ML040850657
| ML040850657 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/19/2004 |
| From: | Meena Khanna NRC/NRR/DLPM/LPD4 |
| To: | Overbeck G Arizona Public Service Co |
| Khanna M, NRR/DLPM/EMCB, 415-2150 | |
| Shared Package | |
| ML040850665 | List: |
| References | |
| TAC MC1069, TAC MC1070, TAC MC1071 | |
| Download: ML040850657 (18) | |
Text
March 19, 2004 Mr. Gregg R. Overbeck Senior Vice President, Nuclear Arizona Public Service Company P. O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 -
ISSUANCE OF AMENDMENT ON CONTAINMENT TENDON SURVEILLANCE PROGRAM AND CONTAINMENT LEAKAGE RATE TESTING PROGRAM (TAC NOS. MC1069, MC1070, AND MC1071)
Dear Mr. Overbeck:
The Commission has issued the enclosed Amendment No. 151 to Facility Operating License No. NPF-41, Amendment No. 151 to Facility Operating License No. NPF-51, and Amendment No. 151 to Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated October 7, 2003, as supplemented by letter dated December 18, 2003.
The amendment revises Technical Specification (TS) Section 5.5.6, "Containment Tendon Surveillance Program," for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC. The amendment also deletes the provisions of Surveillance Requirement (SR) 3.0.2 from this TS. In addition, the amendment revises TS 5.5.16, "Containment Leakage Rate Testing Program," to add exceptions to Regulatory Guide 1.163, "Performance-Based Containment Leak-Testing Program." Also, the paragraphs in Section 5.5.16 have been sequenced to more clearly separate the requirements of the program. This is considered an administrative change and is consistent with the guidance in NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 2.
G. Overbeck A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Meena Khanna, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No. 151 to NPF-41
- 2. Amendment No. 151 to NPF-51
- 3. Amendment No. 151 to NPF-74
- 4. Safety Evaluation cc w/encls: See next page
G. Overbeck A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Meena Khanna, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No.151 to NPF-41
- 2. Amendment No.151 to NPF-51
- 3. Amendment No.151 to NPF-74
- 4. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
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- previously concurred OFFICIAL RECORD COPY
ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated October 7, 2003, and its supplement dated December 18, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:
(A)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 151, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19, 2004
ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. NPF-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated October 7, 2003, and its supplement dated December 18, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:
(A)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 151, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19, 2004
ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. NPF-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated October 7, 2003, and its supplement dated December 18, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:
(A)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 151, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19, 2004
ATTACHMENT TO LICENSE AMENDMENT NOS. 151, 151, AND 151 FACILITY OPERATING LICENSE NOS. NPF-41, NPF-51, AND NPF-74 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
REMOVE INSERT 5.5-4 5.5-4 5.5-23 5.5-23 5.5-24 5.5-24
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO. NPF-41, AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO. NPF-51, AND AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO. NPF-74 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530
1.0 INTRODUCTION
By application dated October 7, 2003, and its supplement dated December 18, 2003, Arizona Public Service Company, et al. (the licensee) requested changes to the Technical Specifications (TSs, Appendix A to Facility Operating License Nos. NPF-41, NPF-51, and NPF-74) for the Palo Verde Generating Station, Units 1, 2, and 3 (PVGS). The proposed amendments would revise TS Section 5.5.6, "Containment Tendon Surveillance Program," for consistency with the requirements of Section 50.55a(g)(4) of Title 10 of the Code of Federal Regulations (10 CFR) for components classified as Code Class CC. The licensees proposed revision to TS 5.5.6 is to indicate that the Containment Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code and the applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC. The licensee has also proposed to delete the provisions of Surveillance Requirement (SR) 3.0.2 from this TS. In addition, the licensee proposed to revise TS 5.5.16, "Containment Leakage Rate Testing Program," to add exceptions to Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Testing Program." The licensee also provided, in its application, the corresponding changes to the TS Bases for SR 3.6.1.1. In addition, the paragraphs in Section 5.5.6 have been sequenced to more clearly separate the requirements of the program. This is considered an administrative change and is consistent with the guidance in NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 2.
The December 18, 2003, supplemental letter provided revised technical specification pages to reflect changes that were approved in Amendment No. 149, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on December 9, 2003 (68 FR 68659).
2.0 REGULATORY REQUIREMENTS Section 50.55a(b)(2)(vi) of 10 CFR requires that licensees use either the 1992 Edition with the 1992 Addenda or the 1995 Edition with the 1996 Addenda of Subsection IWE and Subsection IWL of the ASME Code, as modified and supplemented by the requirements in paragraphs (b)(2)(viii) and (b)(2)(ix) of 10 CFR 50.55a when implementing the initial 120-month inspection interval for the containment inservice inspection requirements of 10 CFR 50.55a.
Section 50.55a(g)(4) of 10 CFR requires that throughout the service of a boiling or pressurized water-cooled nuclear power facility, components which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements set forth in Section XI of editions of the ASME Code and Addenda that become effective subsequent to editions specified in paragraphs (g)(2) and (g)(3) of 10 CFR 50.55a and that are incorporated by reference in paragraph (b) of 10 CFR 50.55a, to the extent practical within the limitations of design, geometry and materials of construction of the components.
10 CFR 50.54(o) requires that primary reactor containments for water cooled power reactors, other than facilities for which the certifications required under 10 CFR 50.82(a)(1) have been submitted, shall be subject to the requirements set forth in Appendix J to this part.
3.0 TECHNICAL EVALUATION
3.1 Proposed Changes to Technical Specifications In its application, the licensee proposed the following changes to TSs 5.5.6 and 5.5.16:
1.
TS 5.5.6 - at the end of the first paragraph after the phrase "in accordance with," the phrase "Regulatory Guide 1.35, as described in Section 1.8 of the USAR" would be replaced by the phrase "ASME Code Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC."
2.
TS 5.5.6 - SR 3.0.2 would be deleted from the second paragraph. If SR 3.0.2 is applicable, then the interval, as specified in the TS, may be extended up to 1.25 times that interval.
3.
TS 5.5.16.a (revised sequenced paragraph) - at the end of the paragraph, the following is added to modify compliance with RG 1.163: "as modified by the following exceptions to: (1) the visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Code Section XI, Subsection IWL, except where relief has been authorized by the NRC. The containment concrete visual examinations may be performed during either power operation, e.g., performed concurrently with other containment inspection-related activities such as tendon testing, or during a maintenance/refueling outage. (2) The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Code Section XI, Subsection IWE, except where relief has been authorized by the NRC."
4.
TS 5.5.16 - the paragraphs have been sequenced to more clearly separate the requirements of the program. This is considered an administrative change. The staff noted that a typographical error was made in the submittal with respect to this item. The licensee indicated, in the submittal, that this change was for the paragraphs in Section 5.5.6; however, the section should be 5.5.16. The staff discussed this with the licensee via telecon on January 21, 2004.
The proposed amendment modifies the requirements on containment tendon surveillance and containment leakage rate testing programs. It does not change the design requirements on the containment.
As proposed in item 1 above, the containment tendon surveillance program and its inspection frequencies and acceptance criteria are proposed to be changed from that specified in draft Revision 3 of RG 1.35, "Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments" to that specified in Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an exemption or relief has been authorized by the NRC. Item 2 deletes SR 3.0.2 from TS 5.5.6.
As proposed in item 3, the amendment would not change the current requirements that the leakage rate testing program shall meet the requirements of 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B, as modified by approved exemptions. However, the current requirement that the program shall be in accordance with RG 1.163 shall be modified by adding two exceptions to the RG.
3.2 Evaluation The requirements of 10 CFR 50.55a were amended (61 FR 41303) to incorporate, by reference, Subsections IWE and IWL of Section XI of the ASME Code, for the inspection of containments of light water-cooled reactors. Subsection IWE provides the requirements for inservice inspection, repair, and replacement of Class MC pressure retaining components, and metallic shell and penetration liners of Class CC pressure retaining components, and their integral attachments. Subsection IWL provides the requirements for preservice examination, inservice inspection and repair of the reinforced containments.
Currently, TS 5.5.6 states in part, "The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance criteria shall be in accordance with Regulatory Guide 1.35, as described in Section 1.8 of the UFSAR." The regulation covering the ISI of the containment tendons is 10 CFR 50.55a(g)(4). This requires that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code and Addenda that become effective subsequent to editions specified in...
The licensee has proposed to replace the reference to Regulatory Guide 1.35, as described in Section 1.8 of the UFSAR, by a reference to the regulations and to the specific subsection of Section XI of the ASME Code for containment tendons (IWL). Because the licensee has proposed the specific regulatory requirements for the containment tendon surveillance program, the staff concludes that the proposed change is acceptable.
Additionally, since the tendon inspection frequencies will be in accordance with ASME Section XI, Subsection IWL, the provisions of SR 3.0.2 are no longer necessary and are deleted from TS 5.5.6. As such, 10 CFR 50.55a requires the implementation of ASME Section XI, Subsection IWL, and specifies the requirements for extending inspection frequencies. Based on this, the staff concludes that deletion of SR 3.0.2 from TS 5.5.6 is acceptable.
For PVNGS TS 5.5.16, the licensee stated in its application that:
Currently, PVNGS TS 5.5.16 contains requirements for the containment leakage rate testing program, and it specifies that the program shall be in accordance with the guidelines contained in RG 1.163. Regulatory Position C.3 of the regulatory guide states that Section 9.2.1, Pretest Inspection and Test Methodology, of NEI 94-01 provides guidance for the visual examination of accessible interior and exterior surfaces of the containment system for structural problems. These examinations should be conducted prior to initiating a Type A test, and during two other refueling outages before the next Type A test if the interval for the Type A test has been extended to 10 years, in order to allow for early uncovering of evidence of structural deterioration. There are no specific requirements in NEI 94-01 for the visual examination except that it is to be a general visual examination of accessible interior and exterior surfaces of the primary containment components.
The licensee proposes to modify TS 5.5.16 to specify that:
In addition to the requirements of RG 1.163 and NEI 94-01, the concrete surfaces of the containment must be visually examined in accordance with the ASME Section XI Code, Subsection IWL, and the liner plate inside containment must be visually examined in accordance with Subsection IWE. The frequency of visual examination of the concrete surfaces per Subsection IWL is once every five years, and the frequency of visual examination of the liner plate per Subsection IWE is, in general, three visual examinations over a 10-year period. The visual examinations performed pursuant to Subsection IWL may be performed at any time during power operation or during shutdown, and the visual examinations performed pursuant to Subsection IWE are performed during refueling outages, since this is the only time that the liner plate is fully accessible.
As a result of this modification to TS 5.5.16, one less visual examination will be conducted during the 10-year interval. The licensee indicated, however, that the requirements of Subsection IWE and IWL are more rigorous than those performed pursuant to RG 1.163 and NEI 94-01. Further, the licensee stated that with respect to examinations performed pursuant to both Subsections IWL and IWE, visual examinations of both the concrete surfaces and the liner plate must be reviewed by an inspector regularly employed by an insurance company authorized to write boiler and pressure vessel insurance, in accordance with IWA-2110 and IWA-2120 of the ASME Code. The staff agrees that the combination of the Code requirements for the visual examinations plus the third party review will offset the fact that there will be one less visual examination during the 10-year interval.
The regulation 10 CFR 50.55a(b)(2)(ix)(E) states, a general visual examination as required by Subsection IWE must be performed once each period. For Palo Verde, the IWE requirements of their Code of record, which is the 1992 Edition of the ASME Code, requires the general visual examination prior to each Type A test. With the relaxation of leak rate test frequencies in Option B of Appendix J, these examinations may be performed at 10 or 15 years, as indicated in the Palo Verde TS, which is less restrictive than the frequency specified in 10 CFR 50.55a(b)(2)(ix)(E). However, because the operating license requires the licensee to comply with both the technical specifications and the regulations, the licensee will be required to comply with the more restrictive interval specified in the regulations.
Therefore, in operating Palo Verde, the licensee must meet the requirements in both the technical specifications and the regulations and, if both documents should specify different frequencies for the same surveillance, in this case, a general visual examination of the steel containment liner plate, the licensee must follow the more restrictive frequency. By following the more restrictive frequency, the license is complying with both sets of requirements. The licensee stated as such in its application. Also, in a conference call with the licensee on February 11, 2004, the licensee indicated that when it adopts its next Code of record, the new Code of record is not anticipated to be different than 10 CFR 50.55a(b)(2)(ix)(E).
Based on the previous paragraph, the staff concludes that the proposed amendment, with respect to TS 5.5.16, complies with 10 CFR 50.55a(g)(5)(ii), in that the licensee's ISI program is in compliance with both the regulations and the technical specifications.
The staff agrees with the licensee that the visual examinations of the containment concrete surfaces and the liner plate performed pursuant to Subsections IWL and IWE, respectively, are more rigorous than those performed pursuant to RG 1.163 and NEI 94-01. The requirements in Subsections IWL and IWE of the ASME Code constitute acceptable requirements for the inspection of the concrete surfaces and the liner plate in the Palo Verde containment, in that the requirements in Subsections IWL and IWE meet 10 CFR 50.55a(b)(2)(vi) and 50.55a(g)(4).
Therefore, the staff finds that the insert proposed with respect to TS 5.5.16 is acceptable.
The last proposed revision is in regard to the administrative change of the sequencing of paragraphs in TS Section 5.5.16, to more clearly separate the requirements of the program.
The staff agrees with the licensee that this is consistent with the guidance in NUREG-1432.
Therefore, the staff finds the licensees administrative change acceptable.
3.3 Conclusions Based on the above conclusions and the proposed amendments being consistent with Section XI of the ASME Code, the staff concludes that the proposed amendments are acceptable, except for the reformatting proposed for TS 5.5.16. This reformatting is addressed below in Section 3.4. Also, after its review of the TS Bases changes for SR 3.0.2, SR 3.6.1.1, and SR 3.6.1.2, which are in the licensees application, the staff has no disagreement with the licensees identified changes to the TS Bases for the SR.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arizona State Official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the surveillance requirements. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (69 FR 700). Accordingly, the amendment meets 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 amendment.
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 Commission's 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.
Principal Contributor: Meena Khanna Date: March 19, 2004
Palo Verde Generating Station, Units 1, 2, and 3 cc:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007 Douglas Kent Porter Senior Counsel Southern California Edison Company Law Department, Generation Resources P.O. Box 800 Rosemead, CA 91770 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 40 Buckeye, AZ 85326 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Chairman Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor Phoenix, AZ 85003 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, AZ 85040 Mr. M. Dwayne Carnes, Director Regulatory Affairs/Nuclear Assurance Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072-2034 Mr. Hector R. Puente Vice President, Power Generation El Paso Electric Company 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004 Mr. John Taylor Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Albuquerque, NM 87107-4224 Ms. Cheryl Adams Southern California Edison Company 5000 Pacific Coast Hwy Bldg DIN San Clemente, CA 92672 Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, AZ 85251 Terry Bassham, Esq.
General Counsel El Paso Electric Company 123 W. Mills El Paso, TX 79901 Mr. John Schumann Los Angeles Department of Water & Power Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100 Brian Almon Public Utility Commission William B. Travis Building P. O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326