05000416/LER-2013-002, Regarding Reactor Protection System Actuation Due to a Turbine Trip
| ML13077A056 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/15/2013 |
| From: | Perino C Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| GNRO-2013/00006 LER 13-002-00 | |
| Download: ML13077A056 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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 |
| 4162013002R00 - NRC Website | |
text
~~Entergy GNRO-2013/00006 March 15, 2013 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Christina L. Perino Director, Nuclear Safety Assurance Grand Gulf Nuclear Station Tel. (601) 437-6299
SUBJECT:
Dear Sir or Madam:
Licensee Event Report 2013-002-00 Reactor Protection System Actuation Due to a Turbine Trip Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 Attached is Licensee Event Report 2013-002-00, which is a final report. This report is submitted in accordance with Title 10 Code of Federal Regulations 50.73(a)(2)(iv)(A).
This letter contains no new commitments. If you have any questions or require additional information, please contact Mr. Jeffery A. Seiter at (601) 437-2344.
Sincerely, CLP/slw
Attachment:
Licensee Event Report (LER) 2013-002-00 cc:
(see next page)
GNRO-2013/00006 Page 2 of2 cc:
U. S. Nuclear Regulatory Commission AnN: Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission AnN: Mr. Alan Wang, NRRlDORL Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2013/00006 Licensee Event Report (LER) 2013-002-00
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010) digits/characters for each block) the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 13. PAGE Grand Gulf Nuclear Station, Unit 1 05000416 10F3
- 4. TITLE Reactor Protection System Actuation Due to a Turbine Trip
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME N/A MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR N/A 01 14 2013 2013-002-00 03 15 2013 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) o 20.2201 (b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii) 1 o 20.2201 (d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 50.36(c)(1 )(i)(A) o 50.73(a)(2)(iii) o 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL o 20.2203(a)(2)(ii) o 50.36(c)(1 )(ii)(A) 181 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71 (a)(4) 100 o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71 (a)(5) o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(i)(B) o 50.73(a)(2)(v)(D)
Specify in Abstract below or in
E. CORRECTIVE ACTIONS
YEAR I SEQUENTIAL I REV.
NUM6ER NO 05000 416 I----'---'-"="-'--.L-.:.=.--I 2013 -- 002 -- 00 30F3 To correct the condition that caused this event, additional portions of the isophase bus with seal off bushings were de-energized. Covers were installed over the isophase bus duct viewing ports.
F. SAFETY ASSESSMENT
The event posed no threat to public health and safety as the RPS performed as designed. All safety systems responded as designed. The breaker thermal for the 1N21 F01 08 start-up outlet valve was reset and returned to service and did not prevent Operations from controlling the reactor water level.
Immediate actions performed by the Operations staff were adequate and appropriate in placing and maintaining the reactor in a safe shutdown condition. The highest noted pressure was approximately 1110 pounds per square inch gauge (psig). The lowest noted pressure was apprOXimately 930 psig. The lowest noted reactor water level was 0.89 inch on narrow range.
Although a reactor SCRAM is an initiator, nuclear safety was not compromised because safety related equipment necessary to safely shutdown the unit performed its safety function.
During the event, no Technical Specification defined Safety Limits were challenged.
Radiological Safety was not affected since there was no radiological release to the public during the event.
Response of the crew did not challenge established industrial safety protocol or requirements. There was no impact to the health and safety of the public, industrial safety or radiological safety as a result of this event.
G. ADDITIONAL INFORMATION
The isophase bus ducts were modified during the extended power uprate project in 2012. No previous SCRAMs at the site were caused by water leaking into an isophase bus.
The cause of start-up outlet valve 1N21 F01 08 not opening was determined to be a thermal overload breaker trip. The breaker thermal was reset and the valve was returned to service. CR-GGN-2012-13297 documents this issue and the corrective actions that will be taken as part of a work order during the next refueling outage.