05000529/LER-2020-001, Reactor Trip on Low Steam Generator Level Signal
| ML20121A285 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/29/2020 |
| From: | Rash B Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-08077-BR/MMD LER 2020-001-00 | |
| Download: ML20121A285 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 5292020001R00 - NRC Website | |
text
10 CFR 50.73 A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek BRUCE J. RASH Vice President Nuclear Engineering/Regulatory Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623 393 6491 102-08077-BR/MMD April 29, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 2 Docket No. STN 50-529 / License No. NPF 51 Licensee Event Report 2020-001-00 Enclosed please find Licensee Event Report (LER) 50-529/2020-001-00 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER reports a Unit 2 reactor trip and other specified system actuations that occurred on March 3, 2020.
In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the Nuclear Regulatory Commission (NRC) Regional Office, NRC Region IV, and the Senior Resident Inspector.
Arizona Public Service Company makes no commitments in this letter. If you have questions regarding this submittal, please contact Matthew Kura, Department Leader, Nuclear Regulatory Affairs, at (623) 393-5379.
Sincerely, BR/MMD Enclosure cc:
S. A. Morris NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector PVNGS Rash, Bruce (Z77439)
Digitally signed by Rash, Bruce (Z77439)
DN: cn=Rash, Bruce (Z77439)
Date: 2020.04.30 12:53:10 -07'00'
NRC FORM 366 (04-2020)
NRC FORM 366 (04-2020)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 04/30/2020 LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 1. Facility Name Palo Verde Nuclear Generating Station (PVNGS) Unit 2
- 2. Docket Number 05000529
- 3. Page 1 OF 4
- 4. Title Unit 2 Reactor Trip on Low Steam Generator Level Signal
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year Sequential Number Rev No.
Month Day Year Facility Name Docket Number 05000 03 03 2020 2020
- - 001
- - 00 04 30 2020 Facility Name Docket Number 05000
- 9. Operating Mode 1
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0104), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503; e-mail: oira_submission@omb.eop.gov. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 3. LER NUMBER Palo Verde Nuclear Generating Station (PVNGS) Unit 2 05000-529 YEAR SEQUENTIAL NUMBER REV NO.
2020
- - 001
- - 00
5. ASSESSMENT OF SAFETY CONSEQUENCES
This event did not result in a challenge to fission product barriers or result in the release of radioactive materials. The event did not adversely affect the safe operation of the plant or health and safety of the public.
The RPS functioned as designed and initiated an automatic reactor trip that placed the plant in a safe condition. All required plant systems responded as expected and all CEAs fully inserted into the reactor core. The AFAS, the ESP pumps and the DGs actuated due to the of the low SG level. No safety related components failed to actuate. In addition, the MFWPs were available immediately following their trip to provide the heat removal function, if required.
The Unit 2 reactor trip did not result in a transient more severe than those already analyzed in the Updated Final Safety Analysis Report. The primary system and secondary pressure boundary limits were not approached.
The event would not have prevented the fulfillment of any safety function of structures or systems as defined by 10CFR 50.73(a)(2)(v).
6. CAUSE OF THE EVENT
The cause evaluation is still in progress; a supplement will be submitted to incorporate the result of the evaluation.
7. CORRECTIVE ACTIONS
The cause evaluation is still in progress; a supplement will be submitted to incorporate the result of the evaluation.
8. PREVIOUS SIMILAR EVENTS
The cause evaluation is still in progress; a supplement will be submitted to incorporate the result of the evaluation.