ML103140175
| ML103140175 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/09/2010 |
| From: | - No Known Affiliation |
| To: | Division of License Renewal |
| References | |
| Download: ML103140175 (27) | |
Text
1 DiabloCanyonNPEm Resource From: Tan, Miranda [M1TF@pge.com]
Sent: Tuesday, November 09, 2010 11:31 AM To:Pick, Greg Cc: Grebel, Terence
Subject:
DCPP - 71002 Regional Inspection Over view Presentation (08-03-10).ppt Attachments:
DCPP - 71002 Regional Inspection Over view Presentation (08-03-10).ppt Greg, Attached is the Regional Inspection Overview presentation. Slide 17 contains major plant modifications.
Best, Miranda 805 781 9415
<<DCPP - 71002 Regional Inspection Overview Presentation (08-03-10).ppt>>
Hearing Identifier: DiabloCanyon_LicenseRenewal_NonPublic Email Number: 2156 Mail Envelope Properties (D065043718A59C4B99DDA1862BB067DE01BA243D)
Subject:
DCPP - 71002 Regional Inspection Overview Presentation (08-03-10).ppt Sent Date: 11/9/2010 11:31:22 AM Received Date: 11/9/2010 11:32:37 AM From: Tan, Miranda Created By: M1TF@pge.com Recipients: "Grebel, Terence" <TLG1@pge.com>
Tracking Status: None "Pick, Greg" <Greg.Pick@nrc.gov>
Tracking Status: None Post Office: exchange12.Utility.pge.com
Files Size Date & Time MESSAGE 228 11/9/2010 11:32:37 AM DCPP - 71002 Regional Inspection Overview Presentation (08-03-10).ppt 2674240 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
1 License Renewal NRC 71002 Regional Inspection Weeks of August 16 & September 13, 2010 License Renewal License Renewal NRC 71002 Regional Inspection NRC 71002 Regional Inspection Weeks of August 16 & September 13, 2010 Weeks of August 16 & September 13, 2010 Diablo Canyon Power Plant Diablo Canyon Power Plant Diablo Canyon Power Plant Diablo Canyon Power Plant License Renewal 71002 Regional Inspection Overview US NRC 71002 License Renewal Regional Inspection August 16, 2010 3 DCPP License Renewal Project AMP Overview
- LR Project Overview -J. Fledderman
- Plant Description & AMP Development -P. Soenen 4DCPP License Renewal Project Organization Overview*Safety*Facilities
- Plant/Project Organization
- STARS 5 Safety*Use of Site Standards Handbook (SSH)
- Dial 779 from any plant phone in case of an emergency (refer to SSH page 7)*In case of fire in the Administration Building 6 FacilitiesRooms for Week 1:Rooms for Week 2:
Breakout 528 PG&E LR Team Room 215 NRC Team Room 533 Purpose Room No.Breakout 214 Breakout 527 PG&E LR Team Room 215 NRC Team Room 533 Purpose Room No.
7 Regional Inspection Leads
- NRC-Nathaniel Ferrer -LR Project Manager
-Greg Pick -Lead Inspector
- DCPP -Terry Grebel -License Renewal PM
-Philippe Soenen -Assistant License Renewal PM
-Mike Wright -Engineering Single Point of Contact
- STARS-Tony Harris -STARS COB Manager
-Chalmer Myer -PAM COB Production Manager
-David Kunsemiller -DCPP Project Manager 8 DCPP Plant Organization John ConwaySenior Vice PresidentEnergy Supply &Chief Nuclear Officer Jim BeckerSite Vice President Loren SharpEngineeringSenior Director Ken PetersStation DirectorBill GuldemondSite Services Director Lynn Walter Learning Services Director Susan WestcottEngineering Services Director Jude Fledderman Strategic Projects DirectorTerence GrebelLicense RenewalManagerJim Welsch Operations Services Director Cary HarborMaintenance Services Director Tim KingOutage Management DirectorDennis PetersenQuality Verification Director 9 DCPP LR Project Organization 10DCPP AMP Owners Identified for InspectionHardesty XI.M37B2.1.21 JohnsonX.E1B3.2Frantz XI.M36B2.1.20Khatri X.M1B3.1Beard XI.M35B2.1.19GoryanceB2.1.38Goyette XI.M34B2.1.18Beard XI.M12B2.1.39Beard XI.M33B2.1.17HardestyB2.1.37Beard XI.M32B2.1.16GoryanceXI.E4B2.1.36Bojduj XI.M31B2.1.15ZakariaXI.E6B2.1.35Wessel XI.M30B2.1.14ZakariaXI.E5B2.1.34Hromyak XI.M26B2.1.13 O'sullivan WongXI.S7B2.1.33Hromyak XI.M27B2.1.12 O'sullivan WongXI.S6B2.1.32Porter XI.M23B2.1.11Horstman WongXI.S5B2.1.31Wessel XI.M21B2.1.10HoltzXI.S4B2.1.30Anastasio XI.M20B2.1.9 HillXI.S3B2.1.29 Arhar XI.M19B2.1.8WongXI.S2B2.1.28Beard XI.M18B2.1.7 HillXI.S1B2.1.27Goyette XI.M17B2.1.6Zakaria HansonXI.E3B2.1.26Hardesty XI.M11AB2.1.5O'Neil SullivanXI.E2B2.1.25 Hill XI.M10B2.1.4ZakariaXI.E1B2.1.24Beard XI.M3B2.1.3 Efron XI.M39B2.1.23Gardner XI.M2B2.1.2Beard XI.M38B2.1.22 Hill XI.M1B2.1.1Plant OwnerGALL ProgramLRA SectionPlant OwnerGALL ProgramLRA Section 11 The STARS Alliance
- 7 companies operate 13 nuclear units with over 15,000 MWe generating capacity
-AmerenUE's Callaway Station, -Arizona Public Service's Palo Verde Station,-Luminant's Comanche Peak Station, -Pacific Gas & Electric's Diablo Canyon Station, -Southern California Edison's San Onofre Station, -STP Nuclear Operating Company
-Wolf Creek Nuclear Operating Corporation
- The alliance was formed to capitalize on the collective abilities of the seven companies to support each other's efforts with three primary objectives: 1) achieving and maintaining operational excellence, 2) achieving effective industry influence, and 3) enhancing economic performance.
- P lant A ging M anagement Center o f Business in Goodyear, AZ
- Staffed by utility and contractor personnel
- Work with station project managers to pr epare License Renewal Applications for STARS members
- Standard process employed
- Participation in industry working groups
- Experience from previous STARS and other utilities License Renewal reviews 13 STARS PAM-COB Organization Plant Description & AMP Development August 16, 2010Philippe Soenen 15 DCPP Basic Description
- The DCPP site consists of approximately 750 acres located in SanLuis Obispo County, California
- Both DCPP Units employ a four-loop pressurized water reactor nuclear steam supply system furnished by Westinghouse Electric Corporation.
- The balance of plant for each Unit was designed and constructed by PG&E with the assistance of Bechtel.
- PG&E is authorized to operate Units 1 and 2 of the Diablo CanyonPower Plant, each at the licensed reactor core power level of 3,411 MWt (100 percent rated power).
-Current Operating Licenses expire in 2024 and 2025
- The plant incorporates two similar PWR nuclear power units, eachconsisting of an NSSS, turbine-generator, auxiliary equipment, controls, and instrumentation.
- Principal structures include the containment structures, turbinebuilding, and auxiliary building (which includes th e control room, the fuel handling areas, and the ventilation areas).
- The NSSS for each Unit is contained within a steel-lined reinforced concrete structure.
16 DCPP Site Aerial Photo 17 Major Plant Modifications
- Steam generators have been replaced in both units
- The reactor vessel head has been repl aced in Unit 2, and the Unit 1 reactor vessel head is scheduled to be replaced during the fall 2010 outage 18 DCPP LRA Quality Overview
- Follows the STARS Standards
-Uses the guidance and checks built into LRDMT
-Four step preparation, review, comment, owner acceptance
-Experience from Wolf Creek and Palo Verde
- Incorporates Industry Lessons Learned
-Observations from Industry Audits and Inspections
-Observations from ACRS Meetings
- 21 Draft RAI sets (including 1 from Environmental)
- 15 Official RAI sets
- 8 Official sets responded by PG&E
- 9 LRA amendments submitted
- 2 amendments pending submittal 20 Errata TBDCorrections to interfaces between LRID 28 and 15 to reflect modification to cut and cap sample coolers;Correction to FE tables for HE system s in the TB (LRID 3, 4, 5, 6, 7, 8, and 9) 20 9/8/10 Corrections to: -boundary drawings, screening aging evaluations for LRID 26 interfaces with systems 8, 9 &19;-terminal component designations for LRID 3, 7, 8, 14, 21, 23A & B, and 28; -environments for LRID 23B chiller coils-boundary drawings, screening and aging evalto add battery room eye-wash stations and buried components for LRID 16-AMP changes associated with system 16 changes
-LRID 7 to correct the CME combinations for the RCP Seal Cooler-Addition of FAC to aging evaluations for LRID 3 and 5 18 8/19/10 Revisions to boundary drawings, screening and aging evaluations for LRID 11, 16, 21, 24, 4 and modifications to the CST internal plenum 13Response Due Description of Errata RAI Set #
21 PER AMP Contents
- 10-Element reports
-Evaluation of the 10 NUREG-1801 chapter X/XI program elements
- OE summary reports
-Index of applicable DCPP corrective action and Industry OE documents
-Summary of each DCPP corrective action docu ment listed in index
-Summary of each NRC OE document listed in index
-Other OE sources such as inspection reports, system healt h cards, outage summary reports, correspondence, etc.
- Implementing Procedures
-Procedures credited for managing aging effects per NUREG-1801
- AMP Applicability List
-List of all plant components that credit a particular AMP
- LRA Appendix A
-Stand-alone copy of the LRA Appendix A text
- LRA Appendix B
-Stand-alone copy of the LRA Appendix B text
- References
-Any additional documents used in preparing the AMP
- RAIs/Amendments
-RAIs pertaini ng to the program 22 Operating Experience
- STARS LRDMT:
-Initial date search interval from 1/1/1997 -6/30/2009
-Used keyword search terms to identify potential age-related OE
-Evaluated remaining OE for aging effect and/or AMP applicability
-Applicable corrective action documents (ARs, Notifications) are listed in "Tab 2"the AMP Program Evaluation Reports (PERs)
- Significant plant OE searched for dates prior to 1997
- OE White Papers prepared for each AMP
-Additional word search using AMP specific terms using STARS/NRC audit search strings
-NCR, MR, Program Health Reports, Self/QA assessments
-Currently available in hardcopy PER binders
- Example: Boric Acid Corrosion OE Whitepaper -
B oric Acid Corrosio n
23 System Notebook Contents
- Scoping Report
-Scope determination based on 9 questions, system description andintended functions, *Screening Report
-Rolls up component types listing long/short-lived, active/passive, intended functions, and material/environments
- Component List
-Listing of all components associated with the system (LRID) whether in scope or not*Aging Evaluation Report
-Provides information contained in chapter 3.x.2-y (9-column) tabl e, plus listing of materials, environments, and credited AMPs
- Component Material Reference List
-Lists each component subject to AMR and its material reference
- AMR OE Summary
-Listing of DCPP corrective action doc uments and industry OE documents applicable to a system
- Boundary Drawings
-Contains all boundary drawings for an in-scope mechanical system
- RAIs/Amendments
-RAIs pertaining to the system.
24 Questions?
25 DCPP Corrective Action Program CAP Process Flowchart Create NotificationA Root Cause Analysis is recommended to determine the root causes andcorresponding corrective actions to prevent recurrence.B Apparent or Common Cause is recommended to determine causes andcorresponding corrective actions.C No formal investigation is required to determine causes and correctiveactions.a. Risk -Involves two elements:Consequences, both actual and potential.Probability of recurrence if corrective actions are not initiated.b. Uncertainty -Involves two elements:Uncertainty regarding the cause.Uncertainty regarding the corrective actions that may be initiated with noinvestigation.Is there a problem?Program, Process or Human Error related problem?YesHuman Error Involved ?Is this an equipment problem that needs an equipment ACE?(ER1A)Program or Process Issue?Implement corrective actionsInattentive ErrorOrganizationally Induced ErrorAccountabilityPossible Human Performance Issue NoYesYes NoPerform ER ACE YesClose to Trend NoImplement corrective actionsHigh (A)Sig. 1Equipment Problem?Enter Work ControlProcessYesError with Consequence?Perform HEITThe determination of response type should be based upon the following risk matrix:Medium (B)Sig. 1, 2Low (C)Sig. 3RCAHT ACEHT ACE LT ACECommon Cause(WGE) WGEClose to TrendEntry HighMediumLowHigh A A BRiskMedium A B CLow B C CUNCERTAINTYNote: RCA/ACE evaluations may always be requested for any station Significance Level at management discretionExample:Inadvertent CriticalityExample:Unplanned entry into LCO Action statementExample:Minor issues that effect, but do not impact Technical Specifications or Safety Related equipmentWGE / Close to Trend NoProgram, Process IssueYesDN NotificationDA NotificationYes