05000387/LER-2004-001, Unit 1 - Automatic Actuation of a Emergency Diesel Generator When Operator Removed Incorrect 4.16 Kv Bus Fuses

Unit 1 - Automatic Actuation of a Emergency Diesel Generator When Operator Removed Incorrect 4.16 Kv Bus Fuses

ML041330374
Person / Time
Site:	Susquehanna
Issue date:	05/04/2004
From:	Richard Anderson Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5749 LER 04-001-00
Download: ML041330374 (6)

LER-2004-001, Unit 1 - Automatic Actuation of a Emergency Diesel Generator When Operator Removed Incorrect 4.16 Kv Bus Fuses

Event date:
Report date:
Reporting criterion:	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)(ix)(A) 10 CFR 50.73(a)(2)(iii) 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)(v), Loss of Safety Function
3872004001R00 - NRC Website

text

Richard L. Anderson Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3883 Fax 570.542.1504 rlanderson~pplweb.com

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WVm MAY 0 4 ZUU4 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP-1-17 Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2004-001-00 LICENSE NO. NPF-14 PLA-5749 Docket No. 50-387 Attached is Licensee Event Report 50-387/2004-001-00. This event'was determined to be reportable per 10 CFR 50.73(a)(2)(iv)(A), for an event that resulted in an unplanned automatic actuation of an emergency diesel generator. On March 7, 2004 at 0201 hours0.00233 days <br />0.0558 hours <br />3.323413e-4 weeks <br />7.64805e-5 months <br />, the 'A' emergency diesel generator started due to a detected under-voltage condition on its associated Unit 1 4.16 kV bus. The bus under-voltage condition was created when fuses were removed from an incorrect 4.16 kV bus breaker cubicle during equipment alignment activities for a planned load center / 4.16 kV bus maintenance outage. All plant equipment operated as expected. This event resulted in no actual adverse consequences to the health and safety of the public. There are no commitments associated with this Licensee Event Report.

Richard L. Anderson Vice President - Nuclear Operations Attachment

• 6~2_2-Document Control Desk PLA-5749 cc:

Mr. H. J. Miller Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19408 Mr. S. L. Hansell Sr. Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35 Berwick, PA 18603-0035 Mr. R. Osborne Allegheny Electric Cooperative P. 0. Box 1266 Harrisburg, PA 17108-1266 Mr. R. R. Janati Bureau of Radiation Protection Rachel Carson State Office Building P. 0. Box 8469 Harrisburg, PA 17105-8469

l NRC FbRM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7-2001)

COMMISSION

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

3. PAGE Susquehanna Steam Electric Station - Unit 1 05000387 1 OF 4

4. TITLE Automatic Actuation of 'A' Emergency Diesel Generator When Operator Removed Incorrect 4.16 kV Bus Fuses

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE J

8. OTHER FACILITIES INVOLVED

_ I FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMUBER ENO MO DAY YEAR I SSES - Unit 2 05000388 FACILITY NAME DOCKET NUMBER 03 07 2004 2004 -

001 -

00 05 04 2004 05000

9. OPERATING

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

MODE 5

l 20.2201 (b) 20.2203(a)(3)(ii) l 50.73(a)(2)(ii)(B) l 50.73(a)(2)(ix)(A) 1 0. POWER 20.2201 (d)

__20.2203(a)(4)

__50.73(a)(2)(iii) 50.73(a)(2)(x)

LEVEL 0

20.2203(a)(1) 50.36(c)(1)(i)(A) x 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a) (5) 20.2203(a)(2)(ii) 50.36(cI(2) 50.73(a)(2)(v)(B)

OtHer

- Specify in Abstract below or In

_ 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)

Abstract

At 02:01 on March 7, 2004 with Unit 1 in Mode 5 at 0% power and Unit 2 in Mode 1 at 100% power, the

'A' Diesel Generator (DG) started due to a detected under-voltage condition on the 1 A201 4.1 6kV Engineered Safeguard System bus. The bus under-voltage condition was created when an in-plant operator removed fuses from an incorrect 4.16 kV bus breaker cubicle during equipment alignment activities for a planned load center / 4.16 kV bus maintenance outage. All plant equipment operated as expected. The 'A' DG was returned to standby status at 16:44 on March 7, 2004. Two root causes were found. The in-plant operators involved did not use adequate self-check / peer-check techniques during performance of the procedure step that identified the location of the breaker cubicle fuses. Additionally, the load center / 4.16 kV bus maintenance outage procedure was not written in accordance with human performance standards. Human performance training was conducted at the plant's performance simulator for all available operators and supervisors. The corrective actions to be taken include establishing a peer-to-peer human performance observation program for field operational activities and incorporating human performance standards into all station load center / 4.16 kV bus procedures. This event is reportable as an event that resulted in an unplanned automatic actuation of an emergency diesel generator per 10 CFR 50.73(a)(2)(iv)(A). There were no actual consequences to the health and safety of the public as a result of this event since there was no actual design basis accident and all station equipment responded as designed during the event.

NNI, ILJMM 366 (7fL 1)

I (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)

ADDITIONAL INFORMATION

Past Similar Events:

LER 94-001-00 Docket No. 05000387 LER 90-022-00 Docket No. 05000387 Failed Component:

None