Letter Sequence Request |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement
Results
Other: L-2012-309, FPL Review Comments on Extended Power Uprate Safety Evaluation, L-2012-382, Extended Power Uprate Cycle 24 Startup Report, ML11119A084, ML11119A085, ML112360230, ML12053A345, ML12165A511, ML12191A236, ML12194A287, ML12195A168
|
MONTHYEARL-2010-259, St. Lucie, Unit 1 - Transmittal of Affidavits from Westinghouse, Areva and Caldon Ultrasonica Technology Center Re License Amendment Request for Extended Power Uprate2010-11-22022 November 2010 St. Lucie, Unit 1 - Transmittal of Affidavits from Westinghouse, Areva and Caldon Ultrasonica Technology Center Re License Amendment Request for Extended Power Uprate Project stage: Request L-2010-302, License Amendment Request for Extended Power Uprate2010-12-15015 December 2010 License Amendment Request for Extended Power Uprate Project stage: Request L-2011-021, License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups2011-02-25025 February 2011 License Amendment Request for Extended Power Uprate, Attachment 8; Core Operating Limits Report (COLR) Markups Project stage: Request ML1107302822011-02-25025 February 2011 License Amendment Request for Extended Power Uprate, Attachment 2; Supplemental Environmental Report Project stage: Supplement ML1105906632011-03-0909 March 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review ML1110100982011-04-19019 April 2011 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI ML1113200042011-05-12012 May 2011 EPU - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Project stage: Acceptance Review NRC-2011-0128, St. Lucie, Unit 1 - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Documents Access to Sensitive Unclassified Nonsafeguards Information2011-06-0202 June 2011 St. Lucie, Unit 1 - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Documents Access to Sensitive Unclassified Nonsafeguards Information Project stage: Approval ML11119A0852011-06-0202 June 2011 Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Documents Access to Sensitive Unclassified Nonsafeguards Information Project stage: Other ML11119A0842011-06-0808 June 2011 Transmittal Letter - Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non Safeguards Information Project stage: Other ML11173A1042011-06-23023 June 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review ML12037A1472011-07-21021 July 2011 NRR E-mail Capture - EFH Species for St. Lucie Project stage: Request NRC-2011-0190, St. Lucie Nuclear Plant, Units 1 and 2 - Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI2011-08-26026 August 2011 St. Lucie Nuclear Plant, Units 1 and 2 - Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Info Project stage: Approval ML11208B6442011-08-26026 August 2011 Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Information Project stage: Other ML11208B6422011-09-0101 September 2011 Transmittal Letter - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Information Project stage: Other ML1123602302011-09-0202 September 2011 Request for Concurrence on List of Species with Essential Fish Habitat in the Vicinity of the St. Lucie Plant, Units 1 and 2 Project stage: Other L-2011-397, Unusual or Important Environmental Event - Reportable Fish Kill2011-09-20020 September 2011 Unusual or Important Environmental Event - Reportable Fish Kill Project stage: Request L-2011-413, Submittal of Attachment 2, Response to NRC Reactor Systems Branch Request for Additional Information Re Extended Power Uprate License Amendment Request2011-09-29029 September 2011 Submittal of Attachment 2, Response to NRC Reactor Systems Branch Request for Additional Information Re Extended Power Uprate License Amendment Request Project stage: Request L-2011-410, Environmental Protection Plan Report 316(b) Related Documentation2011-09-30030 September 2011 Environmental Protection Plan Report 316(b) Related Documentation Project stage: Request L-2011-450, Submittal of Final Revised Industrial Wastewater Facility Permit No. FL0002208, and Environmental Protection Plan Report2011-10-20020 October 2011 Submittal of Final Revised Industrial Wastewater Facility Permit No. FL0002208, and Environmental Protection Plan Report Project stage: Request 05000335/LER-2011-001, For St. Lucie, Unit 1, Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure Caused by Severe Influx of Jellyfish Into the Intake Structure2011-10-20020 October 2011 For St. Lucie, Unit 1, Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure Caused by Severe Influx of Jellyfish Into the Intake Structure Project stage: Request ML11332A0212011-12-28028 December 2011 Federal Register Notice - Draft Environmental Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Request ML11332A0202011-12-28028 December 2011 Transmittal Letter - Draft Environmental Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Other L-2011-566, Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-14014 January 2012 Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-043, Comment (1) of Richard L. Anderson, on Behalf of Florida Power & Light, Regarding Draft Environmental Assessment and Draft Finding of No Significant Impact Related the Proposed Extended Power Uprate2012-01-30030 January 2012 Comment (1) of Richard L. Anderson, on Behalf of Florida Power & Light, Regarding Draft Environmental Assessment and Draft Finding of No Significant Impact Related the Proposed Extended Power Uprate Project stage: Draft Other ML12044A1272012-02-13013 February 2012 Comment (2) from Edward W. Johnson Opposing NCR Permit Approval for St. Lucie 1 & 2 Project stage: Request ML12053A3452012-03-20020 March 2012 Request to Initiate Abbreviated EFH Consultation for Proposed Extended Power Uprate at St. Lucie Plant, Units 1 and 2 Project stage: Other L-2012-199, Response to Request for Additional Information on Draft Environment Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate2012-05-0202 May 2012 Response to Request for Additional Information on Draft Environment Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Response to RAI ML12132A0672012-05-0202 May 2012 NRR E-mail Capture - FW: St. Lucie Unit 1 and 2 EPU - Draft EA RAI Responses Project stage: Draft RAI ML12144A0082012-05-21021 May 2012 NRR E-mail Capture - FW: NRC St Lucie Plant; NMFS Comments Project stage: Request ML12144A3162012-05-23023 May 2012 NRR E-mail Capture - Federal Consistency Review Regarding the CZMA Project stage: Request ML12165A5112012-06-25025 June 2012 Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Other ML12165A5122012-06-25025 June 2012 Federal Register - Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Request L-2012-281, Retraction of Extended Power Uprate License Amendment Request Proposed Technical Specification Change Related to Emergency Diesel Generator Surveillance Requirements2012-07-0505 July 2012 Retraction of Extended Power Uprate License Amendment Request Proposed Technical Specification Change Related to Emergency Diesel Generator Surveillance Requirements Project stage: Request L-2012-274, Submittal of 120-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-07-0909 July 2012 Submittal of 120-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI ML12156A2082012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate Project stage: Approval ML12181A0192012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate (Redacted) Project stage: Approval ML12191A2362012-07-0909 July 2012 Technical Specification Pages Project stage: Other ML12194A2872012-07-12012 July 2012 Correction to Amendment No. 213 Regarding Extended Power Uprate Project stage: Other ML12195A1682012-07-13013 July 2012 Letters to H. Mueller, A. Hubbard, and S. Norton Re Environmental Assessment and Finding of No Significant Impact Related to Proposed Extended Power Uprate Project stage: Other L-2012-309, FPL Review Comments on Extended Power Uprate Safety Evaluation2012-08-0707 August 2012 FPL Review Comments on Extended Power Uprate Safety Evaluation Project stage: Other ML12235A4632012-09-24024 September 2012 Issuance of Amendment Regarding Extended Power Uprate Project stage: Approval ML12268A1672012-09-24024 September 2012 Public - Safety Evaluation Regarding Extended Power Uprate Project stage: Approval ML12268A1802012-09-24024 September 2012 Technical Specification Pages Regarding Extended Power Uprate Project stage: Other L-2012-382, Extended Power Uprate Cycle 24 Startup Report2012-10-19019 October 2012 Extended Power Uprate Cycle 24 Startup Report Project stage: Other 2011-09-29
[Table View] |
LER-2011-001, For St. Lucie, Unit 1, Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure Caused by Severe Influx of Jellyfish Into the Intake Structure |
| Event date: |
|
|---|
| Report date: |
|
|---|
| Reporting criterion: |
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
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
|---|
| 3352011001R00 - NRC Website |
|
text
FFPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 October 20, 2011 L-2011-454 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:
St. Lucie Unit I Docket No. 50-335 Reportable Event: 2011-001 Date of Event: August 22, 2011 Unit 1 Manual Reactor Trip Due To High Condenser Backpressure Caused by Severe Influx of Jellyfish into the Intake Structure The attached Licensee Event Report 2011-001 is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Very truly yours, Richard L. Anderso Site Vice President St. Lucie Plant RLA/dlc Attachment an FPL Group company
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 11o-2010)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear LICENSEE EVENT REPORT (LER)
Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects.resourse@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE St. Lucie Unit 1 05000335 1 OF 3
- 4. TITLE Unit 1 Manual Reactor Trip Due To High Condenser Backpressure Caused by Severe Influx of Jellyfish into the Intake Structure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV ONTH FACILITY NAME DOCKET NUMBER NUMBER NO.
M IFACILITY NAME DOCKET NUMBER 08 22 2012 2011 -
001 -
00 10 20 2011j
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[] 20.2201(b)
[l 20.2203(a)(3)(i)
[E 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
[1 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
[] 50.73(a)(2)(ii)(B)
[3 50.73(a)(2)(viii)(B)
__ 20.2203(a)(2)(i)
E] 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
Z 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
El 73.71(a)(4) 89 20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
[3 73.71(a)(5) 89%
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in Analysis of Safety Significance All safety related systems functioned as designed.
The plant response to the event was a manual reactor trip due to high backpressure-low vacuum.
The automatic turbine vacuum trip set point was never reached and conservative measures were taken before reaching automatic set points.
The plant was not at full power when the events occurred and a complete loss of condenser cooling did not occur.
There were no safety system actuations as a result of the trip.
Given the response of the plant and actions taken, the health and safety of the public was not affected by this event.
Over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> upon reactor trip, the conditional core damage probability (CCDP) and conditional large early release probability (CLERP) would reach 1.81E-09 and 1.55E-11, respectively.
These values are significantly below the threshold required by Regulatory Guide 1.174 for the risk to be "small" where CDP is below 1.OE-06 and LERP is below 1.OE-07.
This event is reportable under the requirements of 10 CFR 50.73(a) (2) (iv) (A) due to manual reactor protection system (RPS) actuation.
Corrective Actions
The corrective actions and supporting actions listed below are entered into the site corrective action program.
Any changes to the actions will be managed under the corrective action program.
- 1. Revise the circulating water off normal procedures to establish that the station will conduct a pre-emptive rapid downpower to the affected unit(s) in the event of a jellyfish, sea grass, or intake intrusion event that is occurring and meeting the specific criteria.
- 2.
Implement a design change to both St. Lucie units to upgrade existing traveling water screens to increase the capacity to help prevent future unplanned downpowers due to jellyfish and sea grass intrusion.
- 3.
Revise the intake intrusion monitoring and mitigation procedural guidance to include additional mitigation equipment checks and revise the threat assessment guideline to update action levels and response direction to reflect risk levels associated with the intrusion rate.
Similar Events
A search was performed using an industry database from 2006 to present.
Results identified five events similar to the circumstances of this jellyfish intrusion event.
A similar theme was challenges to traveling water screens required the tripping of circulating water pumps and down powering or tripping of the unit as a result of the decreased flow of circulating water.
Common corrective actions included procedure upgrades to reflect risk and actions to mitigate such a threat, increased monitoring and sampling.
Failed Components lB main feed pump lB condensate pump discharge check valve 1A2 traveling water screen
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000335/LER-2011-001, For St. Lucie, Unit 1, Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure Caused by Severe Influx of Jellyfish Into the Intake Structure | For St. Lucie, Unit 1, Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure Caused by Severe Influx of Jellyfish Into the Intake Structure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000389/LER-2011-001, Regarding Inadvertent Crosstie of Component Cooling Water (CCW) to Control Room A/C Units | Regarding Inadvertent Crosstie of Component Cooling Water (CCW) to Control Room A/C Units | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000335/LER-2011-002, Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure | Regarding Unit 1 Manual Reactor Trip Due to High Condenser Backpressure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000389/LER-2011-002, Regarding Unplanned Automatic Reactor Trip During Reactor Protection System Testing | Regarding Unplanned Automatic Reactor Trip During Reactor Protection System Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000335/LER-2011-003, Regarding Long-Term Post-LOCA Hot Leg Injection Single Failure Vulnerability | Regarding Long-Term Post-LOCA Hot Leg Injection Single Failure Vulnerability | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
|