05000293/LER-2016-001, Regarding Both Emergency Diesel Generators Inoperable
| ML16168A030 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/09/2016 |
| From: | Perkins E Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.16.030 LER 16-001-00 | |
| Download: ML16168A030 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(v), Loss of Safety Function 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) |
| 2932016001R00 - NRC Website | |
text
~Entergx June 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 2016-001-00, Both Emergency Diesel Generators Inoperable Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35 LETTER NUMBER: 2.16.030
Dear Sir or Madam:
The enclosed Licensee Event Report (LER) 2016-001-00, Both Emergency Diesel Generators Inoperable, is submitted in accordance with 10 CFR 50. 73.
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If you have any questions or require additional information, contact me at (508) 830-8323, This letter contains no commitments.
Sincerely,
~t>Pu__~~
Everett P. Perkins, Jr.
Manager, Regulatory Assurance EPP/fxm Attachment : Licensee Event Report 2016-001-00, Both Emergency Diesel Generators Inoperable (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 NRC Senior Resident Inspector Pilgrim Nuclear Power Station
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Letter No.'2.16.030 Page 2 of 2
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Attachment Letter Number 2.16.030 Licensee Event Report 2016-001-00 Both Emergency Diesel Generators Inoperable (4 Pages)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
""*l!tlli:q 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 />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
~
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections LICENSEE EVENT REPORT (LER)
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by 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 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Pilgrim Nuclear Power Station 05000293 1 OF 4
- 4. TITLE Both Emergency Diesel Generators Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR N/A N/A FACILITY NAME DOCKET NUMBER 04 12 2016 2016 -
001 - 00 06 09 2016 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that ann/vJ D 20.2201(b)
D 20.2203(a)(3)(i)
D 50. 73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
N 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.:a-ko3(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)
D 50.73(a)(Z)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
~ 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 5o.36(c)(2)
~ 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 20.2203(a)(2)(iv)
D 5o.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1) 100 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
IRJ 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 73.71(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
SAFETY CONSEQUENCES
The standby AC power source provides two independent diesel generators as the onsite source of AC power to the emergency service portions of the station Auxiliary Power Distribution System. Each onsite source provides AC power to safely shut down the reactor, maintain the safe shutdown condition, and operate all auxiliaries necessary for station safety.
The safety objective of the standby AC power source is to provide a single failure proof source of onsite AC power adequate for the safe shutdown of the reactor following abnormal operational transients and postulated accidents.
The unit AC power source provides AC power to all station auxiliaries and is the normal station AC power I
source when the main generator is operating. The station preferred (offsite) AC power source provides AC power to all station auxiliaries required for startup and shutdown and is normally in use when the unit AC power source is unavailable. The secondary ( offsite) AC power source provides AC power to essential station auxiliaries. It is used to supply essential station auxiliary loads only when the main generator is shut down, there is a failure of the preferred AC power source, and failure of a standby AC power source.
The Station Blackout AC Power Source provides an independent diesel generator as the onsite source of AC power to the emergency service portions of the Auxiliary Power Distribution System in the unlikely event of a loss of preferred and secondary offsite power sources combined with a complete failure of the Standby AC Power System.
At the time of the event, the preferred AC and the secondary AC power sources were Operable and available to perform their intended safety function. In addition, the Station Blackout AC Power Source was Functional and available as the onsite source of AC power to the emergency service portions of the Auxiliary Power Distribution System.
Based on the operable and available preferred and secondary power sources, there was no adverse impact on the public health or safety.
REPORT ABILITY This report is submitted in accordance with 1 O CFR 50. 73(a)(2)(v)(A), 50. 73(a)(2)(v)(B), and 50. 73(a)(2)(v)(D) for 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 shutdown condition, remove residual heat, and mitigate the consequences of an accident.
PREVIOUS EVENTS Events involving LERs where both EDGs were inoperable were reviewed. These LERs are summarized as follows:
LER 99-006-00, LER 97-021-00, and LER 97-027-00 involved events where both emergency diesel generators were declared inoperable due to high ambient air temperatures. LER 98-004-00 and LER 98-002-00 involved events where both EDGs were declared inoperable due to low ambient temperatures.
These prior LERs involved events where both EDGs were declared inoperable at the same time; however, the events are different because equipment failure and EOG maintenance was not involved.
ENERGY INDUSTRY IDENTIFICATION SYSTEM (EllS) CODES The EllS codes for Components and Systems referenced in this report are as follows:
COMPONENTS Pipe Fitting SYSTEMS Diesel Cooling Water System
REFERENCES:
Condition Report CR-PNP-2016-2537 CODES PSF CODES LB