Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: 2CAN010401, Arkansas, Unit 2 - License Renewal Application Clarifications, 2CAN020502, License Renewal Clarification, Arkansas Nuclear One - Unit 2, 2CAN030401, License Renewal Application Clarifications, Arkansas Nuclear One - Unit 2, 2CAN070409, Unit 2, License Renewal Application Clarifications, 2CAN080401, Unit 2, License Renewal Application Clarifications, 2CAN090402, Unit 2, License Renewal Application Clarifications, 2CAN100302, License Renewal Application, Attachment a - E, ML040900270
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MONTHYEAR2CAN100302, License Renewal Application, Attachment a - E2003-10-14014 October 2003 License Renewal Application, Attachment a - E Project stage: Other ML0407706112003-12-22022 December 2003 E-Mail MSIV Leakage Pathway RAI & License Amendment Request - Attachment 3 Project stage: Request ML0407706062003-12-22022 December 2003 E-mail Draft Proposed Emergency Changes to Technical Specifications 3.8.1.1 to Support Steam Diesel Generator Inspections - Attachment 4 Project stage: Request ML0407705992003-12-22022 December 2003 Draft Information Input Configuration Risk Management Program - Attachment 5 Project stage: Request ML0407705932003-12-23023 December 2003 Draft Information Request PRA Analysis Assessment PRA-03-024, Rev. 0 - Attachment 6 Project stage: Request ML0407705842003-12-28028 December 2003 Draft Information Input Material Discussion - Attachment 8 Project stage: Request 2CAN010401, Arkansas, Unit 2 - License Renewal Application Clarifications2004-01-22022 January 2004 Arkansas, Unit 2 - License Renewal Application Clarifications Project stage: Other ML0406105422004-02-26026 February 2004 & 12/16/2003 Summary of Telephone Calls with Entergy Operations Incorporated Regarding Draft Responses to Questions Pertaining to the Arkansas Nuclear One, Unit 2 License Renewal Application Project stage: Draft Other ML0407104662004-03-0808 March 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI 2CAN030401, License Renewal Application Clarifications, Arkansas Nuclear One - Unit 22004-03-24024 March 2004 License Renewal Application Clarifications, Arkansas Nuclear One - Unit 2 Project stage: Other ML0409002702004-03-29029 March 2004 Summary of Telephone Call Between U.S. Nuclear Regulatory Commission (NRC) and Entergy Operations Incorporated Concerning Questions Pertaining to Aging Management Review for Arkansas Nuclear One, Unit 2 LRA Project stage: Other 2CAN040401, Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB84022004-04-0606 April 2004 Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB8402 Project stage: Request ML0409902302004-04-0808 April 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0410508202004-04-13013 April 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0408206822004-04-13013 April 2004 Draft Information Input, Memo from 12/2/03 to 12/28/03 Project stage: Request ML0410508582004-04-14014 April 2004 Request for Additional Information, Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0412003842004-04-23023 April 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0412805542004-05-0505 May 2004 RAI, License Renewal Application, Section 3.3 Auxiliary Systems Project stage: RAI ML0413304862004-05-11011 May 2004 Request for Additional Information for Arkansas Nuclear One-Unit 2 License Renewal Application from Plant Systems Branch Division of Systems Safety and Analysis Docket No. 50-368 Project stage: RAI 05000368/LER-2004-001, Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation2004-05-17017 May 2004 Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation Project stage: Request ML0413802842004-05-17017 May 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application (Tac No. MB8402) Project stage: RAI 2CAN050404, Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN050401, Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN050403, Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN050402, Arkansas, Unit 2, Request for Additional Information Response for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2, Request for Additional Information Response for License Renewal Application Project stage: Request 2CAN050407, Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB84022004-05-24024 May 2004 Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB8402 Project stage: Request ML0414700212004-05-25025 May 2004 Request for Additional Information for Review of Arkansas Nuclear One, Unit 2, License Renewal Application - DE Eeib Mcconnell Knox Project stage: RAI ML0414801342004-05-26026 May 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application (Tac No. MB8402) Project stage: RAI 2CAN060401, Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application2004-06-10010 June 2004 Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request ML0416202472004-06-11011 June 2004 Request for Additional Information, Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI 2CAN060403, Unit 2 - Request for Additional Information Responses for License Renewal Application TAC No. MB84022004-06-16016 June 2004 Unit 2 - Request for Additional Information Responses for License Renewal Application TAC No. MB8402 Project stage: Request ML0417305712004-06-21021 June 2004 Summary of Telephone Call with Entergy Operations, Inc., Representatives Regarding Draft Request for Additional Information Pertaining to the Arkansas Nuclear One, Unit 2 License Renewal Application Project stage: Draft RAI ML0417305262004-06-21021 June 2004 & 04/16/2004 Summary of Telephone Calls Between the U.S. NRC Staff and Entergy Operations, Inc., Representatives Concerning Draft Request for Additional Information Pertaining to the Arkansas Nuclear One Project stage: Draft RAI ML0417700372004-06-23023 June 2004 & 05/27/2004, Summary of Telephone Calls Held Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Entergy Operations, Inc., Representatives Concerning Drai Pertaining to the Arkansas One, Unit 2, License Renewal Application Project stage: RAI ML0417705572004-06-24024 June 2004 Request for Additional Information, Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI 2CAN070404, Unit 2, Request for Additional Information Responses for License Renewal Application2004-07-0101 July 2004 Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request ML0419602602004-07-14014 July 2004 Summary of Telephone Conference Call Held on June 30, 2004, Between NRC and Entergy Representatives Concerning Request for Additional Information Pertaining to the Arkansas Nuclear One, Unit 2, LRA Project stage: RAI ML0421603562004-07-22022 July 2004 Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN070409, Unit 2, License Renewal Application Clarifications2004-07-22022 July 2004 Unit 2, License Renewal Application Clarifications Project stage: Other 2CAN070406, Unit 2, Request for Additional Information Responses for License Renewal Application2004-07-22022 July 2004 Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN080401, Unit 2, License Renewal Application Clarifications2004-08-18018 August 2004 Unit 2, License Renewal Application Clarifications Project stage: Other ML0423703952004-08-23023 August 2004 Summary of Telephone Conference Held on July 28, 2004, Between the USNRC and Entergy Operations, Inc., Concerning a Request for Additional Information Pertaining to the Arkansas Nuclear Station, Unit 2, License Renewal Application Project stage: RAI ML0423806322004-08-25025 August 2004 Summary of Telephone Call Held on July 7 and 8, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Entergy Operations Inc., Representatives Concerning Request for Additional Information Pertaining to the Arkansas Nuclear O Project stage: RAI 2CAN090402, Unit 2, License Renewal Application Clarifications2004-09-10010 September 2004 Unit 2, License Renewal Application Clarifications Project stage: Other ML0427406512004-09-30030 September 2004 Summary of Telephone Calls Held on August 26 and September 1, 2004, Between the U.S. NRC Staff and Entergy Operations Inc., Representatives Concerning RAI Pertaining to the Arkansas Nuclear One, Unit 2 LRA Project stage: RAI ML0427406292004-09-30030 September 2004 Summary of Telephone Call Held on August 24, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Entergy Operations Inc., Representatives Concerning Request for Additional Information Pertaining to the Arkansas Nuclear One, Project stage: RAI 2CAN120403, License Renewal Application Draft Safety Evaluation Report Comments2004-12-0909 December 2004 License Renewal Application Draft Safety Evaluation Report Comments Project stage: Draft Other 2CAN020502, License Renewal Clarification, Arkansas Nuclear One - Unit 22005-02-28028 February 2005 License Renewal Clarification, Arkansas Nuclear One - Unit 2 Project stage: Other 2004-05-24
[Table View] |
LER-2004-001, Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation |
| Event date: |
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| Report date: |
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| 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 |
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| 3682004001R00 - NRC Website |
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text
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Entergy Entergy Operations, Inc.
144 S.R. 333 Russeliville, AR 72802 Tel 501 858 5000 2CAN050406 May 17, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OPl-17 Washington, DC 20555
Subject:
Licensee Event Report 50-368/2004-001-00 Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
In accordance with 10CFR50.73(a)(2)(i)(B), enclosed is the subject report concerning operation prohibited by technical specifications due to an inoperable channel of wide-range containment water level instrumentation.
New commitments contained in this submittal are summarized in Attachment 1.
Sincerely,
/Dale
.James
( Ma tager, Licensing DEJ/dh enclosure attachment
-- e-cq" -
2CAN050406 Page 2 cc:
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 LEREvents@inpo.org 2CAN050406 Commitment Summary to 2CAN050406 Page 1 of I This table identifies actions discussed in this letter for which Entergy Operations, Inc.
(Entergy) commits to perform. Any other actions discussed in this submittal are described for the NRC's information and are not commitments.
TYPE ONE-TIME CONTINUING SCHEDULED
COMMITMENT
ACTION COMPLIANCE COMPLETION DATE A protective cover will be X
August 31, 2004 installed over the wide-range containment water level power switch to minimize the likelihood of inadvertent movement.
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30.2001 (1-.201)
COMMISSION Estimated burden per response to comply with this mandatory Information collection request 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Send comments regarding LICENSEE EVENT REPORT (LER) burden estimate to the Records Management Branch (T-6 E6), U.S.
I Nuclear Regulatory Commission, Washington. DC 20555-0001, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and Budget.
l__
lWashington, DC 20503.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Arkansas Nuclear One -
Unit 2
- - IF 05000368 1 OF 4 TITLE (4) Operation Prohibited by Technical Specifications due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation EVENT DATE (5)
LER NUMBER (6) l REPORT DATE (7) l OTHER FACILITIES INVOLVED (8)
SEOUENTAL REV FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR FACILITY NAME DOCKET NUMBER 03 16 2004 2004 001 00 05 17 2004 OPERATING 1 1
THISREPORTISSUBMITTEDPURSUANTTOTHE REQUIREMENTSOF10CFR:
(Checkoneormore) (11)
MODE (9) 1 l
20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
POWER l
20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A)
LEVEL (10) l100 I 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) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) l 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) l 50.36(c)(2) l 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 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract l
lllll=
(17)
A.
Plant Status At the time this condition was discovered, Arkansas Nuclear One, Unit 2 (ANO-2) was operating in Mode 1 at 100 percent power.
B.
Event Description
On March 16, 2004, while performing shiftly rounds, a waste control operator (WCO) found the power switch for Wide-Range Containment Water Level Transmitter 2LT-5645-1 [IP] in the off position and the power indicating light extinguished.
The switch being in the off position rendered the associated control room level indication and chart recorder inoperable.
Control room personnel directed the WCO to place the switch in the correct position, thus restoring power to the level transmitter.
A review of plant data indicated that the power switch had been turned off on October 9, 2003, during the latter part of the previous refueling outage while the plant was in Mode 5. The condition was not detected during subsequent mode changes associated with plant heatup and power operation, and remained undetected until March 16, 2004.
ANO-2 technical specifications (TS) require two channels of wide-range containment water level indication to be operable in Modes 1, 2 and 3 to provide for post accident monitoring.
The loss of one channel of wide-range containment water level indication resulted in operation prohibited by TS.
Prior to heatup from the refueling outage, operability of the wide-range containment level instrumentation was verified by comparing control board indication of the two channels.
The wide-range containment water level indication is a measurement of the water level above the containment floor elevation. Water level in this range is not expected unless post-accident conditions are present.
Normal control board indication is at the bottom of the scale or zero inches.
Control board indication is not lost when level transmitter power is turned off, but fails low to zero inches; therefore, visual observation of the control board indication was inadequate to detect this condition.
The monthly channel check of containment level instrumentation was performed multiple times with satisfactory results during the period of time that the level instrumentation was inoperable.
AL. a ULr I 1 (17)
C.
Root Cause An investigation of this condition did not reveal any activity that would explain why the power switch for Level Transmitter 2LT-5645-1 was turned off.
Subsequent to the last calibration, performed on March 21, 2003, no surveillances or maintenance activities were identified that would have required manipulation of the toggle switch.
During the refueling outage, many personnel passed by the power switch due to its location in the exit path from the containment building.
It is likely that on October 9, 2003, the power switch was accidentally bumped into the off position by personnel exiting the containment building.
There was no physical barrier to protect against accidental repositioning of the power switch.
At the time this event occurred, there was no requirement to verify the position of the level transmitter power switch.
The method of performing the monthly channel check for wide-range containment water level indication was inadequate to identify this condition.
D.
Corrective Actions
The power switch for Wide-Range Containment Water Level Transmitter 2LT-5645-1 was returned to the correct position, restoring operability of the level indication instrumentation and TS compliance.
A verification of the power switch position for level transmitter 2LT-5645-1 has been added to the ANO-2 operator channel check log.
This requirement extends to other switches for wide-range containment water level transmitters that have a similar vulnerability to inadvertent repositioning.
A similar requirement to verify power switch positions has been added to ANO-1 operator logs.
In addition to the existing channel checks for control room level instrumentation, the methodology for performing monthly post-accident channel checks has been revised to include verification of the power switch position and local indication.
1 (1 7)
A protective cover will be installed over the containment wide-range water level transmitter power switch to minimize the likelihood of inadvertent movement of the switch.
E.
Safety Significance
The containment wide-range water level transmitters provide indication of containment conditions post-accident.
The unavailability of one indication due to its power switch being off does not adversely impact the actions dependent on these indications.
The loss of level indication has no impact on reactor coolant system [AB] leakage detection and is limited to determining the amount of water in the containment building.
In post-accident conditions, the wide-range containment water level indication is used along with other indications to determine if a loss-of-coolant accident occurred inside or outside of containment.
The wide-range level instrumentation does not provide input to any annunciators or alarms.
For these reasons, the safety significance of this condition was determined to be minimal.
F.
Basis for Reportability This report of operation prohibited by TS is submitted in accordance with 10CFR50.73(a)(2)(i)(B).
G.
Additional Information
There have been no previous similar events reported by ANO as Licensee Event Reports.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
ILA I UrNT 1
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| 05000313/LER-2004-001-01, Arkansas Unit 1, on 04/29/2004, Operation Prohibited by Tech Specs Due to Undetected Inoperable Channel of Required Source Range Nuclear Instrumentation During Core Alterations Caused by a Signal Processing Unit Circuit Brea | Arkansas Unit 1, on 04/29/2004, Operation Prohibited by Tech Specs Due to Undetected Inoperable Channel of Required Source Range Nuclear Instrumentation During Core Alterations Caused by a Signal Processing Unit Circuit Breaker Failure | 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), 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) | | 05000368/LER-2004-001, Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation | Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation | 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) | | 05000368/LER-2004-002, Unit 2, Regarding Operation Prohibited by Technical Specification Due to an Inoperable Containment Cooling Fan Resulting from the Failure to Perform an Adequate Verification and Post-Maintenance Test | Unit 2, Regarding Operation Prohibited by Technical Specification Due to an Inoperable Containment Cooling Fan Resulting from the Failure to Perform an Adequate Verification and Post-Maintenance Test | 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) | | 05000313/LER-2004-002, Arkansas, Unit 1 Re Operation Prohibited by Technical Specifications Due to Degradation of a Principal Safety Barrier Caused by Primary Water Stress Corrosion Cracking of a Control Rod Drive Mechanism Nozzle | Arkansas, Unit 1 Re Operation Prohibited by Technical Specifications Due to Degradation of a Principal Safety Barrier Caused by Primary Water Stress Corrosion Cracking of a Control Rod Drive Mechanism Nozzle | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000368/LER-2004-003, Regarding Entry Into an Operational Mode Prohibited by Technical Specification Due to Inoperable Pressurizer Proportional Heaters | Regarding Entry Into an Operational Mode Prohibited by Technical Specification Due to Inoperable Pressurizer Proportional Heaters | 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) |
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