05000382/LER-2008-002, Regarding Inoperable Steam Generator Narrow Range Level Channels
| ML082040278 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/17/2008 |
| From: | Murillo R Entergy Nuclear South |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2008-0007 LER 08-002-00 | |
| Download: ML082040278 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3822008002R00 - NRC Website | |
text
'd=ýEntergy Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504 739 6715 Fax 504 739 6698 rmurill@entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3F1-2008-0007 July 17, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 08-002-00 Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Entergy is hereby providing Licensee Event Report (LER) 08-002-00 for Waterford Steam Electric Station Unit 3. The LER is for a condition wherein one of four transmitters used in each Steam Generator for level protection was inoperable during Cycle 15 operation. This condition was a violation of Technical Specification Table 3.3-1, and the condition is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B).
This report contains no new commitments. Please contact Robert J. Murillo at (504) 739-6715 if you have questions regarding this information.
Sincerely, RJM/GCS/ssf
Attachment:
Licensee Event Report 08-002-00 A4IR
W3F1-2008-0007 Page 2 (w/Attachment) cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington,' TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 R.K. West, lerevents@inpo.org - INPO Records Center
Attachment W3FI-2008-0007 Licensee Event Report 08-002-00
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- 3. PAGE Waterford 3 Steam Electric Station 05000382 1 oF 3
- 4. TITLE Inoperable Steam Generator Narrow Range Level Channels
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED 1FAACIITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIALMR REV MONTH DAY YEAR.
FAI NAME NUMBERTNO NA ME
_l FACILITY NAME DOCKET NUMBER 05 23 2008 2008 - 002 - 00 07 17 2008 NA 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
ED 20.2201(b)
ED 20.2203(a)(3)(i)
[-:. 50.73(a)(2)(i)(C)
EW 50.73(a)(2)(vii) 6 ED 20.2201(d)
ED 20.2203(a)(3)(ii)
[: 50.73(a)(2)(ii)(A)
ED 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[]
20.2203(a)(2)(i)
ED 50.36(c)(1)(i)(A)
[D 50.73(a)(2)(iii)
EW 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E] 20.2203(a)(2)(ii)
[W 50.36(c)(1)(ii)(A)
E] 50.73(a)(2)(iv)(A)'
50.73(a)(2)(x)
E] 20.2203(a)(2)(iii)
ED 50.36(c)(2) -
17 50.73(a)(2)(v)(A)
D 73.71(a)(4) 0
[] 20.2203(a)(2)(iv)
D-50.46(a)(3)(ii)
W '50.73(a)(2)(v)(B)
El 73.71(a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
Ej 50.73(a)(2)(v)(C)
S c
OTHER Specify in Abstract below Dr inl
__ 20.2203(a)(2)(vi)
E 50.73(a)(2)(i)(B)
E:1 50.73(a)(2)(v)(D)
REPORTABLE OCCURRENCE.
On May 23, 2008, one transmitter for SG 1 and one transmitter for SG 2 used for narrow range level PPS trip input were determined to be inoperable. The transmitters were out of calibration and inoperable during Cycle
- 15. Technical Specification Table 3.3-1, Action 2, requires that with the number of channels operable one less than the total number of channels, which are four per Steam Generator, startup or power operation may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Plant personnel were unaware of this condition during Cycle 15, and therefore did not place the inoperable channels in the bypass or tripped condition per the Technical Specification. This condition constituted a violation of Technical Specification Table 3.3-1, and the condition is reportable within 60 days pursuant to 1 OCFR 50.73(a)(2)(i)(B).
INITIAL CONDITIONS At the time the two SG level transmitters were determined to be inoperable, the plant was in Mode 6 refueling. There were no other structures, systems, or-components inoperable at the time of discovery that contributed to this condition.
EVENT DESCRIPTION
On May 8, 2008, maintenance was being performed per procedures MI-003-005 and MI-003-006, Steam Generator Level Loop Check and Calibration for SG 1 and SG 2 respectively. During the performance of the maintenance, personnel discovered that one transmitter for SG 1 and one transmitter for SG 2 used for SG narrow range level PPS trip input were out of calibration. On May 23, 2008, evaluation established the two transmitters were inoperable during Cycle 15 operation.
CAUSAL FACTORS During RF14 seven of the eight SG level transmitters used for PPS trip input were replaced for SG 1 and SG
- 2. The transmitters were replaced by temporary outage workers. The one SG narrow range transmitter that was not replaced remained in calibration during Cycle 15 operation. The Apparent Cause Evaluation established the condition occurred due to procedural inadequacy as the procedures did not provide sufficient detail to assure proper manipulations of valves and venting of sensing lines after installation of the seven SG narrow range transmitters.
CORRECTIVE ACTIONS
Corrective actions taken include:
" An Apparent Cause Evaluation, documented in condition report CR-WF3-2008-2107, was performed.
" A Failure Modes and Effects Evaluation was performed.
The seven SG narrow range transmitters were calibrated.
" A Corrective Action Program (CAP) action was issued to revise calibration procedures.
" A CAP action was issued to enhance the training for temporary outage workers in the calibration of transmitters.
SAFETY SIGNIFICANCE
V The condition described in this LER has minimal safety significance.
The SG narrow range level transmitters provide inputs to the PPS safety channels to actuate two PPS functions: (1) initiate reactor trip on SG high level and (2) initiate reactor trip and Emergency Feedwater Actuation Signal (EFAS) on low SG level. Evaluation of the safety analysis and setpoints established that the PPS analytical limit for EFAS on low SG level could not have been exceeded based on the degree of the out of calibration of the transmitters. The evaluation established the analytical limit for the PPS limit for high SG level could have been exceeded based on the magnitude of the out of calibration condition. The SG high level PPS trip is an equipment protection trip 6nd not a safety function trip. The SG high level PPS trip prevents excessive moisture carryover from the steam generator [SB] from reaching the turbine [TA], which could result in damage to the turbine. Three of thefour SG narrow range channels were available and operable during Cycle 15 operation. Two SG narrow range channels are required to generate a reactor trip.
There was a zero percent delta Core Damage Frequency, or no increase in core damage probability, with j both transmitters not operable. This condition did not exceed the NRC Green criteria of <10-6 per year.
SIMILAR EVENTS
A record search was performed for other similar reported conditions at Waterford 3. No similar conditions were identified and reported over the last 3 year period.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes are identified in the text within brackets [I.