Regarding a Train a Safety Injection and Reactor Trip
Person / Time
ML12214A399
Site:	Salem
Issue date:	07/12/2012
From:	Kandasamy J Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N12-0229 LER 12-003-00
Download: ML12214A399 (3)
v • d • e

LER-2012-003, Regarding a Train a Safety Injection and Reactor Trip

Event date:
Report date:
2722012003R00 - NRC Website
v • d • e

text

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

~PSEG Nuclear LLC JUL 1, 2 2012 LR-N12-0229 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Unit 1 Facility Operating License No. DRP-70 NRC Docket No. 50-272

Subject:

Special Report 272/12-003-00, pursuant to the Requirements of Salem Unit I Technical Specification (TS) 3.5.2, Action b, for SI Accumulated Actuation cycles to date.

This Special Report is being submitted pursuant to the requirements of Salem Unit I Technical Specification (TS) 3.5.2, Action b. TS 3.5.2 Action b states:

"In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date."

DESCRIPTION OF OCCURRENCE On April 30, 2012, Salem Unit 1 was operating in Mode 1 at 100% Rated Thermal Power. Instrument and Control technicians were performing a functional surveillance on turbine first-stage pressure transmitter 1 PT505. Test preparations require the tripping of High Steam Line Flow bistables which make up the High Steam Line Flow coincident with either the Low Steam Line Pressure or Low-Low Tavg Safety Injection logic of the Solid State Protection System. At 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br /> (hrs.), upon trip of the second bistable, a Train "A" Safety Injection and Reactor Trip occurred. All SI, Phase A and Containment Ventilation Isolation components actuated as expected for a single train SI. The unit experienced a Main Feedwater Isolation, a Main Steam Isolation, and auto start of the Auxiliary Feedwater (AFW) system and Emergency Diesel Generators.

Operations entered Emergency Operations Procedure 1 -EOP-TRIP-1, Reactor Trip or Safety Injection, to respond to the trip and SI. Train B of SI was manually actuated. The

Document Control Desk Page 2 JUL 1, 2 2012 LR-N 12-0229 unit then transitioned to 1 -EOP-TRIP-3, Safety Injection Termination, to terminate the SI and realign the plant to transition to Mode 3, Hot Standby conditions.

Accumulated Cycles:

The total number of accumulated actuation cycles to date for Salem Unit I is 22 SI cycles to date.

There are no new commitments in this letter.

If there are any questions, please contact Thomas Cachaza at 856-339-5038.

Sincrely,~

Jhansi Kandasamy Manager - Salem Regulatory Assurance

Document Control Desk Page 3 LR-N12-0229 C

W. Dean, Administrator - Region 1 J. Hughey, Licensing Project Manager - Salem D. Schroeder, USNRC Senior Resident Inspector - Salem P. Mulligan, Manager, IV, Bureau of Nuclear Engineering T. Cachaza, Salem Commitment Coordinator L. Marabella, Corporate Commitment Coordinator

Licensee Event Report

Salem

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000272/LER-2012-001, Regarding Single Train Actuation of Safety Injection Due to Failure of Solid State Protection System	Regarding Single Train Actuation of Safety Injection Due to Failure of Solid State Protection System	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000311/LER-2012-001, Regarding Automatic Reactor Trip Due to Turbine Trip	Regarding Automatic Reactor Trip Due to Turbine Trip
05000311/LER-2012-002, Regarding Auxiliary Feedwater Flow Control Valve Failed Open with Zero Demand	Regarding Auxiliary Feedwater Flow Control Valve Failed Open with Zero Demand	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000272/LER-2012-003, Regarding a Train a Safety Injection and Reactor Trip	Regarding a Train a Safety Injection and Reactor Trip
05000311/LER-2012-004, Regarding Isolation of Service Water to the Emergency Diesel Generators While in Mode 6	Regarding Isolation of Service Water to the Emergency Diesel Generators While in Mode 6	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000272/LER-2012-004, Regarding Loss of Circulating Water and Manual Reactor Trip Due to Hurricane Sandy	Regarding Loss of Circulating Water and Manual Reactor Trip Due to Hurricane Sandy	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000272/LER-2012-005, Reactor Trip Due to Failure of the Main Power Transformer Overexcitation Relay	Reactor Trip Due to Failure of the Main Power Transformer Overexcitation Relay	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000311/LER-2012-005, Regarding Reactor Trip Due to Failure of a Feedwater Control Valve	Regarding Reactor Trip Due to Failure of a Feedwater Control Valve	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000272/LER-2012-003, Regarding a Train a Safety Injection and Reactor Trip

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