05000530/LER-2016-001, Regarding Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications
| ML16260A417 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/16/2016 |
| From: | Lacal M Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-07337-MLL/SPD LER 16-001-00 | |
| Download: ML16260A417 (5) | |
| 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)(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) |
| 5302016001R00 - NRC Website | |
text
10 CFR 50.73 A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek MARIA L. LACAL Senior Vice President Nuclear Regulatory and Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623 393 6491 102-07337-MLL/SPD September 16, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 3 Docket No. STN 50-530 / License No. NPF 74 Licensee Event Report 2016-001-00 Enclosed please find Licensee Event Report (LER) 50-530/2016-001-00 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER reports a condition prohibited by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.11, Control Room Essential Filtration System (CREFS). This condition resulted in a CREFS air filtration unit being inoperable greater than the LCO Required Action Completion Time. The event investigation to determine the cause of this condition is in progress. A final disposition will be provided in a supplement to this LER which will be submitted upon completion of the event investigation.
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 Mark McGhee, Nuclear Regulatory Affairs Department Leader, at (623) 393-4972.
Sincerely, MLL/SPD/akf Enclosure cc:
K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector PVNGS Andrews, George W(Z99748)
Digitally signed by Andrews, George W(Z99748)
DN: cn=Andrews, George W(Z99748)
Reason: I am approving this document as delegated for Maria Lacal Date: 2016.09.16 16:10:57 -07'00'
NRC FORM 366 (11-2015)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (11-2015)
LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
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- 1. FACILITY NAME Palo Verde Nuclear Generating Station (PVNGS) Unit 3
- 2. DOCKET NUMBER 05000530
- 3. PAGE 1 OF 4
- 4. TITLE Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications
- 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 07 01 2016 2016 -
001
- - 00 09 19 2016 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(4) 100 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 73.77(a)(2)(i) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(ii) 50.73(a)(2)(i)(C)
OTHER Specify in Abstract below or in LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
5. ASSESSMENT OF SAFETY CONSEQUENCES
This event did not result in a potential transient more severe than those analyzed in the Updated Final Safety Analysis Report (UFSAR) or result in an abnormal release of radioactive materials to the environment. There were no actual safety consequences as a result of this event and the event did not adversely affect the health and safety of the public.
The nuclear safety risk significance associated with the subject condition was minimal. The degraded CREFS AFU filtration capability impacts design basis requirements regarding CR staff dose in design basis accidents. However, the condition has minimal impact on actual risk due to: (1) remaining margin in the filters capable of limiting doses from design basis events to those which will not create acute health effects and (2) the availability of portable air breathing devices to minimize the dose impacts from elevated CR airborne radionuclides in design basis and beyond design basis events. In addition, the likelihood of events creating radioactive releases capable of causing acute health effects to the CR staff assuming no CREFS AFU capability is very small (< 2E-6 per year) based on the probabilistic risk assessment model results.
The event would not have prevented the fulfillment of a safety function and the condition did not result in a safety system functional failure as defined by 10 CFR 50.73 (a)(2)(v). A final disposition will be provided in a supplement to this LER which will be submitted upon completion of the event investigation.
6. CAUSE OF THE EVENT
The event investigation is still in progress. The cause of this condition will be reported in a supplement to this LER.
7. CORRECTIVE ACTIONS
As an immediate corrective action, the CREFS AFU filter bed was replaced and testing was completed.
The CREFS AFU was declared operable on July 24, 2016.
The event investigation is still in progress. The corrective actions will be reported in a supplement to this LER.
8. PREVIOUS SIMILAR EVENTS
No similar conditions have been reported by PVNGS in the last three years.