ML032320080

License Amendment, Issuance of Amendment Revision to Reactor Pressure Vessel Material Surveillance Program

ML032320080
Person / Time
Site:	Peach Bottom
Issue date:	11/04/2003
From:	George Wunder NRC/NRR/DLPM/LPD1
To:	Skolds J Exelon Generation Co
Wall, S. NRR/DLPM 415-2855
References
TAC MB7006, TAC MB7007
Download: ML032320080 (17)

Text

November 4, 2003 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT RE: REVISION TO THE REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM (TAC NOS. MB7006 AND MB7007)

Dear Mr. Skolds:

The Commission has issued the enclosed Amendments Nos. 249 and 253 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS-2 and 3). These amendments are in response to your application dated December 20, 2002, as supplemented on May 30, 2003.

These amendments authorize the revision of the Updated Final Safety Analysis Report for PBAPS-2 and 3 by allowing implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program as the basis for demonstrating the compliance with the requirements of Appendix H, Reactor Vessel Material Surveillance Program Requirements, to Title 10 of the Code of Federal Regulations, Part 50.

A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA by SWall for/

George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosures:

1. Amendment No. 249 to Renewed DPR-44

2. Amendment No. 253 to Renewed DPR-56

3. Safety Evaluation cc w/encls: See next page

Peach Bottom Atomic Power Station, Units 2 and 3 cc:

Vice President, General Counsel and Rich Janati, Chief Secretary Division of Nuclear Safety Exelon Generation Company, LLC Bureau of Radiation Protection 2301 Market Street, S23-1 Department of Environmental Protection Philadelphia, PA 19101 Rachel Carson State Office Building P.O. Box 8469 Site Vice President Harrisburg, PA 17105-8469 Peach Bottom Atomic Power Station Exelon Generation Company, LLC Board of Supervisors 1848 Lay Road Peach Bottom Township Delta, PA 17314 545 Broad Street Ext.

Delta, PA 17314-9203 Plant Manager Peach Bottom Atomic Power Station Mr. Richard McLean Exelon Generation Company, LLC Power Plant and Environmental 1848 Lay Road Review Division Delta, PA 17314 Department of Natural Resources B-3, Tawes State Office Building Regulatory Assurance Manager Annapolis, MD 21401 Peach Bottom Atomic Power Station Exelon Generation Company, LLC Dr. Judith Johnsrud 1848 Lay Road National Energy Committee Delta, PA 17314 Sierra Club 433 Orlando Avenue Resident Inspector State College, PA 16803 U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station Manager-Financial Control & Co-Owner P.O. Box 399 Affairs Delta, PA 17314 Public Service Electric and Gas Company P.O. Box 236 Regional Administrator, Region I Hancocks Bridge, NJ 08038-0236 U.S. Nuclear Regulatory Commission 475 Allendale Road Manager Licensing-Limerick and Peach King of Prussia, PA 19406 Bottom Exelon Generation Company, LLC Mr. Roland Fletcher Nuclear Group Headquarters Department of Environment Correspondence Control Radiological Health Program P.O. Box 160 2400 Broening Highway Kennett Square, PA 19348 Baltimore, MD 21224 Correspondence Control Desk Exelon Generation Company, LLC 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348

Peach Bottom Atomic Power Station, Units 2 and 3 cc:

Director - Licensing Exelon Generation Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Vice President-Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President-Mid-Atlantic Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President, Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President, Operations Support Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Chief Operating Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

November 4, 2003 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT RE: REVISION TO THE REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM (TAC NOS. MB7006 AND MB7007)

Dear Mr. Skolds:

The Commission has issued the enclosed Amendments Nos. 249 and 253 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS-2 and 3). These amendments are in response to your application dated December 20, 2002, as supplemented on May 30, 2003.

These amendments authorize the revision of the Updated Final Safety Analysis Report for PBAPS-2 and 3 by allowing implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program as the basis for demonstrating the compliance with the requirements of Appendix H, Reactor Vessel Material Surveillance Program Requirements, to Title 10 of the Code of Federal Regulations, Part 50.

A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA by SWall for/

George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosures:

1. Amendment No. 249 to Renewed DPR-44

2. Amendment No. 253 to Renewed DPR-56

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC PDI-2 R/F JClifford GWunder MOBrien (2) OGC ACRS SCoffin JUhle JHoncharik LLois GHill (4) BPlatchek, RGN-I ADAMS Accession Numbers: ML032320080

• SE input provided - no major changes made.

• • See previous concurrence.

OFFICE PDI-2/PM PDI-2/LA EMCB/SC* OGC** PDI-2/SC NAME SWall for GWunder MOBrien SCoffin LZaccari JBoska for JClifford DATE 11/03/03 10/31/03 06/30/03 08/29/03 11/03/03 OFFICIAL RECORD COPY

EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 249 Renewed License No. DPR-44

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated December 20, 2002, as supplemented by letter dated May 30, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended to authorize changes to the Updated Final Safety Analysis Report (UFSAR) to allow implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program as the basis for demonstrating compliance with the requirements of Appendix H, Reactor Vessel Material Surveillance Program Requirements, to 10 CFR Part 50, as set forth in the licensees application dated December 20, 2002, as supplemented by letter dated May 30, 2003.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days. Implementation of the amendment is the incorporation into the UFSAR of the program description set out in the licensees application dated December 20, 2002, as supplemented by letter dated May 30, 2003, and evaluated in the safety evaluation enclosed with this amendment. The licensee shall submit the changes authorized by this amendment with the next update of the UFSAR in accordance with 10 CFR 50.71(e).

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by JBoska for/

James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Date of Issuance: November 4, 2003

EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 253 Renewed License No. DPR-56

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated December 20, 2002, as supplemented by letter dated May 30, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended to authorize changes to the Updated Final Safety Analysis Report (UFSAR) to allow implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program as the basis for demonstrating compliance with the requirements of Appendix H, Reactor Vessel Material Surveillance Program Requirements, to 10 CFR Part 50, as set forth in the licensees application dated December 20, 2002, as supplemented by letter dated May 30, 2003.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days. Implementation of the amendment is the incorporation into the UFSAR of the program description set out in the licensees application dated December 20, 2002, as supplemented by letter dated May 30, 2003, and evaluated in the safety evaluation enclosed with this amendment. The licensee shall submit the changes authorized by this amendment with the next update of the UFSAR in accordance with 10 CFR 50.71(e).

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by JBoska for/

James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Date of Issuance: November 4, 2003

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 249 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AND AMENDMENT NO. 253 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-56 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278

1.0 INTRODUCTION

By application dated December 20, 2002 (Reference 1), as supplemented on May 30, 2003 (Reference 2), Exelon Generation Company, LLC (Exelon or the licensee), requested amendments to revise the Updated Final Safety Analysis Report (UFSAR) for Peach Bottom Atomic Power Station, Units 2 and 3 (PBAPS-2 and 3), by allowing implementation of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) reactor pressure vessel (RPV) integrated surveillance program (ISP) as the basis for demonstrating the compliance with the requirements of Appendix H, Reactor Vessel Material Surveillance Program Requirements, to Title 10 of the Code of Federal Regulations (10 CFR), Part 50. The supplement dated May 30, 2003, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 4, 2003 (68 FR 5669).

The BWRVIP RPV ISP was submitted for NRC staff review and approval in Topical Reports BWRVIP-78, BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan, and BWRVIP-86, BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan, (References 3 and 4). Additional information necessary to establish the technical basis for, and proposed implementation of, the BWRVIP ISP was provided in letters from the BWRVIP to the NRC dated December 15, 2000, and May 30, 2001, (References 5 and 6). The NRC staff approved the proposed BWRVIP ISP in a safety evaluation (SE) which was provided to the BWRVIP by letter dated February 1, 2002, (Reference 7). However, the NRC staffs SE specified that plant-specific information be provided by BWR licensees who wish to implement the BWRVIP ISP for their facilities. The licensees December 20, 2002, and May 30, 2003, submittals addressed the plant-specific information specified the NRC staffs February 1, 2002, BWRVIP ISP SE.

2.0 REGULATORY REQUIREMENTS The NRC staff determined that Exelon, in its December 20, 2002, and May 30, 2003, submittals, identified the applicable regulatory requirements. The regulatory requirements for which the NRC staff based its acceptance are described below.

Appendix H to 10 CFR Part 50 requires nuclear power plant licensees to implement RPV surveillance programs to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region...which result from exposure of these materials to neutron irradiation and the thermal environment. Two specific alternatives are provided with regard to the design of a facilitys RPV surveillance program which may be used to address the requirements of Appendix H to 10 CFR Part 50.

The first alternative is the implementation of a plant-specific RPV surveillance program consistent with the requirements of American Society for Testing and Materials (ASTM)

Standard Practice E 185, Standard Practice for Conduction Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels. In the design of a plant-specific RPV surveillance program, a licensee may use the edition of ASTM Standard Practice E 185 which was current on the issue date of the American Society of Mechanical Engineers Code to which the reactor vessel was purchased, or later editions through the 1982 Edition.

The second alternative provided in Appendix H to 10 CFR Part 50 is the implementation of an ISP. An ISP is defined in Appendix H to 10 CFR Part 50 as occurring when, the representative materials chosen for surveillance for a reactor are irradiated in one or more other reactors that have similar design and operating features. Five specific criteria are stated in Appendix H to 10 CFR Part 50 which must be met to support approval of an ISP:

a. The reactor in which the materials will be irradiated and the reactor for which the materials are being irradiated must have sufficiently similar design and operating features to permit accurate comparisons of the predicted amount of radiation damage.

b. Each reactor must have an adequate dosimetry program.

c. There must be adequate arrangement for data sharing between plants.

d. There must be a contingency plan to assure that the surveillance program for each reactor will not be jeopardized by operation at reduced power level or by an extended outage of another reactor from which data are expected.

e. There must be substantial advantages to be gained, such as reduced power outages or reduced personnel exposure to radiation, as a direct result of not requiring surveillance capsules in all reactors in the set.

As noted above in Section 1.0, the NRC staff approved the proposed BWRVIP ISP in an SE issued to the BWRVIP by letter dated February 1, 2002, (Reference 7). In Reference 7, all of the criteria cited above for approval of an ISP were addressed either completely or partially.

For those criteria which could not be fully addressed in Reference 7, plant-specific information was needed. The NRC staff identified in Reference 7 the specific information which would be

needed from licensees who wished to implement the BWRVIP for their facilities. As stated in Reference 7:

[L]icensees who wish to participate in the BWR ISP must provide, for NRC staff review and approval, information which defines how they will determine RPV and/or surveillance capsule fluences based on the dosimetry data which will be available for their facilities. This information must be submitted concurrently with each licensees submittal to replace their existing plant-specific surveillance program with the BWR ISP as part of their facilitys licensing basis. The information submitted must be sufficient for the staff to determine that:

(1) RPV and surveillance capsule fluences will be established as based on the use of an NRC-approved fluence methodology that will provide acceptable results based on the available dosimetry data; and (2) If one methodology is used to determine the neutron fluence values for a licensees RPV and one or more different methodologies are used to establish the neutron fluence values for the ISP surveillance capsules which represent that RPV in the ISP, the results of these differing methodologies are compatible (i.e., within acceptable levels of uncertainty for each calculation).

This plant-specific information was needed by the NRC staff to ensure that Criterion III.C.1.b of Appendix H to 10 CFR Part 50 for an ISP could be met by each facility and to confirm that data which would be shared as part of the BWRVIP ISP could be effectively utilized by each licensee for the monitoring of RPV embrittlement for their facility.

Regulatory Guide (RG) 1.190, Calculational and Dosimetry Methods For Determining Pressure Vessel Neutron Fluence, describes methods and assumptions acceptable to the NRC staff for determining the pressure vessel neutron fluence. The guide is intended to ensure the accuracy and reliability of the fluence determination required by General Design Criteria 14, 30, and 31 of Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50.

3.0 TECHNICAL EVALUATION

In its application dated December 20, 2002, as supplemented on May 30, 2003, Exelon submitted information for PBAPS-2 and 3 which addressed the plant-specific information requested in the NRC staffs SE approving the BWRVIP ISP (Reference 7). Exelon provided revised Section 4.2.5.1.4 of the PBAPS-2 and 3 UFSAR which stated in part:

PBAPS RPV fluence has been evaluated using a method in accordance with the recommendations of RG 1.190. Future evaluations of RPV fluence will be completed using a method in accordance with the recommendations of RG 1.190.

RG 1.190 was developed to provide state-of-the-art calculations and measurement procedures that are acceptable to the NRC staff for determining pressure vessel fluence. Although the NRC staff would note that the guidance in RG 1.190 is not a regulatory requirement of the NRC, the staff has concluded that the inclusion of this statement in the PBAPS-2 and 3 UFSAR

is sufficient to address both items (1) and (2) from Reference 7. Regarding item (1), the licensees use of a methodology for determining PBAPS-2 and 3 RPV neutron fluence values which is consistent with the attributes of RG 1.190 and has been approved by the NRC staff will provide acceptable results based upon the available dosimetry data. Regarding item (2), RPV surveillance capsules tested under the BWRVIP ISP will have their fluences determined by the use of a methodology which is consistent with the attributes of RG 1.190 and has been approved by the NRC staff. The NRC staff has concluded that any two (or more) different fluence methodologies will provide compatible (as defined in Reference 7) results provided that the best estimate fluence values are within each others uncertainty bounds.

The licensee proposed a revision to Section 4.2.6 of the PBAPS-2 and 3 UFSAR which documented the licensees incorporation of the BWRVIP ISP into the PBAPS-2 and 3 licensing basis. Relevant excerpts from the PBAPS-2 and 3 UFSAR section is provided below:

In 2003, the NRC approved PBAPS participation in the BWR Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) as described in BWRVIP-86-A (Reference 1) [BWRVIP-86-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP), Final Report, October 2002]. The NRC approved the ISP for the industry in Reference 1 and approved PBAPS participation...The ISP meets the requirements of 10 CFR 50 Appendix H and provides several advantages over the original program...The current withdrawal schedule for both units is based on the NRC-approved revision of BWRVIP-86-A (Reference 1).

In addition, Exelon provided, in proposed Section 4.2.6 of the PBAPS-2 and 3 UFSAR, the withdrawal schedule for PBAPS-2 and 3 in accordance with the NRC staff-approved BWRVIP-86.

The NRC staff has concluded that the information provided in the revised PBAPS-2 and 3 UFSAR is adequate to document the licensees intent to appropriately implement the BWRVIP ISP as the method for demonstrating the compliance of PBAPS-2 and 3 with the requirements of Appendix H to 10 CFR Part 50.

Based on the above, the NRC staff has concluded that the information provided by the licensee was sufficient to conclude that the BWRVIP ISP, as approved in Reference 7, can be implemented for PBAPS-2 and 3 as the basis for demonstrating continued compliance with the requirements of Appendix H to 10 CFR Part 50. As part of the implementation of this amendment and documentation of the licensees intent to utilize the BWRVIP ISP for this purpose, the licensee shall modify the PBAPS-2 and 3 UFSAR as stated in its December 20, 2002, and May 30, 2003, submittals. This document is controlled in accordance with the requirements of 10 CFR 50.59, Changes, tests, and experiments.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (68 FR 5669). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

1. M. P. Gallagher, Exelon, to U.S. NRC Document Control Desk, Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule, December 20, 2002.

2. K. R. Jury, Exelon, to U.S. NRC Document Control Desk, Additional Information Supporting the Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule, May 30, 2003.

3. C. Terry, BWRVIP, to U.S. NRC Document Control Desk, Project No. 704 - BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan (BWRVIP-78), December 22, 1999.

4. C. Terry, BWRVIP, to U.S. NRC Document Control Desk, Project No. 704 -

BWRVIP-86: BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan, [Electric Power Research Institute] EPRI Technical Report 1000888, December 22, 2000.

5. C. Terry, BWRVIP, to U.S. NRC Document Control Desk, Project No. 704 - BWRVIP Response to NRC Request for Additional Information Regarding BWRVIP-78, December 15, 2000.

6. C. Terry, BWRVIP, to U.S. NRC Document Control Desk, Project No. 704 - BWRVIP Response to Second NRC Request for Additional Information on the BWR Integrated Surveillance Program, May 30, 2001.

7. W. H. Bateman, NRC, to C. Terry, BWRVIP, Safety Evaluation Regarding EPRI Proprietary Reports BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan (BWRVIP-78) and BWRVIP-86: BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan, February 1, 2002.

Principal Contributors: J. Honcharik L. Lois Date: November 4, 2003