05000387/LER-2016-004, Regarding Electrical Transient Resulting in a Manual Scram

Regarding Electrical Transient Resulting in a Manual Scram

ML16194A242
Person / Time
Site:	Susquehanna
Issue date:	07/12/2016
From:	Franke J Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7503 LER 16-004-00
Download: ML16194A242 (5)

LER-2016-004, Regarding Electrical Transient Resulting in a Manual Scram

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(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 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)
3872016004R00 - NRC Website

text

JUL 1 2 2018 Jon A. Franke Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Jon. F ranke@T alenE nergy.com U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388(387)/2016-004-00 UNIT 2 LICENSE NO. NPF-22 UNIT 1 LICENSE NO. NPF-14 PLA-7503 TALEN--6' ENERGY 10 CFR 50.73 Docket No. 50-388 50-387 Attached is Licensee Event Report (LER) 50-388(387)/2016-004-00. The LER reports an event where Unit 2 experienced an electrical transient which caused the loss of power to essential plant loads. Drywell cooling was subsequently lost and drywell pressure increased causing operators to manually scram the reactor. A second reactor scram signal occurred and High Pressure Coolant Injection was overridden and declared inoperable, resulting in a Loss of Safety Function.

The power loss also tripped Reactor Building Heating Ventilation Air Conditioning causing a loss of secondary containment differential pressure resulting in a loss of safety function.

This event was dete1mined to be reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event or condition that resulted in manual or automatic actuation of an ECCS system and 10 CFR 50.73(a)(2)(v)(C) as an event or condition that could have prevented fulfillment of a safety function.

There were no actual consequences to the health and safety of the public as a result of this event.

latory commitments Attachment: LER 50-388(387)/2016-004-00 Copy:

NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, P A DEP/BRP Document Control Desk PLA-7503

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)

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

1. FACILITY NAME

~* DOCKET NUMBER r*

PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 of 3

4. TITLE Unit 2 experienced an electrical transient resulting in a manual SCRAM

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

MONTH DAY YEAR Susquehanna Steam Electric Station Unit 1 05000387 FACILITY NAME DOCKET NUMBER 05 13 2016 2016

- 004

- 00 O'l I ~ 2016 05000

9. OPERATING MODE

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

D 20.2201(b)

D 20.2203(a)(3)(i)

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

D 50.73(a)(2)(viii)(A) 1 D 20.2201(d)

D 20.2203(a)(3)(ii)

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

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

D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(iii)

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

D 20.2203(a)(2)(i)

D 50.36(c)(1)(i)(A) 1:81 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

D 20.2203(a)(2)(ii)

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

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

D 73.71(a)(4)

10. POWER LEVEL D 20.2203(a)(2)(iii)

D 50.36(c)(2)

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

D 73.71(a)(5) 100 D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii) 1:81 50.73(a)(2)(v)(C)

D 73.77(a)(1)

D 20.2203(a)(2)(v)

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

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

D 73.77(a)(2)(i)

D 20.2203(a)(2)(vi)

D 50.73(a)(2)(i)(B)

D 50.73(a)(2)(vii)

D 73.77(a)(2)(ii)

D 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in

ANALYSIS/SAFETY SIGNIFICANCE

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

2. DOCKET NUMBER

3. LER NUMBER 05000388 YEAR I

SEQUENTIAL I

REV NUMBER NQ 2016

- 004

- 00 Evaluation of the safety significance will be provided in the planned supplement to this LER.

CORRECTIVE ACTIONS

Two cause evaluations are in progress, and corrective actions will be provided in the supplement to this LER.

PREVIOUS SIMILAR EVENTS

Previous similar events will be provided in the planned supplement to this LER.

NRC FORM 366 (11-2015)