05000382/LER-2011-004, Regarding Vendor Notification of Non-Conforming Part Renders Both Trains of QSPDS Inoperable
| ML11272A035 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/26/2011 |
| From: | Steelman W Entergy Nuclear South |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2011-0071 LER 11-004-00 | |
| Download: ML11272A035 (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)(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 |
| 3822011004R00 - NRC Website | |
text
Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 wsteelm@entergy.com William J. Steelman Licensing Manager Waterford 3 W3F1-2011-0071 September 26, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 2011-004-00 Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Entergy is hereby submitting Licensee Event Report (LER) 2011-004-00 for Waterford Steam Electric Station Unit 3. This report provides details associated with the vendor notification of non-conforming part which rendered both trains of the Qualified Safety Parameter Display System (QSPDS) inoperable.
Based on this vendor notification and subsequent plant evaluation, it was determined that this condition is reportable under 10CFR50.73(a)(2)(i)(B) requirements.
This report contains no new commitments. Please contact William J. Steelman at (504) 739-6685 if you have questions regarding this information.
Sincerely, WJS/WH
Attachment:
Licensee Event Report 2011-004-00
W3F1-2011-0071 Page 2 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 RidsRgn4MailCenter@nrc.gov Marlone. Davis@nrc.gov Dean.Overland@nrc.gov Kalv. KalvanamO.nrc.qov INPO Records Center lerevents@inpo.org
Attachment to W3FI-2011-0071 Licensee Event Report 2011-004-00 (This attachment contains 4 pages)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 1013112013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Waterford 3 Steam Electric Station 05000 382 1 OF 4
- 4. TITLE Vendor Notification of Non-Conforming Part Renders Both Trains of QSPDS Inoperable S. EVENT DATE
- 6. LER NUMBER 7 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV YEAR FACILITY NAME DOCKET NUMBER MOT AY YA YA NUMBER' NO MONTH DA05 0
7NAiL O
DAYE YEARE 05000 R
07 27 2011 2011 - 004 - 00 09 26 2011 05000
- 9.
OPERATING ZMODFCLEYNM DCE NME O11.
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[1 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201 (d)
El 20.2203(a)(3)(ii) 0] 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
ED 20.2203(a)(1)
EW 20.2203(a)(4)
ED 50.73(a)(2)(ii)(B)
E] 50.73(a)(2)(viii)(B)
E_ 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
ED 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[] 20.2203(a)(2)(ii)
E] 50.36(c)(1)(ii)(A)
LI 50.73(a)(2)(iv)(A)
FI 50.73(a)(2)(x)
El 20.2203(a)(2)(iii) 17 50.36(c)(2)
[] 50.73(a)(2)(v)(A)
DI 73.71 (a)(4) 1E00 L 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 0l 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[L 50.73(a)(2)(v)(C)
E] OTHER Specify in Abstract below or in E] 20.2203(a)(2)(vi)
Z 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
REPORTABLE OCCURRENCE An undersized power supply harness for the Qualified Safety Parameter Display System (QSPDS)[IP] was installed as a replacement on both safety related trains from August 2009 until July 2011. The Technical Specification (TS) allowed outage time (AOT) was seven days. This created a condition of past inoperability for both safety related trains.
This condition is reportable under 10CFR50.73(a)(2)(i)(B), operation or condition prohibited by Technical Specifications, within 60 days as a Licensee Event Report (LER).
INITIAL CONDITIONS QSPDS is a safety related, class 1 E microprocessor based display system utilized at W3 that meets the regulatory requirements for accident monitoring and assessment. Instrumentation systems such as the Saturation Margin Monitor, the Core Exit Thermocouples (CETs), and the Reactor Vessel Level Monitoring System (RVLMS) provide the necessary plant parameter inputs to QSPDS. QSPDS has two redundant channels of instrumentation and can perform its function coincident with any postulated single failure.
EVENT DESCRIPTION
On July 27, 2011, W3 received Westinghouse Nuclear Safety Advisory Letter NSAL-1 1-3 (dated July 15, 2011) which informed Waterford that a power supply harness for the QSPDS may be undersized in current carrying capacity. The concern identified is that the new cable harness, part number 6D30323G01, may not be able to handle the current to which it is exposed by these systems under all environmental conditions.
As stated in the Westinghouse letter, the vulnerability of QSPDS to this condition is subject to the actual loading on the QSPDS chassis and ambient temperature. At an ambient temperature of 137 degrees F, the highest load that the harness could support without exceeding the manufacturer's rating of the Molex connector would be 5.5 A. At an ambient temperature of 20 degrees C, the current harness could support 11 A without exceeding the manufacturer's temperature rating. Westinghouse has also run engineering tests with the harness loaded to 18 A and 30 A. The testing revealed that, although the connector did see significant temperatures, it did not melt or start a fire.
There are two power supplies feeding each channel of QSPDS for a total of four power supplies. The harness provides power from the power supply to the components in the QSPDS chassis. The suspect harness has been installed in three of the four power supplies. The power supply replacement for Channel 2 was in February 2007 and power supply replacement for Channel 1 was in August 2009.
This condition was entered into the corrective action program as Condition Report CR-WF3-2011-5327.
An immediate operability assessment was performed. As a result, both channels of QSPDS were declared inoperable. Since CET indication is dependent on QSPDS operability, the CETs were also declared inoperable.
Technical Specification (TS) 3.3.3.6 requires the accident monitoring instrumentation channels (including QSPDS) to be OPERABLE in MODES 1, 2, and 3.
No actual failure occurred.
It was also apparent that the same condition rendered both channels of QSPDS inoperable since August 2009 when the suspect power supply harness was installed in the second of the two channels.
CAUSAL FACTORS W3 was notified by letter of a non-conforming replacement part procured from Westinghouse. W3 evaluation of the condition resulted in declaring both channels of QSPDS inoperable. W3 expeditiously performed the recommended repair to restore full operability to QSPDS.
CORRECTIVE ACTIONS
The same Westinghouse letter recommended instillation of a jumper to restore full current carrying capacity. This was performed by site maintenance personnel to both QSPDS channels on July 29, 2011 (CR-WF3-2011-5327 CA-5). This restored operability to both QSPDS channels.
SAFETY SIGNIFICANCE
The safety significance evaluates the limiting design basis accidents with respect to the potentially lost QSPDS indications. The only instrumentation not already supplied by other safety related indications is the QSPDS CETs, RVLMS, and saturation margin.
In the event that the QSPDS was lost, the failure described would not impact the reactor protection system (RPS). Operators could obtain hot leg temperature and pressurizer pressure from the RPS and/or plant process computer, depending on plant configuration, and manually calculate subcooled margin. By reviewing available hot leg temperature, the operators would have a back-up means for approximating CET data and reactor vessel level, based on hot leg temperature and pump flow rates. Hot leg temperature would also provide a coarse means of measuring CET temperatures. In addition, CET voltage information is available in the control room envelope cabinets such that in the longer term CET signal voltages could be correlated to CET temperatures.
The most limiting design basis accident that results in decrease in reactor vessel level and increase in CET temperature is the Loss of Coolant Accident (LOCA). Therefore, post-LOCA reactor vessel level and CET temperatures obtained from QSPDS are used in the LOCA Emergency Operating Procedure (EOP). Waterford 3 design basis post-LOCA Emergency Core Cooling System (ECCS) performance analyses is provided in Updated Final Safety Analysis Report (UFSAR) Section 6.3. The regulatory acceptance criteria for post-LOCA Emergency Core Cooling System (ECCS) are documented in 10CFR50.46. The ECCS performance analyses includes large break LOCA (LBLOCA), small break LOCA (SBLOCA) and long term cooling (LTC) analyses.
Waterford 3 analyses have demonstrated that the criteria of 1 OCFR50.46 are met for both large and small break LOCA. The post-LOCA short term cooling requirement, long term cooling requirement, required manual actions and post-LOCA instrumentation is listed in UFSAR 6.3 and does not specifically reference QSPDS RVLMS, CET, or saturation margin indications. The EOPS do use QSPDS indications to provide operations with additional decision making indications. The alternate QSPDS indications using hot leg temperature, pressurizer pressure, and pump flow rates could be used to provide the EOP information. Therefore, failure of QSPDS would not pose a significant impact on the post-LOCA short term and long term cooldown and would have low safety significance.
SIMILAR EVENTS
None.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes are identified in the text within brackets [].