05000414/LER-2019-003, Component Cooling Water System Alignment Led to Both Trains of Component Cooling Water Inoperable
| ML19247D814 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/04/2019 |
| From: | Simril T Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-19-0346 LER 2019-003-00 | |
| Download: ML19247D814 (7) | |
| 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)(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)(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)(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) |
| 4142019003R00 - NRC Website | |
text
(_-, DUKE
~ ENERGY~
RA-19-0346 September 4, 2019 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 2 Docket No. 50-414 Licensee Event Report (LER) 414/2019-003-00 Tom Simril Vice President Catawba Nuclear Station Duke Energy CN01VP I 4800 Concord Road York, SC 29745 o: 803 701 3340 f 803 701 3221 10 CFR 50.73 Pursuant to 10 CFR 50.73(a)(1) and (d), attached is LER 414/2019-003-00, entitled "Component Cooling Water System Alignment led to Both Trains of Component Cooling Water Inoperable."
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), (B), and (D).
There are no regulatory commitments contained in this letter or its attachment.
This event is considered to be of no significance with respect 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 4, 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 11555 Rockville Pike Mailstop O-8G9A Rockville, MD 20852 J. Austin NRC Senior Resident Inspector
United States Nuclear Regulatory Commission Page 3 September 4, 2019 bxc (electronic copy)(with attachment):
ICES Lee.Harmon@NRC.gov INPO L.E. Harmon Christian Scott S.E. Andrews J. Constant (ICES)
T.G. Hinkle R.T. Simril, Jr.
B.C. Carroll M.C. Nolan A.H. Zaremba A. Linker bxc (hard copy)(with attachment):
ELL-EC02ZF Master File CN-801.01 LER File RGC Date File NCMPA-1 NCEMC PMPA
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.
CAUSAL FACTORS:
The causes of this event were determined to be:
1.
Calculation CNC-1223.23-00-0042 and procedure OP/2/A/6400/005 Enclosure 4.9 changes failed to identify the requirement to meet TS Surveillance 3.7.7.2.
2.
Operators lacked a questioning attitude with information in the design bases document and approved procedures.
CORRECTIVE ACTIONS
Planned:
1.
Correct operating procedures to ensure interlocks are not defeated that would lead to Inoperable train(s).
2.
Issue crew learnings to Operations and Engineering organization with lessons learned.
3.
Implement Training.
SAFETY ANALYSIS
During the time of the Unit 2 KC system Inoperability, the 2B KC train remained available to perform its required safety function to support Emergency Coore Cooling operation. The effects of the Cross Train Alignment on KC system operation for various accident and operating modes relative to flow demands, heat loads were evaluated and determined the alignment to be within the capabilities of the system and equipment. This event is considered to be of very low safety significance as component cooling was not challenged. There was no impact to the health and safety of the public.
4 4
Catawba Nuclear Station, Unit 2 414 2019 003 00 Annunciator received for KC Train B Single Pump Runout, indicative of time when 2KC-5 failed to close KC Train 2A Inoperable, Unit 2 entered TS LCO 3.7.7 Started procedure OP/2/A/6400/005 Enclosure 4.9 Completed OP/2/A/6400/005 Enclosure 4.9 Step 3.1.5 which then defeats the interlocks for the Non-Essential Reactor Building Supply and Return Header Valves. (2B KC Train Inoperable)
Question raised regarding KC Operability with interlocks defeated Completed OP/2/A/6400/005 Enclosure 4.9 Step 3.31 which reinstalls leads to reinstate the interlocks for the Non-Essential Reactor Building Supply and Return Header Valves.
(2B KC Train Operable)
KC Operability question placed into sites corrective action program KC Train 2A returned to Operable Reportability Evaluation approved concluding KC Train 2B was inoperable during alignment While the alignment was in progress, the question was separately raised regarding KC Operability with the interlocks defeated. Additional research was performed that did not immediately lead to a different Operability conclusion. On the same day, the question was placed into Catawbas corrective action program to receive a more formal evaluation.
After the alignment was secured, a reportability evaluation was performed at a later date. This evaluation concluded that KC Train 2B was inoperable during the alignment.
Timeline of Events:
July 5, 2019 1304 July 5, 2019 1330 July 6, 2019 0033 July 6, 2019 0156 July 6, 2019 July 6, 2019 1545 July 6, 2016 1805 July 6, 2019 2250 August 1, 2019
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