IR 05000032/2006005: Difference between revisions

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| issue date = 04/03/2007
| issue date = 04/03/2007
| title = Errata for Diablo Canyon Power Plant - NRC Inspection Report 05000275-06-005; 0500032-06-005 and 07200026-06-002
| title = Errata for Diablo Canyon Power Plant - NRC Inspection Report 05000275-06-005; 0500032-06-005 and 07200026-06-002
| author name = Gaddy V G
| author name = Gaddy V
| author affiliation = NRC/RGN-IV/DRP/RPB-B
| author affiliation = NRC/RGN-IV/DRP/RPB-B
| addressee name = Keenan J S
| addressee name = Keenan J
| addressee affiliation = Pacific Gas & Electric Co
| addressee affiliation = Pacific Gas & Electric Co
| docket = 05000275, 05000323, 07200026
| docket = 05000275, 05000323, 07200026
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:April 3, 2007John S. KeenanSenior Vice President - Generation and Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 770000 Mail Code B32 San Francisco, CA 94177-0001
[[Issue date::April 3, 2007]]
 
John S. KeenanSenior Vice President - Generation and Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 770000 Mail Code B32 San Francisco, CA 94177-0001


==Dear Mr. Keenan:==
==Dear Mr. Keenan:==
SUBJECT: ERRATA FOR DIABLO CANYON POWER PLANT - NRC INSPECTIONREPORT 05000275/2006005; 05000323/2006005 AND 07200026/2006002 Please insert the enclosed corrected pages of NRC Inspection Report 05000275/2006005;05000323/2006005, and 0700026/2006002. The subject inspection report included inspection related activities associated with the Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) project. NRC Inspection Report 07200026/2006002, used for inspection of the ISFSI, was not included with the originally issued inspection report. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) 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).
SUBJECT:ERRATA FOR DIABLO CANYON POWER PLANT - NRC INSPECTIONREPORT 05000275/2006005; 05000323/2006005 AND 07200026/2006002 Please insert the enclosed corrected pages of NRC Inspection Report 05000275/2006005;05000323/2006005, and 0700026/2006002. The subject inspection report included inspection related activities associated with the Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) project. NRC Inspection Report 07200026/2006002, used for inspection of the ISFSI, was not included with the originally issued inspection report. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) 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/
Sincerely,
/RA/
Vince G. Gaddy, ChiefProject Branch B Division of Reactor ProjectsDockets: 50-275  50-323 72-026Licenses: DPR-80 DPR-82 SNM-2511
Vince G. Gaddy, ChiefProject Branch B Division of Reactor ProjectsDockets: 50-275  50-323 72-026Licenses: DPR-80 DPR-82 SNM-2511


===Enclosure:===
===Enclosure:===
As stated Pacific Gas and Electric Company- 2 -cc w/enclosure:
As stated Pacific Gas and Electric Company- 2 -
Donna Jacobs Vice President, Nuclear Services Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424James R. Becker, Vice President Diablo Canyon Operations and Station Director, Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424Sierra Club San Lucia ChapterATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406Nancy CulverSan Luis Obispo Mothers for Peace P.O. Box 164 Pismo Beach, CA 93448ChairmanSan Luis Obispo County Board of Supervisors County Government Building 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408Truman Burns\Robert KinosianCalifornia Public Utilities Commission 505 Van Ness Ave., Rm. 4102 San Francisco, CA 94102-3298Diablo Canyon Independent Safety CommitteeRobert R. Wellington, Esq.
 
Legal Counsel 857 Cass Street, Suite D Monterey, CA 93940 Pacific Gas and Electric Company- 3 -Director, Radiological Health BranchState Department of Health Services P.O. Box 997414 (MS 7610)
Sacramento, CA 95899-7414Antonio Fernandez, Esq.Pacific Gas and Electric Company P.O. Box 7442 San Francisco, CA 94120City EditorThe Tribune 3825 South Higuera Street P.O. Box 112 San Luis Obispo, CA 93406-0112James D. Boyd, CommissionerCalifornia Energy Commission 1516 Ninth Street (MS 34)
Sacramento, CA 95814Jennifer TangField Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111Chief, Radiological Emergency Preparedness Section Oakland Field Office Chemical and Nuclear Preparedness and Protection Division Department of Homeland Security 1111 Broadway, Suite 1200 Oakland, CA 94607-4052 Pacific Gas and Electric Company- 4 -Electronic distribution by RIV:Regional Administrator (BSM1)DRP Director (ATH)DRS Director (DDC)DRS Deputy Director (RJC1)Senior Resident Inspector (TWJ)Branch Chief, DRP/B (VGG)Senior Project Engineer, DRP/E (FLB2)Team Leader, DRP/TSS (FLB2)RITS Coordinator (MSH3)DRS STA (DAP)V. Dricks, PAO (VLD)D. Cullison, OEDO RIV Coordinator (DGC)ROPreports DC Site Secretary (AWC1)W. A. Maier, RSLO (WAM)R. E. Kahler, NSIR (REK)D. B. Spitzberg, FCDB/B (DBS)SUNSI Review Completed: __RLK_ ADAMS: Yes G No Initials: _RLK__ Publicly Available G Non-Publicly Available G Sensitive Non-SensitiveS:\DRP\DRPDIR\DC 2006-05RP Errata.wpdRIV:DNMSC:DRP/BRLKellar;df,mjsVGGaddy/RA//RA/3/29/074/3/07OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax February 13, 2007John S. KeenanSenior Vice President - Generation and Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 770000 Mail Code B32 San Francisco, CA 94177-0001
 
SUBJECT: DIABLO CANYON POWER PLANT - NRC INTEGRATED INSPECTIONREPORT 05000275/2006005; 05000323/2006005 AND 07200026/2006002
 
==Dear Mr. Keenan:==
On December 31, 2006, the U.S. Nuclear Regulatory Commission completed an inspection atyour Diablo Canyon Power Plant, Units 1 and 2, facility. The enclosed integrated report documents the inspection findings that were discussed on January 10, 2007, with Ms. Donna Jacobs and members of your staff.This inspection examined activities conducted under your licenses as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.There were three NRC-identified findings and one self-revealing finding of very low safetysignificance (Green) identified in this report. These findings involved violations of NRC requirements. However, because of their very low risk significance and because they are entered into your corrective action program, the NRC is treating these four findings as noncited violations (NCVs) consistent with Section VI.A of the NRC Enforcement Policy. If you contest any NCV in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011-4005; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Diablo Canyon Power Plant.
 
Pacific Gas and Electric Company-2-In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) 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/Vince G. Gaddy, ChiefProject Branch B Division of Reactor ProjectsDockets: 50-275  50-323 72-026 Licenses: DPR-80 DPR-82 SNM-2511
 
===Enclosure:===
NRC Inspection Report 05000275/2006005; 05000323/2006005 and 0700026/2006002


===w/attachment:===
REGION IVDockets:50-275, 50-323, 72-026 Licenses:DPR-80, DPR-82, SNM-2511 Report:05000275/200600505000323/2006005 07200026/2006002Licensee:Pacific Gas and Electric Company Facility:Diablo Canyon Power Plant, Units 1 and 2 Location:7 1/2 miles NW of Avila Beach Avila Beach, CaliforniaDates:October 1 through December 31, 2006 Inspectors:T. Jackson, Senior Resident InspectorT. McConnell, Resident Inspector M. Brown, Resident Inspector M. Peck, Senior Resident Inspector - Callaway Plant J. Dodson, Regional Operations Officer J. Drake, Operation Engineer P. Goldberg, Reactor Inspector R. Kellar, Health Physicist R. Lantz, Senior Emergency Preparedness InspectorApproved By:V. G. Gaddy, Chief, Projects Branch BDivision of Reactor Projects Enclosure-3-SUMMARY OF FINDINGSIR 05000275/2006005, 05000323/2006005; 07200026/2006002; 10/1/06 - 12/31/06; DiabloCanyon Power Plant Units 1 and 2; Maintenance Risk Assessments and Emergent Work Control, Problem Identification and Resolution, Operability Evaluations, and Other Activities.This report covered a 13-week period of inspection by resident inspectors and Region-basedhealth physics and reactor inspectors. Three NRC-identified violations and one self-revealing, Green, noncited violation were identified. The significance of most findings is indicated by theircolor (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609 "Significance Determination Process." Findings for which the Significance Determination Process does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A.NRC-Identified and Self-Revealing FindingsCornerstone: Initiating Events
Supplemental Informationcc w/enclosure:
*Green. A self-revealing, noncited violation of 10 CFR Part 50, Appendix B,Criterion III, "Design Control," was identified for the failure to apply adequatedesign control measures regarding the installation of thimble tubes with chrome-plated bands. Specifically, Pacific Gas and Electric Company installed thimble tubes with chrome-plated bands at the fuel assembly bottom nozzle/lower core plate interface to address flow-induced vibration wear. Due to the failure of engineering personnel to account for the chrome-plated bands in the thimble tube relocation procedure, the chrome-plated band on Thimble Tube L-13 was removed from its designed location at the fuel assembly bottom nozzle, thereby increasing the potential for thimble tube through-wall wear. This issue was entered into Pacific Gas and Electric Company's corrective action program as Nonconformance Report N0002211.The finding is greater than minor because it is associated with the Initiating EventsCornerstone attribute of design control and affects the associated cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown as well as power operations.
Donna Jacobs Vice President, Nuclear Services Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424James R. Becker, Vice President Diablo Canyon Operations and Station Director, Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424Sierra Club San Lucia ChapterATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406 Enclosure-1-U.S. NUCLEAR REGULATORY COMMISSIONREGION IVDockets:50-275, 50-323, 72-026 Licenses:DPR-80, DPR-82, SNM-2511 Report:05000275/200600505000323/2006005 07200026/2006002Licensee:Pacific Gas and Electric Company Facility:Diablo Canyon Power Plant, Units 1 and 2 Location:7 1/2 miles NW of Avila Beach Avila Beach, CaliforniaDates:October 1 through December 31, 2006 Inspectors:T. Jackson, Senior Resident InspectorT. McConnell, Resident Inspector M. Brown, Resident Inspector M. Peck, Senior Resident Inspector - Callaway Plant J. Dodson, Regional Operations Officer J. Drake, Operation Engineer P. Goldberg, Reactor Inspector R. Kellar, Health Physicist R. Lantz, Senior Emergency Preparedness InspectorApproved By:V. G. Gaddy, Chief, Projects Branch BDivision of Reactor Projects Enclosure-3-SUMMARY OF FINDINGSIR 05000275/2006005, 05000323/2006005; 07200026/2006002; 10/1/06 - 12/31/06; DiabloCanyon Power Plant Units 1 and 2; Maintenance Risk Assessments and Emergent Work Control, Problem Identification and Resolution, Operability Evaluations, and Other Activities.This report covered a 13-week period of inspection by resident inspectors and Region-basedhealth physics and reactor inspectors. Three NRC-identified violations and one self-revealing, Green, noncited violation were identified. The significance of most findings is indicated by theircolor (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609 "Significance Determination Process." Findings for which the Significance Determination Process does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A.NRC-Identified and Self-Revealing FindingsCornerstone: Initiating Events
*Green. A self-revealing, noncited violation of 10 CFR Part 50, Appendix B,Criterion III, "Design Control," was identified for the failure to apply adequatedesign control measures regarding the installation of thimble tubes with chrome-
plated bands. Specifically, Pacific Gas and Electric Company installed thimble tubes with chrome-plated bands at the fuel assembly bottom nozzle/lower core plate interface to address flow-induced vibration wear. Due to the failure of engineering personnel to account for the chrome-plated bands in the thimble tube relocation procedure, the chrome-plated band on Thimble Tube L-13 was removed from its designed location at the fuel assembly bottom nozzle, thereby increasing the potential for thimble tube through-wall wear. This issue was entered into Pacific Gas and Electric Company's corrective action program as Nonconformance Report N0002211.The finding is greater than minor because it is associated with the Initiating EventsCornerstone attribute of design control and affects the associated cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown as well as power operations.


Using the Inspection Manual Chapter 0609, "Significance Determination Process,"
Using the Inspection Manual Chapter 0609, "Significance Determination Process,"

Revision as of 02:37, 13 July 2019

Errata for Diablo Canyon Power Plant - NRC Inspection Report 05000275-06-005; 0500032-06-005 and 07200026-06-002
ML070940259
Person / Time
Site: Diablo Canyon, 05000032  Pacific Gas & Electric icon.png
Issue date: 04/03/2007
From: Vincent Gaddy
NRC/RGN-IV/DRP/RPB-B
To: Keenan J
Pacific Gas & Electric Co
References
IR-06-002, IR-06-005
Download: ML070940259 (8)
v • d • e


Text

April 3, 2007John S. KeenanSenior Vice President - Generation and Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 770000 Mail Code B32 San Francisco, CA 94177-0001

Dear Mr. Keenan:

SUBJECT:ERRATA FOR DIABLO CANYON POWER PLANT - NRC INSPECTIONREPORT 05000275/2006005; 05000323/2006005 AND 07200026/2006002 Please insert the enclosed corrected pages of NRC Inspection Report 05000275/2006005;05000323/2006005, and 0700026/2006002. The subject inspection report included inspection related activities associated with the Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) project. NRC Inspection Report 07200026/2006002, used for inspection of the ISFSI, was not included with the originally issued inspection report. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) 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/

Vince G. Gaddy, ChiefProject Branch B Division of Reactor ProjectsDockets: 50-275 50-323 72-026Licenses: DPR-80 DPR-82 SNM-2511

Enclosure:

As stated Pacific Gas and Electric Company- 2 -

REGION IVDockets:50-275, 50-323,72-026 Licenses:DPR-80, DPR-82, SNM-2511 Report:05000275/200600505000323/2006005 07200026/2006002Licensee:Pacific Gas and Electric Company Facility:Diablo Canyon Power Plant, Units 1 and 2 Location:7 1/2 miles NW of Avila Beach Avila Beach, CaliforniaDates:October 1 through December 31, 2006 Inspectors:T. Jackson, Senior Resident InspectorT. McConnell, Resident Inspector M. Brown, Resident Inspector M. Peck, Senior Resident Inspector - Callaway Plant J. Dodson, Regional Operations Officer J. Drake, Operation Engineer P. Goldberg, Reactor Inspector R. Kellar, Health Physicist R. Lantz, Senior Emergency Preparedness InspectorApproved By:V. G. Gaddy, Chief, Projects Branch BDivision of Reactor Projects Enclosure-3-SUMMARY OF FINDINGSIR 05000275/2006005, 05000323/2006005; 07200026/2006002; 10/1/06 - 12/31/06; DiabloCanyon Power Plant Units 1 and 2; Maintenance Risk Assessments and Emergent Work Control, Problem Identification and Resolution, Operability Evaluations, and Other Activities.This report covered a 13-week period of inspection by resident inspectors and Region-basedhealth physics and reactor inspectors. Three NRC-identified violations and one self-revealing, Green, noncited violation were identified. The significance of most findings is indicated by theircolor (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609 "Significance Determination Process." Findings for which the Significance Determination Process does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A.NRC-Identified and Self-Revealing FindingsCornerstone: Initiating Events

  • Green. A self-revealing, noncited violation of 10 CFR Part 50, Appendix B,Criterion III, "Design Control," was identified for the failure to apply adequatedesign control measures regarding the installation of thimble tubes with chrome-plated bands. Specifically, Pacific Gas and Electric Company installed thimble tubes with chrome-plated bands at the fuel assembly bottom nozzle/lower core plate interface to address flow-induced vibration wear. Due to the failure of engineering personnel to account for the chrome-plated bands in the thimble tube relocation procedure, the chrome-plated band on Thimble Tube L-13 was removed from its designed location at the fuel assembly bottom nozzle, thereby increasing the potential for thimble tube through-wall wear. This issue was entered into Pacific Gas and Electric Company's corrective action program as Nonconformance Report N0002211.The finding is greater than minor because it is associated with the Initiating EventsCornerstone attribute of design control and affects the associated cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown as well as power operations.

Using the Inspection Manual Chapter 0609, "Significance Determination Process,"

Phase 1 Worksheet, the finding is determined to have very low safety significance because, assuming the worst-case degradation, the finding would not result in exceeding the Technical Specification limit for identified reactor coolant system leakage or affect mitigating systems. Specifically, the inspectors verified the worst-case leakage, i.e., guillotine break, from a thimble tube at the fuel assembly bottom nozzle/lower core plate interface to be approximately 7 gpm versus the Technical Specification reactor coolant system identified leakage limit of 10 gpm.

The finding has a crosscutting aspect in the area of problem identification andresolution associated with the corrective action program because Pacific Gas and Electric Company removed a corrective action to prevent recurrence of significant thimble tube wear (Section 4OA5.5).

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