05000293/LER-2016-008, Regarding Emergency Diesel Generator a Past Inoperability

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Regarding Emergency Diesel Generator a Past Inoperability
ML17010A035
Person / Time
Site: Pilgrim
Issue date: 12/09/2016
From: Perkins E
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.16.075 LER 16-008-00
Download: ML17010A035 (7)


LER-2016-008, Regarding Emergency Diesel Generator a Past Inoperability
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

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)(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)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2932016008R00 - NRC Website

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~Ehtergr.

December 9, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. MA 02360

SUBJECT:

Licensee Event Report 2016-008-00, Emergency Diesel Generator 'A' Past lnoperability I

Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.16.075

Dear Sir or Madam:

The enclosed Licensee Event Report 2016-008-00, Emergency Diesel Generator 'A' Past lnoperability, is submitted in accordance with 10 Code of Federal Regulations 50. 73. The date the condition was discovered was September 28, 2016. As such, this 60-day 10 CFR 50.73 Licensee Event Report was due to the NRC Staff on November 27, 2016. This LER is being submitted late and Pilgrim Nuclear Power Station is addressing this through the Corrective Action Program.

If you have any questions or require additional information please contact me at (508) 830-8323.

There are no regulatory commitments contained in this letter.

Sincerely,

~~~~~p Everett P. Perkins~

Manager, Regulatory Assurance EPP/sc Attachment: Licensee Event Report 2016-008-00, Emergency Diesel Generator 'A' Past lnoperability (4 pages)

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station cc:

Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8C2A Washington, DC 20555 NRG Senior Resident Inspector Pilgrim Nuclear Power Station Letter No. 2.16.075 Page 2 of 2

Attachment Letter Number 2.16.075 Licensee Event Report 2016-008-00 Emergency Diesel Generator 'A' Past lnoperability (4 Pages)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014)

Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

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Reported lessons learned are incorporated into the licensing process and fed back to industry.

  • ~1 Send comments regarding burden estimate to the FOIA, Privacy and Information Collections

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~i LICENSEE EVENT REPORT (LER)

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by (See Page 2 for required number of internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC digits/characters for each block) 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME
12. DOCKET NUMBER 1* PAGE Pilgrim Nuclear Power Station 05000293 1 OF4
4. TITLE Emergency Diesel Generator 'A' Past lnoperability
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 MONTH DAY YEAR N/A N/A NUMBER NO.

FACILITY NAME DOCKET NUMBER 09 28 2016 2016

- 008
- 00 12 09 2016 N/A N/A
9. OPERA TING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO lHE REQUIREMENTS OF 10 CFR §: (Check all that apply)

D 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C)

D 50.73(a)(2)(vii)

N D 20.2201(d)

D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

D 20.2203(a)(1)

D 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)

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

D 20.2203(a)(2)(i) 0 50.36(c)(1 )(i)(A)

D 50.73(a)(2)(iii)

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

10. POWER LEVEL D 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

[8J 50.73(a)(2)(v)(A)

D 73.71(a)(4) 100 D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

[8J 50.73(a)(2)(v)(B)

D 73.71(a)(5)

D 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(C) 0 OTHER D 20.2203(a)(2)(vi)

[8J 50. 73(a)(2)(i)(B)

[8J 50.73(a)(2)(v)(D)

Specify in Abstract below or in REPORT ABILITY In a determination completed on October 11, 2016 it was conservatively determined that EOG-A would not have been able to run for its stated mission time of 30 days. This condition existed for a period of 28 days, which is greater than the TS Allowed Out of Service Time (AOT) of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. However, the Station Black Out Diesel Generator was available during this time frame. This issue is reportable under 10 CFR 50.73(a)(2)(i)(B) as an Operation or Condition which was Prohibited by the plant's Technical Specifications.

In addition, on September 15, 2016 EDG-B was made inoperable to perform its monthly operability run. This created a condition that could have prevented the fulfillment of the safety function of a system needed to shut down the reactor and maintain it in a safe condition, remove residual heat, and mitigate the consequences of an accident which is reportable in accordance with 10 CFR 50.73(a)(2)(v)(A), 50.73(a)(2)(v)(B), and

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

The date the condition was discovered was September 28, 2016. As such, this 60-day 10 CFR 50.73 Licensee Event Report was due to the NRC Staff on November 27, 2016. This LER is being submitted late, and PNPS is addressing this through the Corrective Action Program.

PREVIOUS EVENTS Events involving LERs where both EDGs were inoperable were reviewed. One related LER was identified and is summarized as follows:

LER 2016-001, "Both Emergency Diesel Generators Inoperable," dated June 9, 2016 stated while EDG-B was out for maintenance, EOG-A was declared inoperable due to a 130 dpm leak from the jacket water pressure boundary.

There were no other LERs involving EOG inoperability at PNPS identified in a search of the past five (5) years.

REFERENCES:

CR-PNP-2016-7443 CR-PNP-2016-9552 CR-PNP-2016-9653 CR-PNP-2016-9831