IR 05000275/2009006: Difference between revisions

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{{Adams|number = ML092020097}}
{{Adams
| number = ML092020097
| issue date = 07/20/2009
| title = IR 05000275-09-006, on 01/01/2009 - 06/30/2009 for Diablo Canyon Power Plant; Steam Generator Replacement Inspection (50001)
| author name = Gaddy V G
| author affiliation = NRC/RGN-IV/DNMS/NMSB-B
| addressee name = Conway J T
| addressee affiliation = Pacific Gas & Electric Co
| docket = 05000275
| license number = DPR-080
| contact person =
| document report number = IR-09-006
| document type = Inspection Report, Letter
| page count = 11
}}


{{IR-Nav| site = 05000275 | year = 2009 | report number = 006 }}
{{IR-Nav| site = 05000275 | year = 2009 | report number = 006 }}
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==Dear Mr. Conway:==
==Dear Mr. Conway:==
On June 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Diablo Canyon Power Plant, Unit 1. The enclosed report documents the inspection findings that were discussed on June 29, 2009, with Mr. Jim Becker and members of your staff. This inspection examined activities conducted under your Unit 1 license as they relate to safety and compliance with the Commission's rules and regulations, and with the conditions of your Unit 1 license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel. This inspection covers Unit 1 steam generator replacement activities.
On June 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Diablo Canyon Power Plant, Unit 1. The enclosed report documents the inspection findings that were discussed on June 29, 2009, with Mr. Jim Becker and members of your staff.


Based on the results of this inspection, no findings of significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
This inspection examined activities conducted under your Unit 1 license as they relate to safety and compliance with the Commission's rules and regulations, and with the conditions of your Unit 1 license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel. This inspection covers Unit 1 steam generator replacement activities.
 
Based on the results of this inspection, no findings of significance were identified.
 
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Sincerely,/RA/
Sincerely,/RA/
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===w/Attachment:===
===w/Attachment:===
Supplemental Information cc w/enclosure:Sierra Club San Lucia Chapter ATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406 Nancy Culver San Luis Obispo Mothers for Peace P.O. Box 164 Pismo Beach, CA 93448 Chairman San Luis Obispo County Board of Supervisors 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408 Truman Burns\Robert Kinosian California Public Utilities Commission 505 Van Ness Ave., Rm. 4102 San Francisco, CA 94102 Diablo Canyon Independent Safety Committee Attn: Robert R. Wellington, Esq. Legal Counsel 857 Cass Street, Suite D Monterey, CA 93940 Director, Radiological Health Branch State Department of Health Services P.O. Box 997414 (MS 7610)
Supplemental Information cc w/enclosure:Sierra Club San Lucia Chapter ATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406  
Sacramento, CA 95899-7414 City Editor The Tribune 3825 South Higuera Street P.O. Box 112 San Luis Obispo, CA 93406-0112 James D. Boyd, Commissioner California Energy Commission 1516 Ninth Street (MS 31) Sacramento, CA 95814 James R. Becker, Site Vice President & Station Director Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 Jennifer Tang Field Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111 Chief, Technological Hazards Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052 Pacific Gas and Electric Company - 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)
 
Nancy Culver San Luis Obispo Mothers for Peace P.O. Box 164 Pismo Beach, CA 93448 Chairman San Luis Obispo County Board of Supervisors 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408  
 
Truman Burns\Robert Kinosian California Public Utilities Commission 505 Van Ness Ave., Rm. 4102 San Francisco, CA 94102  
 
Diablo Canyon Independent Safety Committee Attn: Robert R. Wellington, Esq. Legal Counsel 857 Cass Street, Suite D Monterey, CA 93940 Director, Radiological Health Branch State Department of Health Services P.O. Box 997414 (MS 7610)
Sacramento, CA 95899-7414 City Editor The Tribune 3825 South Higuera Street P.O. Box 112 San Luis Obispo, CA 93406-0112  
 
James D. Boyd, Commissioner California Energy Commission 1516 Ninth Street (MS 31) Sacramento, CA 95814 James R. Becker, Site Vice President & Station Director Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424  
 
Jennifer Tang Field Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111  
 
Chief, Technological Hazards Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052 Pacific Gas and Electric Company - 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 (Michael.Peck@nrc.gov) Resident Inspector (Tony.Brown@nrc.gov) Branch Chief, DRP/B (Vincent.Gaddy@nrc.gov) Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)
DRS Deputy Director (Troy.Pruett@nrc.gov) Senior Resident Inspector (Michael.Peck@nrc.gov) Resident Inspector (Tony.Brown@nrc.gov) Branch Chief, DRP/B (Vincent.Gaddy@nrc.gov) Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)
DC Site Secretary (Agnes.Chan@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) OEMail Resource Only inspection reports to the following: DRS STA (Dale.Powers@nrc.gov) OEDO RIV Coordinator (Leigh.Trocine@nrc.gov) ROPreports
DC Site Secretary (Agnes.Chan@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) OEMail Resource  


File located: R:_REACTORS\_DC\2009\DC 2009006-MAB.doc ML 092020097 SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGG RIV:RI:DRP/B C:DRS/PSB2 C:DRS/PSBI C:DRS/EBI C:DRS/EB2 MABrown GWerner MShannon TFarnholtz NO'Keefe /RA/ /RA/ LCarson for/RA/ /RA/WSifre for /RA/ GPick for 7/17/09 7/15/09 7/15/09 7/14/09 7/14/09 C:DRS/OB VGGaddy /RA/ RDeese for 7/20/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Dockets: 50-275 Licenses: DPR-80 Report: 05000275/2009006 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Unit 1 Location: 7 1/2 miles NW of Avila Beach Avila Beach, California Dates: January 1, 2009 through June 30, 2009 Inspector: M. Brown, Resident Inspector, Project Branch B, DRP Approved By: V.G. Gaddy, Chief, Project Branch B, Division of Reactor Projects Enclosure  
Only inspection reports to the following: DRS STA (Dale.Powers@nrc.gov) OEDO RIV Coordinator (Leigh.Trocine@nrc.gov) ROPreports
 
File located: R:_REACTORS\_DC\2009\DC 2009006-MAB.doc ML 092020097 SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGG RIV:RI:DRP/B C:DRS/PSB2 C:DRS/PSBI C:DRS/EBI C:DRS/EB2 MABrown GWerner MShannon TFarnholtz NO'Keefe  
/RA/ /R A/ LCarson for
/RA/ /RA/WSifre for
/RA/ GPick for 7/17/09 7/15/09 7/15/09 7/14/09 7/14/09 C:DRS/OB VGGaddy  
/RA/ RDeese for 7/20/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Dockets: 50-275 Licenses: DPR-80 Report: 05000275/2009006 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Unit 1 Location: 7 1/2 miles NW of Avila Beach Avila Beach, California  
 
Dates: January 1, 2009 through June 30, 2009 Inspector: M. Brown, Resident Inspector, Project Branch B, DRP Approved By:
V.G. Gaddy, Chief, Project Branch B, Division of Reactor Projects Enclosure  


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
IR 05000275/2009006; 1/1/09 - 6/30/09; Diablo Canyon Power Plant; Steam Generator Replacement Inspection (50001) This report covered a 6-month period of inspection by the resident inspector. No findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
IR 05000275/2009006; 1/1/09 - 6/30/09; Diablo Canyon Power Plant; Steam Generator Replacement Inspection (50001)  
 
This report covered a 6-month period of inspection by the resident inspector. No findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.


===A. NRC-Identified and Self-Revealing Findings===
===A. NRC-Identified and Self-Revealing Findings===
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===B. Licensee-Identified Violations===
===B. Licensee-Identified Violations===
None.
None.


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====a. Inspection Scope====
====a. Inspection Scope====
This inspection report discusses NRC inspection activities related to the Diablo Canyon Power Plant, Unit 1, steam generator replacement project. These steam generator replacement inspection activities are not part of the normal baseline inspection program, but are performed on an as-needed basis. Therefore, no sample size is specified. The inspector completed the entire procedure for steam generator replacement (50001). Inspection Activities Documented in Other Inspection Reports: A significant portion of these inspection efforts were completed and documented in prior NRC inspection reports, as listed below:
This inspection report discusses NRC inspection activities related to the Diablo Canyon Power Plant, Unit 1, steam generator replacement project.
 
These steam generator replacement inspection activities are not part of the normal baseline inspection program, but are performed on an as-needed basis. Therefore, no sample size is specified. The inspector completed the entire procedure for steam generator replacement (50001).
 
Inspection Activities Documented in Other Inspection Reports:
A significant portion of these inspection efforts were completed and documented in prior NRC inspection reports, as listed below:
* Permanent plant modifications, NRC Integrated Inspection Reports 05000275/2009002 and 05000323/2009002, Section 1R18
* Permanent plant modifications, NRC Integrated Inspection Reports 05000275/2009002 and 05000323/2009002, Section 1R18
* Temporary modifications, NRC Integrated Inspection Reports 05000275/2009002 and 05000323/2009002, Section 1R18
* Temporary modifications, NRC Integrated Inspection Reports 05000275/2009002 and 05000323/2009002, Section 1R18
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==4OA2
==4OA2
* Operability evaluations, NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002, Section 1R15==
* Operability evaluations, NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002, Section 1R15==
* Post installation verification and testing, NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002, Section 1R22 and NRC Integrated Inspection Report 05000275/2009003 and 05000323/2009003, Section 1R19 The results of the security-related inspection activities will be documented in NRC Inspection Report 05000275/2009401 and 05000323/2009401. In addition to the above, as part of this inspection effort, the inspector reviewed additional activities to ensure proper (1) design and planning and (2) removal and replacement, as provided below: Engineering and Technical Support and Permanent Design Modifications.
* Post installation verification and testing, NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002, Section 1R22 and NRC Integrated Inspection Report 05000275/2009003 and 05000323/2009003, Section 1R19 The results of the security-related inspection activities will be documented in NRC Inspection Report 05000275/2009401 and 05000323/2009401.
 
In addition to the above, as part of this inspection effort, the inspector reviewed additional activities to ensure proper (1) design and planning and (2) removal and replacement, as provided below:
Engineering and Technical Support and Permanent Design Modifications.


The inspector reviewed engineering and technical support activities prior to, and during, the replacement outage. The inspector reviewed the following modifications:
The inspector reviewed engineering and technical support activities prior to, and during, the replacement outage. The inspector reviewed the following modifications:
* The complete scope of design changes associated with all the hard (physical plant) and soft (documentation) changes for the replacement of all four Unit 1 steam generators
* The complete scope of design changes associated with all the hard (physical plant) and soft (documentation) changes for the replacement of all four Unit 1 steam generators
* Unit 1 and Unit 2 Tavg and T-feedwater range program
* Unit 1 and Unit 2 Tavg and T-feedwater range program
* Use of alternate methodologies for Units 1 and 2 steam generator replacement projects   The inspector verified the technical adequacy of the modifications, including 10 CFR 50.59 related documents. Lifting and Rigging. The inspector reviewed engineering design, modification, testing, and analysis associated with steam generator lifting and rigging. This included:  (1) crane and rigging equipment; (2) steam generator component drop analysis; (3) safe load paths; (4) load lay-down areas; and (5) heavy load haul path. The inspector verified that the licensee had properly evaluated the potential impact of load handling on the reactor core and spent fuel, including cooling and support systems. This review also included the potential impact to underground electrical lines, fluid piping, and sewer systems that were traversed by the heavy haul route.
* Use of alternate methodologies for Units 1 and 2 steam generator replacement projects The inspector verified the technical adequacy of the modifications, including 10 CFR 50.59 related documents.
 
Lifting and Rigging. The inspector reviewed engineering design, modification, testing, and analysis associated with steam generator lifting and rigging. This included:  (1) crane and rigging equipment; (2) steam generator component drop analysis; (3) safe load paths; (4) load lay-down areas; and (5) heavy load haul path. The inspector verified that the licensee had properly evaluated the potential impact of load handling on the reactor core and spent fuel, including cooling and support systems. This review also included the potential impact to underground electrical lines, fluid piping, and sewer systems that were traversed by the heavy haul route.


The inspector conducted reviews of the preparations and procedures for:  (1) crane and rigging inspections; (2) testing; (3) equipment modifications; (4) lay-down area preparations; and (5) training. The related activities and equipment included:
The inspector conducted reviews of the preparations and procedures for:  (1) crane and rigging inspections; (2) testing; (3) equipment modifications; (4) lay-down area preparations; and (5) training. The related activities and equipment included:
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* Temporary lifting device inside containment
* Temporary lifting device inside containment
* Reactor cavity decking
* Reactor cavity decking
* Steam generator removal, installation of the replacement steam generators, and transport of the old steam generators to the storage facility The inspector directly observed portions of the movement of each installed steam generator, including in the order of removal:  (1) inside containment temporary lifting device lifting and rigging, (2) downending, (3) traversing through the hatch transfer system, (4) single point lift system movements, (5) self-propelled modular transporter travel from the sundeck through the fuel handling building to the outside lift system (6) lifting the outside lift system, and (7) self-propelled modular transporter travel from the outside lift system to the old steam generator storage facility. The inspector also directly observed portions of the installation of the replacement steam generators, which were moved from the replacement steam generator storage facility into containment in reverse order to the old steam generator movements discussed above. The inspector observed a sample of various other activities including the initial lifts, heavy haul routes, and use of the hatch transfer system equipment.
* Steam generator removal, installation of the replacement steam generators, and transport of the old steam generators to the storage facility The inspector directly observed portions of the movement of each installed steam generator, including in the order of removal:  (1)inside containment temporary lifting device lifting and rigging , (2) downending, (3) traversing through the hatch transfer system, (4) single point lift system movements, (5) self-propelled modular transporter travel from the sundeck through the fuel handling building to the outside lift system (6) lifting the outside lift system, and (7) self-propelled modular transporter travel from the outside lift system to the old steam generator storage facility. The inspector also directly observed portions of the installation of the replacement steam generators, which were moved from the replacement steam generator storage facility into containment in reverse order to the old steam generator movements discussed above. The inspector observed a sample of various other activities including the initial lifts, heavy haul routes, and use of the hatch transfer system equipment.


Radiation Protection Program Controls. In addition to the health physics inspections, which are referenced in Section 1.a of this report,  the inspector performed the following radiation protection-related inspections:  (1) direct inspection of radiation protection personnel coverage and control, as low as reasonably achievable, and dosimetry control activities along load movement path of old steam generator from containment to the old steam generator storage facility; and (2) direct inspection of radiation protection controls and procedure adherence to the old steam generator storage facility.
Radiation Protection Program Controls. In addition to the health physics inspections, which are referenced in Section 1.a of this report,  the inspector performed the following radiation protection-related inspections:  (1) direct inspection of radiation protection personnel coverage and control, as low as reasonably achievable, and dosimetry control activities along load movement path of old steam generator from containment to the old steam generator storage facility; and (2) direct inspection of radiation protection controls and procedure adherence to the old steam generator storage facility.


Steam Generator Hold Down Bolts and Major Structural Modifications. The inspector examined the old steam generator hold down bolts for degradation. The inspector also reviewed documentation and performed direct inspections related to permanent structural modifications made to facilitate steam generator replacement. It should be noted that even though these modifications were treated as permanent, all outside rigging and handling equipment was removed after the replacement of the Unit 1 steam generators. These modifications included the outside lift system platform and the outside lift system tower base frame. Foreign Material Controls. The inspector directly observed the cutting and grinding of primary and secondary side main steam line piping as well as the foreign material exclusion boundaries and controls in place for the remaining reactor coolant system piping. The inspector also verified foreign material control measures for the reactor coolant system hot and cold legs after old steam generator removal. The inspector also performed engineering reviews of the foreign material controls and reviewed corrective action documents related to foreign material exclusion.
Steam Generator Hold Down Bolts and Major Structural Modifications. The inspector examined the old steam generator hold down bolts for degradation. The inspector also reviewed documentation and performed direct inspections related to permanent structural modifications made to facilitate steam generator replacement. It should be noted that even though these modifications were treated as permanent, all outside rigging and handling equipment was removed after the replacement of the Unit 1 steam generators. These modifications included the outside lift system platform and the outside lift system tower base frame.
 
Foreign Material Controls. The inspector directly observed the cutting and grinding of primary and secondary side main steam line piping as well as the foreign material exclusion boundaries and controls in place for the remaining reactor coolant system piping. The inspector also verified foreign material control measures for the reactor coolant system hot and cold legs after old steam generator removal. The inspector also performed engineering reviews of the foreign material controls and reviewed corrective action documents related to foreign material exclusion.


Containment Access and Integrity. Final containment close-out and testing inspections were performed by the resident inspectors and documented in NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002. It should be noted that no physical modification or cutting was performed on the containment hatch opening during the Unit 1 steam generator replacement outage.
Containment Access and Integrity. Final containment close-out and testing inspections were performed by the resident inspectors and documented in NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002. It should be noted that no physical modification or cutting was performed on the containment hatch opening during the Unit 1 steam generator replacement outage.
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.
.


No findings of significance were identified.  
No findings of significance were identified.
 
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings, Including Exit==
==4OA6 Meetings, Including Exit==
The inspector presented the inspection results to Mr. J. Becker, Site Vice President, and other members of the licensee's management staff in person on June 29, 2009. The licensee acknowledged the information presented. Some proprietary information was reviewed during this inspection but no proprietary information was included in this report.
The inspector presented the inspection results to Mr. J. Becker, Site Vice President, and other members of the licensee's management staff in person on June 29, 2009. The licensee acknowledged the information presented. Some proprietary information was reviewed during this inspection but no proprietary information was included in this report.


ATTACHMENT:  Supplemental Information    
ATTACHMENT:  Supplemental Information  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
===Licensee Personnel===
: [[contact::J. Becker]], Site Vice President
: [[contact::W. Guldemond]], Director, Site Services
: [[contact::S. Ketelsen]], Manager, Regulatory Services
: [[contact::K. Peters]], Station Director
: [[contact::M. Somerville]], Manager, Radiation Protection
: [[contact::T. Swartzbaush]], Manager, Operations
: [[contact::J. Welsch]], Director, Operations Services
==LIST OF DOCUMENTS REVIEWED==
In addition to the documents referred to in the inspection report, the following documents were selected and reviewed by the inspector to accomplish the objectives and scope of the inspection and to support any findings.
: For inspection activities documented in other NRC inspection reports, the documents reviewed are listed in the respective report:
: PROCEDURES
: NUMBER
: TITLE REVISION
: AD8.ID1 Outage Planning and Management 11
: CF4.ID7 Temporary Modifications 20
: OM3.ID6 Differing Professional Opinion (DPO) 1
: OM7.ID1 Problem Identification and Resolution - Action Requests 30
: OM7.ID12 Operability Determination 12
: QEP 10.03-1 SGT Procedure: "Care and Maintenance Instruction" 0E1
: QEP 10.04
: SGT Procedure: "General Housekeeping, Foreign Material Exclusion (FME), and Cleanness Requirement"
: 1E1
: QEP 10.04-1 SGT Procedure: "FMEA Limited Access Poster" 0
: QEP 11.01 Work Packages 1
: QEP 11.01-1 SGT Work Package Index: "Temporary Power Inside Containment"
: 0E2
: QEP 11.04 SGT Procedure: "Structural and Miscellaneous Steel Installation"
: 0E1
: QEP 12.01 Inspection and Surveillance Planning 1 STP M-45B Containment Inspection When Containment Integrity is Established 
: Attachment
: PROCEDURES
: NUMBER
: TITLE REVISION
: TQ2.ID4 Training Program Implementation 17
: TS3.ID2 Licensing Basis Impact Evaluations 24
: Design Change Packages (DCPs), Design Change Notices (DCNs), and Licensing Basis Impact Evaluations (LBIEs)
: PROCEDURES
: NUMBER
: TITLE REVISION LBIE 2007-013 RSG Component Modification LBIE 50.59 Evaluation
: LBIE 2009-003 Use of Alternative Methodologies for RSGs
: DCP 1000000120 Tavg and Tfeed Ranges Program 0 LBIE 2009-004 Tavg and Tfeed Ranges Program Nonconformance/Deficiency Reports
: SGT
: NCR 1004, November 20, 2008 SGT
: NCR 1017, February 1, 2009
: SGT
: NCR 1019, February 4, 2009 SGT
: NCR 1023, February 8, 2009 SGT
: NCR 1026, February 9, 2009 SGT
: NCR 1029, February 14, 2009 SGT
: NCR 1030, February 15, 2009
: SGT
: NCR 1032, February 16, 2009 SGT
: NCR 1033, February 17, 2009 SGT
: NCR 1034, February 18, 2009 SGT
: NCR 1040, February 23, 2009 SGT
: NCR 1048, February 24, 2009 SGT
: NCR 1049, February 25, 2009 SGT
: NCR 1051, February 25, 2009
: SGT
: NCR 1054, February 27, 2009 SGT
: NCR 1056, March 1, 2009 SGT
: NCR 1058, March 2, 2009 SGT
: DR-44, January 30, 2009 SGT
: DR-47, February 9, 2009
: SGT
: DR-51, February 23, 2009 SGT
: DR-52, February 24, 2009 SGT
: DR-53, March 3, 2009
}}
}}

Revision as of 21:39, 25 August 2018

IR 05000275-09-006, on 01/01/2009 - 06/30/2009 for Diablo Canyon Power Plant; Steam Generator Replacement Inspection (50001)
ML092020097
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 07/20/2009
From: Vincent Gaddy
NRC/RGN-IV/DNMS/NMSB-B
To: Conway J T
Pacific Gas & Electric Co
References
IR-09-006
Download: ML092020097 (11)
v • d • e


Text

July 20, 2009

John Senior Vice President-Energy Supply and Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 3 Mail Code 104/6/601 Avila Beach, California 93424

SUBJECT: DIABLO CANYON POWER PLANT - NRC INSPECTION REPORT 05000275/2009006

Dear Mr. Conway:

On June 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Diablo Canyon Power Plant, Unit 1. The enclosed report documents the inspection findings that were discussed on June 29, 2009, with Mr. Jim Becker and members of your staff.

This inspection examined activities conducted under your Unit 1 license as they relate to safety and compliance with the Commission's rules and regulations, and with the conditions of your Unit 1 license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel. This inspection covers Unit 1 steam generator replacement activities.

Based on the results of this inspection, no findings of significance were identified.

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

Sincerely,/RA/

Vince G. Gaddy, Chief Project Branch B Division of Reactor Projects Docket: 50-275 License: DPR-80 Pacific Gas and Electric Company - 2 -

Enclosure:

NRC Inspection Report 05000275/2009006

w/Attachment:

Supplemental Information cc w/enclosure:Sierra Club San Lucia Chapter ATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406

Nancy Culver San Luis Obispo Mothers for Peace P.O. Box 164 Pismo Beach, CA 93448 Chairman San Luis Obispo County Board of Supervisors 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408

Truman Burns\Robert Kinosian California Public Utilities Commission 505 Van Ness Ave., Rm. 4102 San Francisco, CA 94102

Diablo Canyon Independent Safety Committee Attn: Robert R. Wellington, Esq. Legal Counsel 857 Cass Street, Suite D Monterey, CA 93940 Director, Radiological Health Branch State Department of Health Services P.O. Box 997414 (MS 7610)

Sacramento, CA 95899-7414 City Editor The Tribune 3825 South Higuera Street P.O. Box 112 San Luis Obispo, CA 93406-0112

James D. Boyd, Commissioner California Energy Commission 1516 Ninth Street (MS 31) Sacramento, CA 95814 James R. Becker, Site Vice President & Station Director Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424

Jennifer Tang Field Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111

Chief, Technological Hazards Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052 Pacific Gas and Electric Company - 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 (Michael.Peck@nrc.gov) Resident Inspector (Tony.Brown@nrc.gov) Branch Chief, DRP/B (Vincent.Gaddy@nrc.gov) Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)

DC Site Secretary (Agnes.Chan@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) OEMail Resource

Only inspection reports to the following: DRS STA (Dale.Powers@nrc.gov) OEDO RIV Coordinator (Leigh.Trocine@nrc.gov) ROPreports

File located: R:_REACTORS\_DC\2009\DC 2009006-MAB.doc ML 092020097 SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGG RIV:RI:DRP/B C:DRS/PSB2 C:DRS/PSBI C:DRS/EBI C:DRS/EB2 MABrown GWerner MShannon TFarnholtz NO'Keefe

/RA/ /R A/ LCarson for

/RA/ /RA/WSifre for

/RA/ GPick for 7/17/09 7/15/09 7/15/09 7/14/09 7/14/09 C:DRS/OB VGGaddy

/RA/ RDeese for 7/20/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Dockets: 50-275 Licenses: DPR-80 Report: 05000275/2009006 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Unit 1 Location: 7 1/2 miles NW of Avila Beach Avila Beach, California

Dates: January 1, 2009 through June 30, 2009 Inspector: M. Brown, Resident Inspector, Project Branch B, DRP Approved By:

V.G. Gaddy, Chief, Project Branch B, Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

IR 05000275/2009006; 1/1/09 - 6/30/09; Diablo Canyon Power Plant; Steam Generator Replacement Inspection (50001)

This report covered a 6-month period of inspection by the resident inspector. No findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.

A. NRC-Identified and Self-Revealing Findings

None.

B. Licensee-Identified Violations

None.

REPORT DETAILS

4OA5 Other Activities

.1 Steam Generator Replacement Inspection

Main article: IP 50001

a. Inspection Scope

This inspection report discusses NRC inspection activities related to the Diablo Canyon Power Plant, Unit 1, steam generator replacement project.

These steam generator replacement inspection activities are not part of the normal baseline inspection program, but are performed on an as-needed basis. Therefore, no sample size is specified. The inspector completed the entire procedure for steam generator replacement (50001).

Inspection Activities Documented in Other Inspection Reports:

A significant portion of these inspection efforts were completed and documented in prior NRC inspection reports, as listed below:

==4OA2

In addition to the above, as part of this inspection effort, the inspector reviewed additional activities to ensure proper (1) design and planning and (2) removal and replacement, as provided below:

Engineering and Technical Support and Permanent Design Modifications.

The inspector reviewed engineering and technical support activities prior to, and during, the replacement outage. The inspector reviewed the following modifications:

  • The complete scope of design changes associated with all the hard (physical plant) and soft (documentation) changes for the replacement of all four Unit 1 steam generators
  • Unit 1 and Unit 2 Tavg and T-feedwater range program
  • Use of alternate methodologies for Units 1 and 2 steam generator replacement projects The inspector verified the technical adequacy of the modifications, including 10 CFR 50.59 related documents.

Lifting and Rigging. The inspector reviewed engineering design, modification, testing, and analysis associated with steam generator lifting and rigging. This included: (1) crane and rigging equipment; (2) steam generator component drop analysis; (3) safe load paths; (4) load lay-down areas; and (5) heavy load haul path. The inspector verified that the licensee had properly evaluated the potential impact of load handling on the reactor core and spent fuel, including cooling and support systems. This review also included the potential impact to underground electrical lines, fluid piping, and sewer systems that were traversed by the heavy haul route.

The inspector conducted reviews of the preparations and procedures for: (1) crane and rigging inspections; (2) testing; (3) equipment modifications; (4) lay-down area preparations; and (5) training. The related activities and equipment included:

  • Area preparation for the outside systems
  • Outside lift system
  • Self-propelled modular transporter travel through fuel handling building
  • Single point lift system
  • Hatch transfer system
  • Upending/downending device
  • Temporary lifting device inside containment
  • Reactor cavity decking
  • Steam generator removal, installation of the replacement steam generators, and transport of the old steam generators to the storage facility The inspector directly observed portions of the movement of each installed steam generator, including in the order of removal: (1)inside containment temporary lifting device lifting and rigging , (2) downending, (3) traversing through the hatch transfer system, (4) single point lift system movements, (5) self-propelled modular transporter travel from the sundeck through the fuel handling building to the outside lift system (6) lifting the outside lift system, and (7) self-propelled modular transporter travel from the outside lift system to the old steam generator storage facility. The inspector also directly observed portions of the installation of the replacement steam generators, which were moved from the replacement steam generator storage facility into containment in reverse order to the old steam generator movements discussed above. The inspector observed a sample of various other activities including the initial lifts, heavy haul routes, and use of the hatch transfer system equipment.

Radiation Protection Program Controls. In addition to the health physics inspections, which are referenced in Section 1.a of this report, the inspector performed the following radiation protection-related inspections: (1) direct inspection of radiation protection personnel coverage and control, as low as reasonably achievable, and dosimetry control activities along load movement path of old steam generator from containment to the old steam generator storage facility; and (2) direct inspection of radiation protection controls and procedure adherence to the old steam generator storage facility.

Steam Generator Hold Down Bolts and Major Structural Modifications. The inspector examined the old steam generator hold down bolts for degradation. The inspector also reviewed documentation and performed direct inspections related to permanent structural modifications made to facilitate steam generator replacement. It should be noted that even though these modifications were treated as permanent, all outside rigging and handling equipment was removed after the replacement of the Unit 1 steam generators. These modifications included the outside lift system platform and the outside lift system tower base frame.

Foreign Material Controls. The inspector directly observed the cutting and grinding of primary and secondary side main steam line piping as well as the foreign material exclusion boundaries and controls in place for the remaining reactor coolant system piping. The inspector also verified foreign material control measures for the reactor coolant system hot and cold legs after old steam generator removal. The inspector also performed engineering reviews of the foreign material controls and reviewed corrective action documents related to foreign material exclusion.

Containment Access and Integrity. Final containment close-out and testing inspections were performed by the resident inspectors and documented in NRC Integrated Inspection Report 05000275/2009002 and 05000323/2009002. It should be noted that no physical modification or cutting was performed on the containment hatch opening during the Unit 1 steam generator replacement outage.

b. Findings

.

No findings of significance were identified.

4OA6 Meetings, Including Exit

The inspector presented the inspection results to Mr. J. Becker, Site Vice President, and other members of the licensee's management staff in person on June 29, 2009. The licensee acknowledged the information presented. Some proprietary information was reviewed during this inspection but no proprietary information was included in this report.

ATTACHMENT: Supplemental Information

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

J. Becker, Site Vice President
W. Guldemond, Director, Site Services
S. Ketelsen, Manager, Regulatory Services
K. Peters, Station Director
M. Somerville, Manager, Radiation Protection
T. Swartzbaush, Manager, Operations
J. Welsch, Director, Operations Services

LIST OF DOCUMENTS REVIEWED

In addition to the documents referred to in the inspection report, the following documents were selected and reviewed by the inspector to accomplish the objectives and scope of the inspection and to support any findings.

For inspection activities documented in other NRC inspection reports, the documents reviewed are listed in the respective report:
PROCEDURES
NUMBER
TITLE REVISION
AD8.ID1 Outage Planning and Management 11
CF4.ID7 Temporary Modifications 20
OM3.ID6 Differing Professional Opinion (DPO) 1
OM7.ID1 Problem Identification and Resolution - Action Requests 30
OM7.ID12 Operability Determination 12
QEP 10.03-1 SGT Procedure: "Care and Maintenance Instruction" 0E1
QEP 10.04
SGT Procedure: "General Housekeeping, Foreign Material Exclusion (FME), and Cleanness Requirement"
1E1
QEP 10.04-1 SGT Procedure: "FMEA Limited Access Poster" 0
QEP 11.01 Work Packages 1
QEP 11.01-1 SGT Work Package Index: "Temporary Power Inside Containment"
0E2
QEP 11.04 SGT Procedure: "Structural and Miscellaneous Steel Installation"
0E1
QEP 12.01 Inspection and Surveillance Planning 1 STP M-45B Containment Inspection When Containment Integrity is Established
Attachment
PROCEDURES
NUMBER
TITLE REVISION
TQ2.ID4 Training Program Implementation 17
TS3.ID2 Licensing Basis Impact Evaluations 24
Design Change Packages (DCPs), Design Change Notices (DCNs), and Licensing Basis Impact Evaluations (LBIEs)
PROCEDURES
NUMBER
TITLE REVISION LBIE 2007-013 RSG Component Modification LBIE 50.59 Evaluation
LBIE 2009-003 Use of Alternative Methodologies for RSGs
DCP 1000000120 Tavg and Tfeed Ranges Program 0 LBIE 2009-004 Tavg and Tfeed Ranges Program Nonconformance/Deficiency Reports
SGT
NCR 1004, November 20, 2008 SGT
NCR 1017, February 1, 2009
SGT
NCR 1019, February 4, 2009 SGT
NCR 1023, February 8, 2009 SGT
NCR 1026, February 9, 2009 SGT
NCR 1029, February 14, 2009 SGT
NCR 1030, February 15, 2009
SGT
NCR 1032, February 16, 2009 SGT
NCR 1033, February 17, 2009 SGT
NCR 1034, February 18, 2009 SGT
NCR 1040, February 23, 2009 SGT
NCR 1048, February 24, 2009 SGT
NCR 1049, February 25, 2009 SGT
NCR 1051, February 25, 2009
SGT
NCR 1054, February 27, 2009 SGT
NCR 1056, March 1, 2009 SGT
NCR 1058, March 2, 2009 SGT
DR-44, January 30, 2009 SGT
DR-47, February 9, 2009
SGT
DR-51, February 23, 2009 SGT
DR-52, February 24, 2009 SGT
DR-53, March 3, 2009
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