05000382/LER-2013-003, Regarding Failure to Test Manual Handwheels on Air Operated Valves
| ML13204A043 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/22/2013 |
| From: | Pellegrin B Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1-2013-0033 LER 13-003-00 | |
| Download: ML13204A043 (15) | |
| 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) 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)(ix) 10 CFR 50.73(a)(2)(i) 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)(i)(A), Completion of TS Shutdown |
| 3822013003R00 - NRC Website | |
text
10 CFR 50.73 W3F1-2013-0033 July 22, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 2013-003-00 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) 2013-003-00 for Waterford Steam Electric Station Unit 3. This report provides details associated with failure to test the local manual operation on several air operated valves and the failure of three of those valves to operate locally by hand. Based on plant evaluation, it was determined that this condition is reportable under: 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(ii)(b), 10 CFR 50.73(a)(2)(v)(B), 10 CFR 50.73(a)(2)(v)(D), 10 CFR 50.73(a)(2)(vii), and 10 CFR 50.73(a)(2)(ix).
This report contains no new commitments. Please contact Bryan J. Pellegrin at (504)739-6203 if you have questions regarding this information.
Sincerely,
Attachment:
Licensee Event Report 2013-003-00 Bryan J. Pellegrin Licensing Manager - Acting Waterford 3 Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504 739 6203 Fax 504 739 6698 bpelleg@entergy.com
W3F1-2013-0033 Page 2 cc:
Mr. Arthur T. Howell, III Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4125 RidsRgn4MailCenter@nrc.gov NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 Marlone.Davis@nrc.gov U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Kaly.Kalyanam@nrc.gov
Attachment to W3F1-2013-0033 Licensee Event Report 2013-003-00
NRC FORM 366 (10-2010)obo-3 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 10/31/2013
, 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 12
- 4. TITLE Failure to Test Manual Handwheels on Air Operated Valves
- 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 11 16 2012 2013 - 003 - 00 7
22 2013 FACILITY NAME DOCKET NUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
Defueled 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 000 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER Specify in Abstract below or in In the Waterford PRA model, the only local manipulation of air operated valves using the valve handwheels that is credited is for the EFW flow control valves during loss of motive air or loss of DC power (including Station Blackout (SBO) scenarios). Because SBO scenarios account for almost half of the total plant CDF, the overall result should be the most sensitive to changes made in this part of the model.
The original model included the two local manual actions to control EFW flowQHFEFWFLOP and QHFEFWSBOR. The latter is specific to SBO sequences while the former is related to loss of control of EFW. For this evaluation, the handwheel failures need to be modeled separately from the human failure event. In the cases with the QHFEFWSBOR event, the logic for the handwheel failures was modeled with an OR gate relating it to the Human Failure Event (HFE). Because the HFE included the manipulation of the steam supply valve to the EFW pump turbine as well as the EFW flow control valves, a hardware failure for the steam supply valve was added with the handwheel logic using a generic failure rate.
For the case involving the other local manual action, QHFEFWFLOP, an additional operator action QHFEFWTOSP had to be added to the fault tree logic to account for manual control of the EFW AB turbine steam supply valve and would only be applicable for Transient initiators (non-LOCA). Hardware failure for the EFW AB turbine steam supply valve was also taken into account.
The baseline CDF for this case was computed to be 3.68E-06/ year when using a truncation in EOOS of E-11. The resulting CDF from having the manual hand-wheels inoperative (as described above) is 3.78E-06/ year giving a delta CDF of 1.0E-07/ year. Applying the Average Weather factor of 1.33 to this delta renders a final delta CDF of 1.33E-07/year. Multiplying this result by the exposure time of one year gives and Incremental Core Damage Probability (ICDP) of 1.33E-07 (ICDP = deltaCDF
- exposure time). To account for the contribution from Fire and External Events, this number is assumed to be doubled. This gives a total ICDP of 2.7E-07 which is low safety significance.
Therefore, the risk significance associated with this reported condition is considered low.
SIMILAR EVENTS
A search was performed using the NRCs ADAMS search engine for other similar reported events at Waterford 3. No similar events were identified.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes and component function identifiers are identified in the text with brackets [ ].
Reporting Date Discussion The difference between the event date and report date exceeds 60 days because this condition was not recognized as a reportable condition until another review was performed of the available information.
This condition was determined to be reportable on May 23, 2013. Failure to submit LER 2013-003-00 within 60 days has been entered into the corrective action program in CR-WF3-2013-2564.