05000278/LER-2018-003, Automatic Reactor Scram Due to Loss of Two Condensate Pumps

Automatic Reactor Scram Due to Loss of Two Condensate Pumps

ML18333A304
Person / Time
Site:	Peach Bottom
Issue date:	11/29/2018
From:	Pat Navin Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CCN: 18-121 LER 2018-003-00
Download: ML18333A304 (4)

LER-2018-003, Automatic Reactor Scram Due to Loss of Two Condensate Pumps

Event date:
Report date:
Reporting criterion:	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), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
2782018003R00 - NRC Website

text

Exelon Generation CCN: 18-121 November 29, 2018 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001

Subject:

Peach Bottom Atomic Power Station (PBAPS) Unit 3 Renewed Facility Operating License No. DPR-56 NRC Docket No. 50-278 Licensee Event Report (LER) 3-18-003 10CFR 50.73 Enclosed is a Licensee Event Report concerning an automatic reactor scram following the loss of two condensate pumps. In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations. The specific methods that have been planned to restore and maintain compliance are discussed in the LER. If you have any questions or require additional information, please do not hesitate to contact Matt Retzer at 717-456-4351.

Patrick D. Navin Site Vice President Peach Bottom Atomic Power Station PDN/dnd/IR 4178845 Enclosure cc:

US NRC, Regional Administrator, Region I US NRC, Senior Resident Inspector R. R. Janati, Commonwealth of Pennsylvania D. Tancabel, State of Maryland B. Watkins, PSE&G, Financial Controls and Co-Owner Affairs

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2016)

Estlnated the NRC may not conduct or sponsor, and a o/-0 person ~not required to respond to, the '1formalion collection

3. Page Peach Bottom Atomic Power Station Unit 3 05000278 1

OF 3

4. Title Automatic Reactor Scram Due to Loss of Two Condensate Pumps

5. Event Date

6. LER Number

7. Report Date

8. Other Facilities Involved I

Sequential I Rev Facility Name Docket Number Month Day Vear Vear Number No.

Month Day Vear 05000 Facility Name Docket Number 09 30 2018 2018 -

003 0

11 29 2018 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)

D 20.2201(d)

D 20.2203(a)(3)(ii)

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

D 50.73(a)(2)(viii)(B) 1 D 20.2203(a)(1)

D 20.2203(a)(4)

D D

50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)

D 20.2203(a)(2)(i)

D 50.36(c)(1)(i)(A)

~ 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x) 1 O. Power Level 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)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

D 50. 73(a)(2)(v)(B)

D 73.71 (a)(S)

D 20.2203(a)(2)(iv)

• D so.46(a)(3)(ii)

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

D 13.77(a)(1) 100%

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)

D Other {Specify in Abstract below or in

Cause of the Event

SEQUENTIAL NUMBER 003 REV NO.

0 Both conditions that led to the reactor scram (water in a cable for the '38' condensate pump transformer and an incorrectly routed ground wire for the '3A' condensate pump) were due to failure to comply with Electrical Specification E-1317, 'Wire and Cable - Notes and Details," when work was being performed. This specification contains requirements for waterproofing the ends of cables when they are being pulled through underground conduits and requirements for routing grounding wires when using zero-sequence CTs.

Corrective Actions

The affected equipment has been repaired. Cables have been replaced for the '38' condensate pump and the '3A' cable shield ground wire has been routed through the CT. Additional corrective actions are documented in the Corrective Action Program.

Previous Similar Occurrences No previous similar occurrences have been identified. Page _3_ of _L