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
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 Overview Presentation (08-03-10).ppt Attachments: DCPP - 71002 Regional Inspection Overview 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>>
1
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:
Diablo Canyon Power Plant License Renewal NRC 71002 Regional Inspection Weeks of August 16 & September 13, 2010 1
Diablo Canyon Power Plant License Renewal 71002 Regional Inspection Overview US NRC 71002 License Renewal Regional Inspection August 16, 2010
DCPP License Renewal Project AMP Overview
- LR Project Overview - J. Fledderman
- Plant Description & AMP Development - P. Soenen 3
DCPP License Renewal Project Organization Overview
- Safety
- Facilities
- Plant/Project Organization
- STARS 4
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 5
Facilities Rooms for Week 1: Rooms for Week 2:
Room No. Purpose Room No. Purpose 533 NRC Team Room 533 NRC Team Room 215 PG&E LR Team Room 215 PG&E LR Team Room 528 Breakout 527 Breakout 214 Breakout 6
Regional Inspection Leads
- NRC
- Nathaniel Ferrer - LR Project Manager
- Greg Pick - Lead Inspector
- 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 7
DCPP Plant Organization John Conway Senior Vice President Energy Supply &
Chief Nuclear Officer Jim Becker Dennis Petersen Quality Verification Site Vice President Director Loren Sharp Bill Guldemond Lynn Walter Ken Peters Engineering Site Services Learning Services Station Director Senior Director Director Director Susan Westcott Jim Welsch Engineering Services Operations Services Director Director Jude Fledderman Cary Harbor Strategic Projects Maintenance Services Director Director Terence Grebel Tim King License Renewal Outage Management Manager Director 8
DCPP LR Project Organization 9
DCPP AMP Owners Identified for Inspection LRA Section GALL Program Plant Owner LRA Section GALL Program Plant Owner B2.1.1 XI.M1 Hill B2.1.22 XI.M38 Beard B2.1.2 XI.M2 Gardner B2.1.23 XI.M39 Efron B2.1.3 XI.M3 Beard B2.1.24 XI.E1 Zakaria B2.1.4 XI.M10 Hill B2.1.25 XI.E2 O'Neil Sullivan B2.1.5 XI.M11A Hardesty B2.1.26 XI.E3 Zakaria Hanson B2.1.6 XI.M17 Goyette B2.1.27 XI.S1 Hill B2.1.7 XI.M18 Beard B2.1.28 XI.S2 Wong B2.1.8 XI.M19 Arhar B2.1.29 XI.S3 Hill B2.1.9 XI.M20 Anastasio B2.1.30 XI.S4 Holtz B2.1.10 XI.M21 Wessel B2.1.31 XI.S5 Horstman Wong B2.1.11 XI.M23 Porter B2.1.32 XI.S6 O'sullivan Wong B2.1.12 XI.M27 Hromyak B2.1.33 XI.S7 O'sullivan Wong B2.1.13 XI.M26 Hromyak B2.1.34 XI.E5 Zakaria B2.1.14 XI.M30 Wessel B2.1.35 XI.E6 Zakaria B2.1.15 XI.M31 Bojduj B2.1.36 XI.E4 Goryance B2.1.16 XI.M32 Beard B2.1.37 Hardesty B2.1.17 XI.M33 Beard B2.1.39 XI.M12 Beard B2.1.18 XI.M34 Goyette B2.1.38 Goryance B2.1.19 XI.M35 Beard B3.1 X.M1 Khatri B2.1.20 XI.M36 Frantz B3.2 X.E1 Johnson B2.1.21 XI.M37 Hardesty 10
The STARS Alliance
- 7 companies operate 13 nuclear units with over 15,000 MWe generating capacity
- AmerenUEs Callaway Station,
- Arizona Public Services Palo Verde Station,
- Luminants Comanche Peak Station,
- Pacific Gas & Electrics Diablo Canyon Station,
- Southern California Edisons 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 others efforts with three primary objectives: 1) achieving and maintaining operational excellence, 2) achieving effective industry influence, and 3) enhancing economic performance.
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- Plant Aging Management Center of Business in Goodyear, AZ
- Staffed by utility and contractor personnel
- Work with station project managers to prepare License Renewal Applications for STARS members
- Standard process employed
- Participation in industry working groups
- Experience from previous STARS and other utilities License Renewal reviews 12
STARS PAM-COB Organization 13
Plant Description & AMP Development August 16, 2010 Philippe Soenen
DCPP Basic Description
- The DCPP site consists of approximately 750 acres located in San Luis 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 Canyon Power 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, each consisting of an NSSS, turbine-generator, auxiliary equipment, controls, and instrumentation.
- Principal structures include the containment structures, turbine building, and auxiliary building (which includes the control room, the fuel handling areas, and the ventilation areas).
- The NSSS for each Unit is contained within a steel-lined reinforced concrete structure.
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DCPP Site Aerial Photo 16
Major Plant Modifications
- Steam generators have been replaced in both units
- The reactor vessel head has been replaced in Unit 2, and the Unit 1 reactor vessel head is scheduled to be replaced during the fall 2010 outage 17
- 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
- Insights from other plant RAIs - part of development process 18
RAIs and Amendments
- 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 19
Errata RAI Set # Description of Errata Response Due 13 Revisions to boundary drawings, screening and aging evaluations for LRID 11, 16, 8/19/10 21, 24, 4 and modifications to the CST internal plenum 18 Corrections to: 9/8/10
- 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 eval to 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 20 Corrections to interfaces between LRID 28 and 15 to reflect modification to cut and TBD cap sample coolers; Correction to FE tables for HE systems in the TB (LRID 3, 4, 5, 6, 7, 8, and 9) 20
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 document listed in index
- Summary of each NRC OE document listed in index
- Other OE sources such as inspection reports, system health 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 pertaining to the program 21
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
- 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 -
Boric Acid Corrosion 22
System Notebook Contents
- Scoping Report
- Scope determination based on 9 questions, system description and intended 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) table, plus listing of materials, environments, and credited AMPs
- Component Material Reference List
- Lists each component subject to AMR and its material reference
- Listing of DCPP corrective action documents 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.
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Questions?
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DCPP Corrective Action Program CAP Process Yes Flowchart Enter Work Control Equipment Problem? Implement corrective actions Process DN Notification WGE / Close to Trend Yes No Possible Human Performance Entry Issue Yes Error with Inattentive Error Create Yes Program, Process or Consequence?
Is there a problem? Human Error Involved ? Accountability Notification Human Error related problem? Perform HEIT DA Notification Program, Process Organizationally Issue Induced Error No High (A) Example: RCA Sig. 1 Inadvertent Criticality HT ACE Yes Yes HT ACE Close to Trend Program or Process Medium (B) Example:
LT ACE Unplanned entry into LCO Issue? Sig. 1, 2 Action statement Common Cause (WGE)
Low (C) Example:
Minor issues that effect, but Sig. 3 do not impact Technical The determination of response type should be based upon the following risk matrix: Specifications or Safety WGE No Related equipment Close to Trend UNCERTAINTY High Medium Low High A A B Risk Medium A B C Is this an equipment Yes Low B C C problem that needs an Perform ER ACE equipment ACE?
A Root Cause Analysis is recommended to determine the root causes and (ER1A) corresponding corrective actions to prevent recurrence.
B Apparent or Common Cause is recommended to determine causes and corresponding corrective actions.
C No formal investigation is required to determine causes and corrective actions. No
- a. Risk - Involves two elements:
Consequences, both actual and potential. Implement corrective actions Probability of recurrence if corrective actions are not initiated.
- b. Uncertainty - Involves two elements: Note: RCA/ACE evaluations may Uncertainty regarding the cause. always be requested for any Uncertainty regarding the corrective actions that may be initiated with no station Significance Level at investigation. management discretion 25