05000266/LER-1917-002, Regarding Operation or Condition Prohibited by Technical Specifications
| ML17347A770 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/13/2017 |
| From: | Coffey R Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17347A768 | List: |
| References | |
| NRC 2017-0053 LER 17-002-00 | |
| Download: ML17347A770 (4) | |
| 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2661917002R00 - NRC Website | |
text
December 13, 2017 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 1 Docket 50-266 Renewed License Nos. DPR-24 Licensee Event Report 266/2017-002-00 NRC 2017-0053 10 CFR 50.73 Enclosed is Licensee Event Report (LER) 266/2017-002-00 for Point Beach Nuclear Plant, Unit 1. NextEra Energy Point Beach, LLC is providing this LER regarding an operation or condition prohibited by Technical Specification.
This letter contains no new regulatory commitments.
If you have any questions please contact Mr. Eric Schultz, Licensing Manager, at 920/755-7854.
Sincerely, NextEra Energy Point Beach, LLC Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017) ht!Q://www. nrc.gov/reading-rmldoc-collectionslnuregsls!afflsr1 022/r3[)
the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME
~. DOCKET NUMBER
~*PAGE Point Beach Nuclear Plant Unit 1 05000266 1 of 3
- 4. TITLE Operation or Condition Prohibited by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NA NUMBER NO.
NA 10 29 2017 2017 002 00 12 13 2017 FACILITY NAME DOCKET NUMBER NA NA
- 9. OPERA11NG MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: Check all that apply)
MODE3 0 20.2201 (b) 0 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 0 20.2201(d) 0 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii) 0 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5) 0%
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1) 0 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
(g) 50. 73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT r~LEPHONE NUMBER (Include Ama Code)
Thomas P. Schneider, Senior Licensing Engineer 920-755-7797
- 13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TOEPIX FACTURER TO EPIX NA NA NA NA y
NA NA NA NA NA
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
~NO SUBMISSION NA NA NA DATE [ABSTRACT (Limit to 1400spaces, le., approximately 15sing/e-spacedtypewrilten lines)
On October 29, 2017, Unit 1 entered MODE 3 from MODE 4 without satisfying all of Technical Specification 3.7.5, Auxiliary Feedwater (AFW) Limiting Conditions for Operation (LCO) as required by LCO Applicability 3.0.4 for the Turbine Driven Auxiliary Feedwater (TDAFW) pump system.
LCO Applicability 3.0.4 does not permit entry into a MODE of applicability when an LCO is not met, unless the associated actions to be entered permit continued operation in the MODE for an unlimited time or after performance of an acceptable risk assessment and the appropriate risk management actions have been established. After entering MODE 3, it was discovered that components were not operable, contrary to LCO 3.0.4.
This event is being reported pursuant to 10 CFR 50. 73( a)(2)(i)(B), for an operation or condition prohibited by Technical Specifications.
NRC FORM 366 (04-2017)
Description of the Event:
YEAR 2017
- 3. LERNUMBER SEQUENTIAL NUMBER 002 REV NO.
00 At 1302 on October 29, 2017, Unit 1 entered MODE 3 from MODE 4 without satisfying all of Technical Specification 3.7.5, Auxiliary Feedwater (AFW) Limiting Conditions for Operation (LCO) as required by LCO Applicability 3.0.4.
LCO Applicability 3.0.4 does not permit entry into a MODE of applicability when an LCO is not met, unless the associated actions to be entered permit continued operation in the MODE for an unlimited time or after performance of an acceptable risk assessment and the appropriate risk management actions have been established.
At approximately 1500 on October 29, 2019 after entering MODE 3, it was discovered that components were not operable as required by Technical Specification LCO 3.7.5 to permit entry into MODE 3 per LCO 3.0.4. At 1610 on October 29, 2017 the affected steam supply valves [ISV][BA] to the TDAFW pump [P][BA] were opened, operability was restored and LCO 3.7.5 was met.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B), for an operation or condition prohibited by Technical Specifications.
Cause of the Event
The cause of the operation or condition prohibited by Technical Specifications was less than adequate process interface controls (clearance orders and procedures) to ensure required equipment operability.
Analysis of the Event
The AFW System consists of one full-capacity motor driven auxiliary feedwater (MDAFW) pump system and one full-capacity TDAFW pump system for each unit that ensures adequate feedwater is supplied to the steam generators for heat removal under all circumstances, including loss of offsite power and normal heat sink. During reactor startup activities after a planned refueling, the steam supply isolation valves to the TDAFW pump were not realigned after refueling maintenance activities due to an identified condition on the steam supply line requiring additional maintenance activities. The less than adequate process controls of the isolation components under the clearance order and operating procedure processes allowed the transition to MODE 3 from MODE 4 without having the TDAFW pump operable as required by LCO Applicability 3.0.4.
Corrective Actions
The TDAFW steam valves were positioned to the required position for the MODE of operation. Corrective actions have been created to improve the process interface controls to ensure adequate implementation of Technical Specification, and are being tracked in the corrective action program.
Safety Significance
The event was determined to be of very low safety significance. There is a low probability of an event occurring while the TDAFW pump steam supply valves were not operable. The reactor had been shutdown for several weeks completing refueling operations resulting in a relatively low reactor coolant system decay and residual heat capacity.
While the condition was present, the MDAFW pump was operable with the balance of the engineered safety feature systems, structures or components needed to shut down the reactor, maintain safe shutdown conditions, remove residual heat, control the release of radioactive material or mitigate the consequences of an accident were operable.
Additionally, the standby steam generator (SSG) feedwater pumps were available by manual operator action at the main control boards and local control panels. There was no impact on the health and safety of the public as a result of this condition. Page 2 of 3 (04-2017)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1 022, R.3 for instruction and guidance for completing this form htlp://www.nrc.gov/readinq-rm/doc-collections/nuregs/staff/sr1 022/r3D
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITYNAME
- 2. DOCKET NUMBER
- 3. LERNUMBER YEAR Point Beach Nuclear Plant Unit 1 05000266 2017
Similar Events
SEQUENTIAL NUMBER 002 REV NO.
00 LER 2016-003-00 has reported a similar event of LCO Application 3.0.4 in the past 3 years. However, the cause and corrective actions of this LER are not the same as this event.
Component Failure Data
None Page 3 of 3