05000413/LER-2019-002-01, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Auxiliary Feedwater Sump Pump Conditions
| ML19254F558 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 09/11/2019 |
| From: | Simril T Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-19-0366 LER 2019-002-01 | |
| Download: ML19254F558 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 4132019002R01 - NRC Website | |
text
( a,Dt1KE ENERGY8 RA-19-0366 September 11, 2019 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 Docket No. 50-413 Licensee Event Report (LER) 413/2019-002-01 Tom Simril Vice President Catawba Nuclear Station Duke Energy CN01VP I 4800 Concord Road York, SC 29745
- 0. 803.701.3340 f 803.701.3221 10 CFR 50.73 Pursuant to 10 CFR 50.73(a)(1) and (d), attached is LER 413/2019-002-01, entitled "Condition Prohibited by Technical Specifications and Loss of Safety Function due to Auxiliary Feedwater Sump Pump Conditions." This a revision to LER 412/2019-002-00 submitted on June 10, 2019.
Revisions to the LER are designated by revision bars in the margin.
This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(A), (8), and (D).
There are no regulatory commitments contained in this letter or its attachment.
There was no impact to the health and safety of the public.
If questions arise regarding this LER, please contact Sherry E. Andrews of Regulatory Affairs at (803) 701 -3424.
Sincerely, Tom Simril Vice President, Catawba Nuclear Station Attachment
United States Nuclear Regulatory Commission Page 2 September 11, 2019 xc (with attachment):
L. Dudes Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303 M. Mahoney NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop O-8B1A Rockville, MD 20852-2738 J. Austin (without attachment)
NRC Senior Resident Inspector
United States Nuclear Regulatory Commission Page 3 September 11, 2019 bxc (electronic copy)(with attachment):
INPO ICES L.E. Harmon Lee.Harmon@NRC.gov M. Hare S.E. Andrews J. Constant (ICES)
B.C. Carroll M.C. Nolan A.H. Zaremba NCMPA-1 NCEMC PMPA ELL-EC02ZF bxc (hard copy)(with attachment):
LER File RGC Date File
NRC FORM 366 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION 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/)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
NRC FORM 366 (04-2018) 05000
- 3. Page 1
OF
- 5. Event Date Month Day Year
- 6. LER Number Year Sequential Number Rev No.
- 7. Report Date Month Day Year
- 8. Other Facilities Involved Facility Name Docket Number 05000 Facility Name Docket Number 05000
- 9. Operating Mode
- 10. Power Level
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 20.2201(b) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5) 73.77(a)(1) 73.77(a)(2)(i) 73.77(a)(2)(ii)
Other (Specify in Abstract below or in Page of 05000-
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
Planned Resolve the design basis documentation and procedures to capture the safety significance of the AFW sump pumps as described in the new Auxiliary Building flooding calculation.
Completed A cause analysis was performed to determine why the safety significance of the AFW sump pumps was not recognized.
SAFETY ANALYSIS
The event on January 19, 2019, where all Unit 1 AFW sump pumps were concurrently non-functional, spanned a time of 53 minutes (as indicated by door records with auxiliary operators entering and leaving the pump room). Due to the AFW sump pumps being unavailable during this time, the MDAFW pumps were therefore TS inoperable which results in a loss of safety function. However, the MDAFW pumps could have performed their safety function during this 53 minute time frame. During this time four auxiliary operators were stationed in the AFW pump room while administering a planned activity using an approved test procedure. In the event of a feedwater line break in the interior doghouse, Operators could have backed out of the test procedure and restored functionality of the sump pumps long before the 11.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> required for the AFW pump room to fill with water and flood out the AFW pumps. No damage to AFW equipment occurred. This event is considered to be of very low safety significance as decay heat removal was not challenged. There was no impact to the health and safety of the public.
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