential pressures (DP) due to the accumulation of Frazil Ice on the traveling water screens. All systems functioned as expected and Unit 2 was stabilized in MODE 3 at normal operating pressure and temperature This event was reportable in accordance with 10CFR50.73(a)(2)(iv)(A). Notification of this event was provided via ENS 53852.

NRC FORM 366 (04-2018)

PLANT AND SYSTEM IDENTIFICATION

Westinghouse-Pressurized Water Reactor {PWR/4}

Reactor Protection System {JC/-}

Circulating Water System {KE/-}

Auxiliary FeedWater system {BN-}

IDENTIFICATION OF OCCURRENCE Event Date: January 31, 2019 Discovery Date: January 31, 2019 CONDITIONS PRIOR TO OCCURRENCE

2. DOCKET 05000311 Salem Unit 2 was in Mode 1, operating at 100 percent power.

DESCRIPTION OF OCCURRRENCE

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

3. LER NUMBER YEAR SEQUENTIAL REVISION NUMBER NUMBER 2019 001 00 On January 31, 2019 at 0301, Salem Unit 2 Reactor was manually tripped when four of six circulators were manually tripped on high traveling water screen differential pressures (DP). All of the Circulators experienced high DP across their Circulating Water (CW) intake travelling screens due to the accumulation of Frazil Ice. All systems functioned as expected and Unit 2 was stabilized in MODE 3 at normal operating pressure and temperature.

This event was reportable in accordance with 1 0CFR50. 73(a)(2)(iv)(A). Notification of this event was provided via ENS 53852.

CAUSE OF THE EVENT

The original design of the CW system did not account for the volume of frazil ice drawn in from the Delaware River. The large amount of frazil ice collected and clogged the travelling screens, resulting in high traveling screen DP. This required multiple circulators to be tripped, which required Salem Unit 2 to be manually tripped.

SAFETY CONSEQUENCE AND IMPLICATIONS No safety consequences are associated with this event. Operators responded appropriately to the removal of the CW pumps from service and the subsequent manual reactor trip in accordance with plant procedures. Plant response to the manual reactor trip was normal. All safety systems operated as required.

SAFETY SYSTEM FUNCTIONAL FAILURE This condition did not result in a safety system functional failure as defined in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines. This event did not result in a condition that would have prevented the fulfillment of a safety function of a system needed to shut down the reactor and maintain it in a safe shutdown condition, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident.

(cont.)

PREVIOUS EVENTS

2. DOCKET 05000311

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

3. LER NUMBER YEAR SEQUENTIAL REVISION NUMBER NUMBER 2019 001 00 A review of previous events for the past three years did not identify similar events.

CORRECTIVE ACTIONS

Revise the abnormal operating procedure, SC.OP-AB.ZZ-0001, Adverse Environmental Conditions, to incorporate frazil ice conditions in the Circulating Water Degradation Index.

COMMITMENTS

There are no regulatory commitments contained in this LER. Page 3 of 3

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