05000382/LER-2016-001, Regarding Incorrect Core Protection Calculator Addressable Constant Entered Because of Inadequate Procedure Resulting in a Condition Prohibited by Technical Specifications
| ML16245A929 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/01/2016 |
| From: | Jarrell J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2016-0057 LER 16-001-00 | |
| Download: ML16245A929 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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) |
| 3822016001R00 - NRC Website | |
text
10 CFR 50.73 W3F1-2016-0057 September 1, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Licensee Event Report (LER) 2016-001-00, Incorrect Core Protection Calculator Addressable Constant Entered Because of Inadequate Procedure Resulting in a Condition Prohibited by Technical Specifications Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
On July 3, 2016, Waterford Steam Electric Station, Unit 3 (Waterford 3) determined that an incorrect value for Azimuthal Power Tilt had been entered on one channel of Core Protection Calculators (CPCs).
LER 2016-001-00 provides details associated with a condition that resulted in inoperability of CPC Channel C for approximately 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />, exceeding the outage time allowed by Technical Specification 3.3.1 action 2 and 3.2.3 action a. This condition is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B).
This report contains no new commitments. Please contact John P. Jarrell, Regulatory Assurance Manager, at (504) 739-6685 if you have questions regarding this information.
Sincerely, JPJ/SWM
Attachment:
LER 2016-001-00 Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 jjarrel@entergy.com John P. Jarrell III Manager, Regulatory Assurance Waterford 3
W3F1-2016-0057 Page 2 cc:
Mr. Kriss Kennedy, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 April.Pulvirenti@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov
Attachment to W3F1-2016-0057 Licensee Event Report 2016-001-00 (4 pages)
NRC FORM 366 (06-2016)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (06-2016)
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/)
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- 1. FACILITY NAME Waterford 3 Steam Electric Station
- 2. DOCKET NUMBER 05000-382
- 3. PAGE 1 OF 4
- 4. TITLE Incorrect Core Protection Calculator Addressable Constant Entered Because of Inadequate Procedure 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 07 03 2016 2016 -
001
- - 00 09 01 2016 FACILITY NAME DOCKET NUMBER
- 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)(5)(ii) 50.73(a)(2)(i)(C)
OTHER Specify in Abstract below or in REPORTABLE OCCURRENCE 10 CFR 50.73(a)(2)(i)(B) - "Any operation or condition which was prohibited by the plant's Technical Specifications except when:
(1)
The Technical Specification is administrative in nature; (2)
The event consisted solely of a case of a late surveillance test where the oversight was corrected, the test was performed, and the equipment was found to be capable of performing its specified safety functions; or (3)
The Technical Specification was revised prior to discovery of the event such that the operation or condition was no longer prohibited at the time of discovery of the event."
The plant operated for approximately 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> outside of the allowed TS actions per TS 3.3.1 and 3.2.3.a.
PREVIOUS OCCURRENCES
A review of the Licensees corrective action program and previous Licensee Event Reports for the previous 3 years was performed and revealed no similar event.
CAUSAL FACTORS The Direct Cause of this event was that personnel manually entered an incorrect addressable constant for CPC Tilt (PID 063) on CPC C.
The Apparent Cause of this event is that the Core Protection Calculator Functional Test procedure contains vague guidance on how to verify inputted addressable constants are correct. This apparent cause resulted in this condition by implying to the operator/technician that only using the CPC printed Page of addressable constants to verify inputted addressable constants was correct and did not also prompt use of the CPC change log. This cause produced the effect of inputting a previously used and erroneous value into PID 063 (CPC Tilt). This erroneous value resulted in actual Azimuthal Power Tilt as measured by the COLSS exceeding the value inputted into CPC C. This should have resulted in entry into TS 3.2.3.a. The plant operated for approximately 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> outside of the allowed TS actions per TS 3.3.1 and 3.2.3.a.
The Contributing Cause of this event is that the procedure contains inadequate requirements for verification practices when inputting/changing addressable constants. This contributed to the event by not requiring an independent verification (as outlined in EN-HU-102, Human Performance Traps & Tools) of inputted addressable constants by a second operator.
CORRECTIVE ACTIONS
The key corrective action addressing this condition is to revise the procedure to provide specific guidance on how to verify inputted addressable constants are correct by making specific reference to the Addressable Constants change log maintained by Operations and to include an independent verification by a second operator to ensure that the addressable constants are correct.
SAFETY SIGNIFICANCE
No other CPC channel was inoperable during the time frame that the incorrect addressable constant was entered into CPC C. A review of the Plant Data indicates the maximum value of actual core tilt during this time period never exceeded the Core Operating Limit Report (COLR) of less than or equal to 0.03. CPC C was available during the subject time period to provide the low DNBR and high LPD reactor trip functions with the incorrect applied tilt allowance being slightly less conservative than the tilt allowance of the other three CPCs. If actual core tilt had exceeded the CPC Azimuthal Tilt Exceeded alarm setpoint during the subject time period, an annunciator would have prompted Operator action to evaluate the PID 063 Azimuthal Power Tilt Allowance in all four CPCs. No safety limits were challenged or exceeded during the event. Systems or components needed to safely shutdown the reactor, maintain safe shutdown conditions, remove residual heat, control the release of radioactive material,
and mitigate the consequences of an accident were available.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes and component function identifiers are identified in the text with brackets [ ].