IR 05000458/2009005

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Errata for River Bend Station - NRC Integrated Inspection Report 05000458-09-005
ML100540312
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/22/2010
From: Vincent Gaddy
NRC/RGN-IV/DRP/RPB-C
To: Mike Perito
Entergy Operations
References
IR-09-005
Download: ML100540312 (21)
v • d • e


Text

February 22, 2010

Michael Perito Vice President, Operations Entergy Operations, Inc. River Bend Station 5485 US Highway 61N St. Francisville, LA 70775

Subject: ERRATA FOR RIVER BEND STATION - NRC INTEGRATED INSPECTION REPORT 05000458/2009005

Dear Mr. Perito:

This errata corrects administrative errors that were in the original report. Please replace page 3 of the Summary of Findings, pages 29-31 of the Report Details, and pages A-2 through A-15 of the Supplemental Information in NRC Inspection Report 05000458/2009005, dated February 9, 2010, with the enclosed revised pages.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Vincent G. Gaddy, Chief

Project Branch C Division of Reactor Projects Docket: 50-458 License: NPF-47 Enclosure

Entergy Operations, Inc. - 2 - cc w/

Enclosure:

Senior Vice President Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995

Senior Vice President and COO Entergy Operations, Inc. P. O. Box 31995 Jackson, MS 39286-1995 Vice President, Oversight Entergy Operations, Inc.

P. O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Manager, Licensing Entergy Operations, Inc.

River Bend Station

5485 US Highway 61N St. Francisville, LA 70775 Attorney General State of Louisiana P. O. Box 94005 Baton Rouge, LA 70804-9005 Ms. H. Anne Plettinger 3456 Villa Rose Drive Baton Rouge, LA 70806 President of West Feliciana Police Jury P. O. Box 1921 St. Francisville, LA 70775 Mr. Brian Almon Public Utility Commission William B. Travis Building P. O. Box 13326 Austin, TX 78701-3326 Mr. Jim Calloway Public Utility Commission of Texas

1701 N. Congress Avenue Austin, TX 78711-3326 Louisiana Department of Environmental Quality Radiological Emergency Planning and Response Division P. O. Box 4312 Baton Rouge, LA 70821-4312 Associate General Counsel Entergy Nuclear Operations P. O. Box 31995 Jackson, MS 39286-1995 Chief, Technological Hazards Branch FEMA Region VI 800 N. Loop 288 Denton, TX 76201-3698

Entergy Operations, Inc. - 3 -

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov) Deputy Regional Administrator (Chuck.Casto@nrc.gov) DRP Director (Dwight.Chamberlain@nrc.gov)

DRP Deputy Director (Anton.Vegel@nrc.gov)

DRS Director (Roy.Caniano@nrc.gov)

DRS Deputy Director (Troy.Pruett@nrc.gov) Senior Resident Inspector (Grant.Larkin@nrc.gov)

Resident Inspector (Charles.Norton@nrc.gov) Branch Chief, DRP/C (Vincent.Gaddy@nrc.gov) RBS Administrative Assistant (Lisa.Day@nrc.gov)

Senior Project Engineer, DRP/C (Bob.Hagar@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov) Branch Chief, DRS/TSB (Michael.Hay@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

OEMail Resource ROPreports DRS STA (Dale.Powers@nrc.gov)

OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)

File located: R:\_REACTOR\RB\2009\ERRATA RBS2009005-RP-GFL.doc SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGG SRI:DRP/C C:DRP/C GFLarkin VGGaddy /RA/VGaddy for

/RA/ 2/22/10 2/22/10 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure Therefore, the event in the worst case would have been transparent to the core. Also, the displaced inventory posed no threat to any of the plant's mitigating systems. The inspectors concluded that the finding was of very low safety significance (Green). There is no crosscutting aspect associated with this violation because the finding does not reflect current licensee performance (Section 1R22). Cornerstone: Public Radiation Safety Green. The inspectors identified a noncited violation of 10 CFR 71.5 and 49 CFR 172.604(a) for a failure to ensure that the shift manager, whose phone number was listed as the required 24-hour emergency phone number on shipping documents, was knowledgeable about the radioactive waste shipment that left site on December 16, 2009, and had immediate access to a person who had specific information on the shipment. Specifically, the shift manager was listed as the required 24-hour contact; however, the shift managers (on multiple shifts) were not provided with documentation or information about the shipments that left the site on December 16, 2009. Although the shift manager would have eventually contacted a knowledgeable person, this delay would not have resulted in immediate access to the person with information related to the shipment. The licensee immediately provided the shift manager a copy of the shipping documentation, briefed the shift manager, and entered this issue into their corrective action program as Condition Report CR-RBS-2009-06419.

This performance deficiency was more than minor because it adversely affected the public radiation safety cornerstone to ensure adequate protection of public health and safety from exposure to radioactive materials released into the public domain in that the failure to have ship ment information immediately available could restrict the actions of fire department and/or rescue personnel responding to an accident. When processed through the Public Radiation Safety Determination Process, the finding was determined to be of very low safety significance because the finding: (1) was associated with radioactive material control, (2) involved the licensee's program for radioactive material transportation, (3) did not cause radiation limits to be exceeded, (4) did not involve a breach of package during transit, (5) did not involve a certificate of compliance finding, (6) did not involve a low level burial ground nonconformance, and (7) did not involve a failure to make notifications. The inspectors determined the finding had a crosscutting aspect in area of resources, associated with documentation, because the licensee's procedures did not provide guidance on informing the control room about shipments and thus, the procedures were not complete, accurate nor up-to-date H.2(c) (Section 2PS2).

.4 Selected Issue Follow-up Inspection a. Inspection Scope During a review of items entered in the licensee's corrective action program, the inspectors recognized a corrective action item documenting operator attempt to shift the reactor recirculation pumps from fast speed to slow during a plant shutdown for a refueling outage.

These activities constitute completion of one in-depth problem identification and resolution sample as defined in Inspection Procedure 71152-05.

b. Findings No findings of significance were identified. .5 In-depth Review of Operator Workarounds a. Inspection Scope An operator workaround is defined as a degraded or nonconforming condition that complicates the operation of plant equipment and is compensated for by operator action. During the week of November 2, 2009, the inspectors reviewed the cumulative effect of the existing operator workarounds and contingency plans. The inspectors concentrated on the effect the workarounds have on: (1) the reliability, availability, and potential for misoperation of any mitigating system; (2) whether they could increase the frequency of an initiating event; and (3) their effect on the operation of multiple mitigating systems. In addition, the inspectors reviewed the cumulative effects the operator workarounds have on the ability of the operators to respond in a correct and timely manner to plant transients and accidents. These activities constitute completion of one in-depth review of operator workarounds sample as defined in Inspection Procedure 71152-05.

b. Findings No findings of significance were identified. 4OA3 Event Follow-up (71153) .1 (Closed) Licensee Event Report 05000458/2009-002-00: Unplanned Manual Reactor Scram Following Trip of Both Reactor Recirculation Pumps On September 20, 2009, plant operators were reducing reactor power to begin a refueling outage. At 37 percent reactor power, the operators attempted to shift both reactor recirculation pumps from fast to slow speed. Reactor recirculation pump A shifted to slow speed, but tripped off approximately nine seconds later. Reactor recirculation pump B tripped off directly from high speed. The operator's reactivity manipulation plan relied on forced circulation for plant shutdown. Without a plan for reactor shut down in the natural circulation mode, the operators inserted an unplanned controlled manual reactor scram. Thermal-hydraulic conditions remained within operational limits during the event. The licensee entered the event into their corrective action program as Condition Report CR-RBS-2009-04175. The inspectors discussed the event with licensee management, engineering, operations, and maintenance Enclosure personnel to understand the conditions leading to the loss of both reactor recirculation pumps and subsequent operator actions. This licensee event report is closed. .2 (Closed) Licensee Event Report 05000458/2009-003-00

Low Pressure Coolant Injection Actuation Following Loss of Water from Upper Reactor Cavity Pool The safety significance and the enforcement aspect of this violation are discussed in section 1R22. The licensee has entered the event into their corrective action program as Condition Report CR-RBS-2009-04681. This licensee event report is closed. 4OA5 Other Activities Quarterly Resident Inspector Observations of Security Personnel and Activities a. Inspection Scope During the inspection period, the inspectors performed observations of security force personnel and activities to ensure that the activities were consistent with River Bend security procedures and regulatory requirements relating to nuclear plant security.

These observations took place during both normal and off-normal plant working hours.

These quarterly resident inspector observations of security force personnel and activities did not constitute any additional inspection samples. Rather, they were considered an integral part of the inspectors' normal plant status review and inspection activities.

b. Findings No findings of significance were identified.

4OA6 Meetings Exit Meeting Summary On October 2, 2009, the inspector presented the in-service inspection activities inspection results to Mr. J. Roberts, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

On December 17, 2009, the inspectors presented the radiation safety inspection results to Mr.

M. Perito, Site Vice President, Operations, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.

On January 7, 2010, the inspectors presented the integrated baseline inspection results to Mr. E. Olson, General Manager, Plant Operations, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspectors asked the licensee whether any Enclosure Enclosure materials examined during the inspection should be considered proprietary. No proprietary information was identified.

4OA7 Licensee-Identified Violations The following violation of very low safety significance (Green) was identified by the licensee and is a violation of NRC requirements which meets the criteria of Section VI of the NRC Enforcement Policy, NUREG-1600, for being dispositioned as a noncited violation.

Technical Specification 5.4.1.a requires implementation of applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Section 7(e) of the Appendix requires procedures for training in radiation protection and personnel monitoring. Section 4.0[1] of Procedure EN-RP-100,

"Radworker Expectations," Revision 0, requires, in part, that workers notify health physics upon receipt of any electronic alarming dosimeter alarm that was not prebriefed. Contrary to this, on January 17, 2008, a licensee worker failed to notify radiation protection personnel upon receipt of an electronic alarming dosimeter dose rate alarm in steam jet air ejector room B that was not prebriefed.

This finding had very low safety significance (Green) because: (1) it was not an ALARA finding, (2) there was no overexposure, (3) there was no substantial potential for an overexposure, and (4) the ability to assess dose was not compromised. This item was entered into the licensee's corrective action program as Condition Report CR-RBS-2008-00506.

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened and Closed 05000458/2009005-01 NCV Main Steam Line Plug Seal Failure Results in Loss of Reactor Cavity Inventory (Section 1R22)05000458/2009005-02 NCV Failure to Ensure the Emergency Contact had Knowledge

About a Shipment (Section 2PS2)

Closed 05000458/2009-002-00 LER Unplanned Manual Reactor Scram Following Trip of Both Reactor Recirculation Pumps (Section 4OA3.1)

05000458/2009-003-00 LER Low Pressure Coolant Injection Actuation Following Loss of Water from Upper Reactor Cavity Pool (Section 4OA3.2)

LIST OF DOCUMENTS REVIEWED Section 1R01: Adverse Weather Protection MISCELLANEOUS NUMBER TITLE REVISION/DATE NUREG-1407 Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Weather Vulnerabilities 0 NUREG-1779 Regulatory Effectiveness of the Station Blackout

Rule 0 RIS-2004-05 Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power April 15, 2004 PROCEDURES NUMBER TITLE REVISION AOP-0029 Severe Weather Operation 21 AOP-0064 Degraded Grid 0 EN-LI-101 10CFR50.59 Review Program 4 A-2 Attachment A-3 Attachment ENS-DC-199 Off-Site Power Supply Design Requirements 2 ENS-DC-201 ENS Transmission Grid Monitoring 2 OSP-0063 Grid Monitor 1 Section 1R04: Equipment Alignment

PROCEDURES NUMBER TITLE REVISION SOP-0035 Reactor Core Isolation Cooling System 35 SOP-0049 120 VDC System 27 SOP-0053 Standby Diesel Generator and Auxiliaries 307 SOP-0058 Control Building HVAC Systems 20 TECHNICAL SPECIFICATIONS NUMBER TITLE AMENDMENT Technical Specification 3.7.3 Control Room Air Conditioning (AC) System 132 Technical Specification 3.8.1 AC Sources-Operating 156 Section 1R05: Fire Protection

CONDITION REPORTS CR-RBS-2009-06002 CR-RBS-2009-06003 MISCELLANEOUS NUMBER TITLE REVISION Pre-Fire Plan/Strategy Book DRL-FP-00107 Control Building 116-foot C71 P002 RPS DIST PNL 4 TRM 3.7.9.6 Fire-Rated Assemblies 5

USAR 9A.2 Fire Hazards Analysis 10 USAR 9.4.7.2.1 Fire Pump House Heating and Ventilation System 15 PROCEDURES NUMBER TITLE REVISION AOP-0009 Loss of Normal Service Water 16 EN-DC-127 Control of Hot Work and Ignition Sources 7 EN-DC-128 Fire Protection Impact Reviews 4 FPP-0100 Fire Protection System Impairment 10 FPP-0101 Fire Suppression System Inspection 10 SOP-0037 Fire Protection Water System Operating Procedure (System 251)

27 Section 1R07: Heat Sink Performance CONDITION REPORTS CR-RBS-2008-02821 CR-RBS-2008-02878 CR-RBS-2009-04345 CR-RBS-2009-04830

PROCEDURE NUMBER TITLE REVISION SOP-0042 Standby Service Water 28 UPDATED SAFETY ANALYSIS REPORT DOCUMENTS NUMBER TITLE REVISION/DATE USAR 1.2.2.8.1 Standby Service Water System 19 USAR 3.8.4.4.4 Standby Service Water Cooling Tower and Pumphouse August 1987 USAR 7.3.1.1.8 Standby Service Water (SSW) System 13 USAR 9.2.7 Standby Service Water System 12 A-4 Attachment USAR Table 9.2-5 Decay Heat Rejection and Containment Unit Cooler Heat Load to Standby Service Water Following a Small Line Break Event SBA w/ Bypass 14 USAR Table 9.2-6 Plant Auxiliaries Heat Load (BTU/hr) Input to Standby Service Water Following a DBA 17 USAR Table 9.2-7 Plant Auxiliaries Heat Input to Standby Service Water 17 USAR Table 9.2-10 Total Integrated Heat Input to Standby Service Water from RHR Heat Exchangers, Containment

Unit Cooler, Pumps, and Plant Auxiliaries 17 USAR Table 9.2-11 Standby Cooling Tower Performance Following a Large Recirculation Line Break 17 USAR Table 9.2-13 Standby Service Water System Safeguard Equipment Status Following a DBA 9 USAR Table 9.2-15 Standby Service Water System Major Component Design Data 14 USAR Table 9.2-16 Standby Service Water System Single Passive Failure Criterion Analysis 8A Section 1R08: Inservice Inspection Activities

CONDITION REPORTS CR-RBS-2008-00430 CR-RBS-2008-00511 CR-RBS-2009-04463 CR-RBS-2009-04613 CR-RBS-2009-04683 CR-RBS-2009-04770 CR-RBS-2009-04773 CR-RBS-2009-04850

MISCELLANEOUS NUMBER TITLE DATE ELO-LO-2006-00094 Welding Program Assessment July 24, 2006

PROCEDURES NUMBER TITLE REVISION CEP-NDE-0400 Ultrasonic Examination 3 A-5 Attachment CEP-NDE-0404 Manual Ultrasonic Examination of Ferritic Piping Welds 4 CEP-NDE-0641 Liquid Penetrant Examination (PT) for ASME Section XI 5 CEP-NDE-0731 Magnetic Particle Examination (MT) for ASME Section XI 3 CEP-NDE-0903 VT-3 Examination 5 Section 1R12: Maintenance Effectiveness CONDITION REPORTS CR-RBS-2007-5298 CR-RBS-2008-3091 CR-RBS-2008-3303 CR-RBS-2008-3601 CR-RBS-2008-5073 CR-RBS-2008-5097 CR-RBS-2008-5129 CR-RBS-2008-5130 CR-RBS-2008-6244 CR-RBS-2008-6676 CR-RBS-2008-7029 CR-RBS-2008-7033 CR-RBS-2008-7039 CR-RBS-2008-7040 CR-RBS-2009-0424 CR-RBS-2009-0595 CR-RBS-2009-1485 CR-RBS-2009-5016 CR-RBS-2009-5048 CR-RBS-2009-5133 CR-RBS-2009-5170 CR-RBS-2009-5173 CR-RBS-2009-5314 CR-RBS-2009-5429 CR-RBS-2009-5474 CR-RBS-2009-6338 CR-RBS-2009-6348 PROCEDURES NUMBER TITLE REVISION EN-DC-205 Maintenance Rule Monitoring 2 EN-DC-206 Maintenance Rule (a)(1) Process 1

Section 1R13: Maintenance Risk Assessment and Emergent Work Controls PROCEDURES NUMBER TITLE REVISION ADM-0096 Risk Management Program and Implementation Risk Assessment 304 AOP-0029 Severe Weather Operation 24 A-6 Attachment AOP-0064 Degraded Grid 2 EN-MA-125 Troubleshooting and Control of Maintenance Activities 5 EN-OP-103 Reactivity Management Program 3 EN-WM-101 On-Line Work Management Process 6 Section 1R15: Operability Evaluations CONDITION REPORTS CR-RBS-2002-01095 CR-RBS-2008-02504 CR-RBS-2009-04959 CR-RBS-2009-05882 CR-RBS-2009-05928 MISCELLANEOUS NUMBER TITLE DATE IEEE Standard

C37.91-2008 IEEE Guide for Protecting Power Transformers May 30, 2008

PROCEDURE NUMBER TITLE REVISION STP-251-3205 Diesel Fire Pump Operational Test 14 Section 1R18: Plant Modifications CONDITION REPORT

CR-RBS-2009-06517 MISCELLANEOUS NUMBER TITLE REVISION ARP-SBO-DIESEL SBO Diesel Alarm Response 0 and 1 EC 18153 Replace Old Station Blackout Diesel, BYS-

EG1, with New Generac Diesel Generator 0 A-7 Attachment PROCEDURES NUMBER TITLE REVISION EN-DC-115 Engineering Change Process 8 EN-DC-136 Temporary Modifications 4 EN-LI-100 Process Applicability Determination 7 OSP-0007 Preparation, Review and Revision of Operations Section Procedures 19 RBNP-001 Development and Control of RBS Procedures 29 SOP-0054 Contingency Equipment Operation 306 and 307 UPDATED SAFETY ANALYSIS REPORT DOCUMENTS NUMBER TITLE REVISION/DATE USAR 8.1.4 Onsite AC Systems 6 USAR 15.2.6.1.1.1 Loss of Normal and Preferred Station Service Transformers August 1987

WORK ORDERS NUMBER TITLE WO 00210006 Task 1, Install TMOD 6321 on RWCU A WO 00210006 Task 3, Install TMOD 6321 on RWCU B WO 00209226 Task 3, RTX-XSR1E, Remove Load Tap Changer and Install TMOD 17184 WO 00199598 Task 3 & 4, RTX-XSR1F Transformer Trouble

Alarm Received in Main Control Room Section 1R19: Postmaintenance Testing MISCELLANEOUS NUMBER TITLE REVISION EC 15860 Disable Alarm and Trip Functions for Sudden Pressure Relays for RTX-XSR1F and RTX-

XSR1D 0 A-8 Attachment A-9 Attachment UPDATED SAFETY ANALYSIS REPORT DOCUMENTS NUMBER TITLE REVISION/DATE USAR 8.1.4 Onsite AC Systems 6 USAR 15.2.6.1.1.1 Loss of Normal and Preferred Station Service Transformers August 1987 WORK ORDERS NUMBER TITLE WO 00209226 Task 7, EMRTX-XSR1E Post Installation Testing for TMOD 17814 WO 00199598 Task 3 & 4, RTX-XSR1F Transformer Trouble Alarm Received in Main Control Room Section 1R20: Refueling and Other Outage Activities PROCEDURES NUMBER TITLE REVISION AOP-0001 Reactor Scram 24 GMP-0102 Reactor Vessel Disassembly 18 GMP-0103 Reactor Vessel Assembly 20 GOP-0001 Plant Startup 20 SOP-0031 Residual Heat Removal 306 Section 1R22: Surveillance Testing CONDITION REPORTS CR-RBS-1986-00018 CR-RBS-2009-04681 CR-RBS-2009-06460 MISCELLANEOUS NUMBER TITLE REVISION ARP-SBO-DIESEL SBO Diesel Alarm Response 1 ASME OMb Code-2006 Code for Operation and Maintenance of

Nuclear Power Plants

PROCEDURES NUMBER TITLE REVISION AOP-0027 Fuel Handling Mishaps 23 GMP-0108 Reactor Vessel Disassembly 31 SOP-0054 Contingency Equipment Operation 306 STP-309-0203 Division III Diesel Generator Operability Test 306 STP-309-0601 Division I ECCS Test 31 TECHNICAL SPECIFICATIONS NUMBER TITLE AMENDMENT Technical Specifications 3.8.1 AC Sources-Operating 156 Technical Specifications 3.8.2 AC Sources-Shutdown 132 Technical Specifications 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 81 WORK ORDERS NUMBER TITLE WO 52037115 Miscellaneous Containment Isolation Valves Quarterly Operability Test WO 52228449 Diesel Fire Pump Battery Weekly Surveillance Test Section 2OS2: ALARA Planning and Controls

AUDITS, SELF-ASSESSMENTS, AND SURVEILLANCES NUMBER TITLE DATE LO-RLO-2009-00005 Focused Assessment Report; Occupational Radiation Safety March 06, 2009 LO-RLO-2009-00057 Focused Assessment Report; Occupational Radiation Safety August 07, 2009 A-10 Attachment A-11 Attachment NUMBER TITLE DATE Snapshot Assessment RP Outage Readiness May 26, 2009 Snapshot Assessment Dose Reduction Techniques August 31, 2009 Snapshot Assessment Control and Use of Contaminated Drip Bags May 12, 2009 Snapshot Assessment Access to High Radiological Risk Activities September 30, 2009 CONDITION REPORTS CR-RBS-2009-00309 CR-RBS-2009-01843 CR-RBS-2009-02325 CR-RBS-2009-02414 CR-RBS-2009-02854 CR-RBS-2009-03155 CR-RBS-2009-03918 CR-RBS-2009-04440 CR-RBS-2009-04779 CR-RBS-2009-04817 CR-RBS-2009-04948 CR-RBS-2009-05043 CR-RBS-2009-05064 CR-RBS-2009-05169 CR-RBS-2009-05749 CR-RBS-2009-05751 CR-RBS-2009-05844 MISCELLANEOUS NUMBER TITLE 2009-2013 River Bend Station CRE Goals

PROCEDURES NUMBER TITLE REVISION EN-RP-100 Radworker Expectations 3 EN-RP-101 Access Control for Radiologically Controlled Areas 4 EN-RP-102 Radiological Control 2 EN-RP-105 Radiation Work Permits 7 EN-RP-109 Hot Spot Program 3 EN-RP-141 Job Coverage 4 RADIATION WORK PERMITS NUMBER TITLE 2009-1006 General Radwaste Activities including shipping <1000 mrem 2009-1214 General Radwaste Activities including shipping and LHRA 2009-1432 RF-15 Snubber Work 2009-1603 RF-15 Noble Chemistry Project Activities 2009-1800 RF-15 Refuel Activities 2009-1938 RF-15 Scaffold and Shielding 2009-1943 RF-15 Drywell Section 2PS2: Radioactive Material Processing and Transportation AUDITS, SELF-ASSESSMENTS, AND SURVEILLANCES NUMBER TITLE DATE QA-15-2007-RBS-1 & -2 Quality Assurance Audit of Radwaste and

Radiation Protection Pro g rams January 3, 2008 QA-15-2007-RBS-1 Followup to Audits July 14-17, 2008 QS-2008-RBS-11 Followup of the 2008 Radwaste

SurveillanceDecember 15-17, 2008

CONDITION REPORTS CR-HQN-2007-0541 CR-HQN-2007-0939 CR-HQN-2007-0939 CR-HQN-2007-0978 CR-HQN-2008-0013 CR-HQN-2008-0023 CR-HQN-2009-0400 CR-RBS-2007-3140 CR-RBS-2007-3661 CR-RBS-2007-3776 CR-RBS-2007-3793 CR-RBS-2007-4679 CR-RBS-2008-0452 CR-RBS-2008-3446 PROCEDURES NUMBER TITLE REVISION EN-RW-102 Radioactive Shipping Procedure 6 A-12 Attachment EN-RW-104 Scaling Factors 5 EN-RW-105 Process Control Program 1 RWS-0304 Radioactive Waste Handling and Control 15 RADIOACTIVE MATERIAL SHIPMENTS 2008-039 2009-040 2009-105 2009-106 2009-107 10 CFR Part 61 Waste Stream Scaling Factors TITLE DATE Spent Pool Fuel Cleanup (SFC 2009) June 9, 2009 Westinghouse Chemical Decon March 1, 2008 Dry Active Waste August 7, 2008 Condensate and Liquid Waste System January 21, 2009 Section 4OA1: Performance Indicator Verification

PROCEDURES NUMBER TITLE REVISION EN-LI-102 Corrective Action Process 13 EN-LI-114 Performance Indicator Process 4 Section 4OA2: Identification and Resolution of Problems

CONDITION REPORTS CR-RBS-2003-00670 CR-RBS-2008-02182 CR-RBS-2008-05650 CR-RBS-2009-04175 CR-RBS-2009-05933 A-13 Attachment LICENSEE EVENT REPORTS NUMBER TITLE REVISION LER 1995-012 Manual Scram Due to Recirculation Pump Transient 0 LER 2009-002 Unplanned Manual Reactor Scram Following Trip of Both Reactor Recirculation Pumps 0

MISCELLANEOUS NUMBER TITLE REVISION CEO 2009-00005 Nuclear Oversight Fleet Quarterly Report 0 ER-RB-2002-0042 Evaluation of Recirculation Pump Downshift Logic 0 TITLE DATE Caution Tags Greater than 90 day Index August 31, 2009 October 31, 2009 Clearances Greater than 90 day Index August 31, 2009 October 31, 2009 Control Room Annunciator Index August 31, 2009 October 31, 2009 Control Room Deficiency Index August 31, 2009 October 31, 2009 Operations Aggregate Index August 31, 2009 October 31, 2009 Operator Burden Index August 31, 2009 October 31, 2009 Operator Work Around Index August 31, 2009 October 31, 2009 ODMI Index November 6, 2009 ODMI, FWS P1A/B/C Operation with High Seal Leakage ODMI, High Alterx Housing Vibration ODMI, Turbine # 2 Valve Packing Leak Temporary Modification Log A-14 Attachment A-15 Attachment PROCEDURES NUMBER TITLE REVISION AOP-0024 Thermal Hydraulic Stability Controls 22 GOP-0004 Single Loop Operation 20 Section 4OA3: Event Follow-Up CONDITION REPORTS CR-RBS-2003-00670 CR-RBS-2008-02182 CR-RBS-2008-05650 CR-RBS-2009-04175 CR-RBS-2009-05933 MISCELLANEOUS NUMBER TITLE REVISION ER-RB-2002-0042 Evaluation of Recirculation Pump Downshift Logic 0 LER 1995-012 Manual Scram Due to Recirculation Pump Transient 0 LER 2009-002 Unplanned Manual Reactor Scram Following Trip of Both Reactor Recirculation Pumps 0 PROCEDURES NUMBER TITLE REVISION AOP-0024 Thermal Hydraulic Stability Controls 22 GOP-0004 Single Loop Operation 20

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