ML17298B778
| ML17298B778 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/14/1984 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8501040189 | |
| Download: ML17298B778 (28) | |
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Docket No.:
50-528 Mr. E.
E.
Van Brunt, Jr.
Vice President - Nuclear Projects Arizona Public Service Company Post Office Box 21666 Phoenix, Arizona 85036
Dear Mr. Van Brunt:
DI-STRIBUT-ION,'
et NRC PDR L PDR NSIC PRC System LBP3 R/F JLee ELicitra TNovak OELD RHeischman EJordan NGrace ACRS (16)
Subject:
Palo Verde Nuclear Generating Station, Unit 1 Draft License As you are aware, the staff is preparing a license for the Palo Verde Nuclear Station, Unit 1.
Enclosed is a draft copy of the license.
It is provided for your information, review and comment to insure that it accurately reflects the commitments required of you as described in the
We request that you review the draft license and provide any comments in writing by December 20I, 1984.
For any questions regarding this draft license, contact the Palo Verde Project
- Manager, Mr. E. A. Licitra at (301) 492-7200.
Sincerely,
Enclosure:
As stated cc:
See next page Thomas M. Novak, Assistant Director for Licensing Division of Licensing LB43:DLQj LBB3:
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Palo Verde Mr. E.
E.
Van Brunt, Jr.
Vice President
- Nuclear Projects Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Arthur C. Gehr, Esq.
Snell 5 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. James M. Flenner, Chief Counsel Arizona Corporation Commission 1200 West Washington Phoenix, Arizona 85007 Charles R. Kocher, Esq. Assistant Counsel James A. Boeletto, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, Cal ifornia 91770 Ms. Margaret Walker Deputy Director of Energy Programs Economic Planning and Development Office 1700 West Washington Phoenix, Arizona 85007 Mr. Rand L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Resident Inspector Palo Verde/NPS U.S. Nuclear Regulatory Commission P. 0.
Box 21324 Phoenix, Arizona 85001 Ms. Patricia Lee Hourihan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator - Region V
U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596..
Kenneth Berlin, Esq.
Winston
& Strawn Suite 500 2550 M Street, NW Washington, DC 20037 Ms. Lynne Bernabei Government Accountability Project of the Institute for Policy Studies 1901 Que Street, NW Washington, DC 20009 Ms. Jill Morrison 522 E. Colgate Tempi, Arizona 85238
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY 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 SOUTHERN CALIFORNIA PUBLIC POWER AUTHORITY DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 FACILITY OPERATING LICENSE License No.
NPF-34 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for license filed by Arizona Public Service
- Companv, on behalf of itself and the Salt River Project Agricultural Improve-ment 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 (licensees),
complies with the standards and requirements of the Atomic Energy Act of 1954, as
- amended, and the Commission's reaulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Palo Verde Nuclear Generating Station, Unit 1
(facility) has been substantially completed in conformity with Construction Permit No.
CPPR-141 and the application, as
- amended, the provisions of the Act and the regulations of the Commission; C.
The facility will operate in conformity with the application, as
- amended, the provisions of the Act, and the regulatiqps of-the Commission (except as exempted from compliance in Section 2.D below);
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D.
There is reasonable assurance:
(i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10- CFR Chapter I (except as exempted from compliance in Section 2.D below);
E.
Arizona Public Service Company* is technically qualified to enqage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The licensees have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnitv Agreements",
of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No.
NPF-34 subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51, of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoing findings-, the Initial Decision issued by the Atomic Safety and Licensing Board dated December 30, 1982, and the Decision issued by the Atomic Safety and Licensing Appeal Board dated February 15, 1983 (ALAB-713), regarding this facility, Facility Operating License Ho.
NPF-34 is hereby issued to the Arizona Public Service Company, Salt River Proiect 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 (licensees) to read as follows:
- r>zona u
ic ervice Company is authorized to act as agent for'alt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Comp'any, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern Califnrnia Public Power Authority and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
(
A.
This license applies to the Palo Verde Nuclear Generating Station, Unit I, a pressurized water reactor and associated equipment (facility) owned by the licensees.
The facility is located on the"licensees'ite in Maricopa County, Arizona and is described in the licensees'inal Safety Analysis Report, as supplemented and amended through Amendment No. 13, and as further amended as described in a letter bv Arizona Public Service
- Company, ANPP-
, dated
- in the related CESSAR Final Safety Ana'lysis Report, as sup~pemented and amended through Amendment No. 9, and as further amended as described in a letter by Arizona Public Service
- Company, ANPP-
, dated
- and in their Environmental
- Report, as sup~p emented and amenaae through Supplement No. 4.
B.
Subject to the conditions and requirements incorporated
- herein, the Commission hereby licenses:
( l)
Pursuant to Section 103 of the Act and 10 CFR Part 50, Arizona Public Service Company, 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 to possess, and Arizona Public Service Company (APS) to use and -operate the facility at the designated location in Maricopa County, Arizona, in accordance with the procedures and limitations set forth in this license; (2)
Pursuant to the Act and 10 CFR Part 70, APS to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the licensees'inal Safety Analysis Report, as supplemented and amended through Amendment No.
13 and the CESSAR Final Safety Analysis Report as supplemented and amended through Amendment No. 9.
(3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, APS to
- receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor
- startup, sealed sources for reactor instrumentation and radia-tion monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Part 30, 40 and 70, APS to
- receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis orrimtrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, APS to,
- possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
a rf" I
VI 11 l
l t) l C.
This license shall be deemed to contain and is sub,iect to the conditions specified in the Commission's regulations set fo'rth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(I)
Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3800 megawatts thermal (100K power) in accordance with the conditions specified herein and in Attachment I to this license.
The pre-operational
- tests, startup tests and other items identified in Attachment I to this license shall be completed as specified.
'ttachment I is hereby incorporated into this license.
Pending Commission approval, this.license is restricted to power levels not to exceed 5 percent of full power (190 megawatts thermal);
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, are hereby incorporated into this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan; (3)
Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license; (4) 0 eratin Staff Ex erience Re uirements Prior to initial criticality, APS shall have operators on each shift who meet the requirements described in Attachment 2.
Attachment 2 is hereby incorporated into this license.
(5)
Initial Test Pro ram (Section 14, SER and SSER 2)*
APS shall conduct the post-fuel loading initial test program set forth in Section 14 of the FSARs (Palo Verde and CESSAR),
as
- amended, without making any modifications to this program unless such modifications have prior NRC approval.
Major modifications are defined as:
e parent etica notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
(a)
(b)
(c)
(d)
(e)
Elimination of any safety-related test*
Modification of objectives, test methods, or acceptance criteria for any safety-related test Performance of any safety-related test at a power level different from that stated in the FSAR by more than 5
percent of rated power Failure to satisfactorily complete the entire initial startup test program by the time core burnup equals 120 effective full power days Deviation from initial test program administrative procedures or quality assurance controls described in the FSAR Delays in the test program in excess of 30 days (14 days if power level exceeds 50 percent),
concurrent with power operation.
If continued power operation is desired during a delay, APS shall provide,iustification that adequate testing has been performed and evaluated to demonstrate that the facility can be operated at the planned power level with reasonable assurance that the health and safety of the public will not be endangered.
(6)
Environmental gualification (Section 3. 11, SSER 7)
Prior to November 30,
- 1985, APS shall environmentally qualify all electrical equipment according to the provisions of 10 CFR 50.49.
(7)
Fire (a)
(b)
Protection Pro ram (Section 9.5. 1, SSFR 6 and SSER 7) the licensees shall maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment No.
13 and as provided in the SER through Supplement 7, subject to provisions (b) 5 (c) below.
The licensees may make no change in features of the approved fire protection program which would decrease the level of fire prntection in the plant without prior approval of the Comnission.
To make such a change the licensees must submit an application for license amendment pursuant to 10 CFR 50.90.
i
't. i Iii -ii.
i i and operation of safety-related
- systems, structures, and equioment.
P'r~~
gad ak (c)
The licensees may make changes to features of the approved fire protection program which do not decrease the level of fire protection without prior Comnission approval, provided:
(i) such changes do not otherwide involve a change in a
license condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59),
and (ii) such changes do not result in failure to carry out the fire protection program approved by the Comnission prior to license issuance.
The licensees shall maintain, in an auditable
- form, a
current record of all such changes including an analysis of the effects of the change on the fire protection proqram and shall make such records available to NRC inspectors upon request.
All changes to the approved program made without prior Commission approval shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses.
(8)
ICCI S stem (Section II.F.2, SSER 6)
Prior to initial criticality, APS shall revise the emergency operating procedures to reflect staff comments in SSER 6 on the use of the reactor vessel level monitoring system.
Prior to exceeding five percent
- power, APS shall submit a report for the ICCI system as described in Appendix D to SER Supplement No. 6.
(9)
Emer enc Pre aredness In the event that the NRC finds that the lack nf progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
( 10)
Results of Pi in Vibration Test Pro ram (Section 3.9.2, SER)
Three months following completion of the piping vibration test program performed during initial startup, APS shall submit a
summary of the results which demonstrate that the vibration of piping systems is within acceptable levels.
<<r 'r>>
(ll) Initial Inservice. Ins ection Pro ram (Sections 5.2.4 and Four months prior to the first refueling outaqe, APS shall submit the initial inservice inspection program for staff approval.
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(12)
Condensate/Feedwater S stem Test (Section 10.4.7, SER)
APS shall perform a test of the condensate/feedwater system with the plant at approximately 15 percent of full power tn demonstrate that damaging feedwater/steam generator water hammers will not occur.
(13)
Guide Tube i<ear Surveillance (Section 7.2.5, SSER 2)
Six months prior to the first refueling outage, APS shall submit the details of the fuel assembly guide tube fretting wear inspection program for staff review and approval.
APS shall perform the approved inspection program during the first refueling.
(14)
Fuel Rod Growth (Section 4.2.4, SSER 5)
Prior to startup following the first refueling outage, should generic resolution not be reached, APS shall provide surveillar ce results or modifications which assure that the shoulder gap clearance is adequate.
( 15)
Loose Parts Monitorin S stem (Section 4.4.l, SSER 5)
Three months following completion of the start-up tests, system calibration, and estabishment of the alert level for the loose parts monitoring system, APS shall submit a report for the
- system, as described in SSER 5.
(16)
(RESERVED FOR SALEM ATMS CONDITION)
(17)
(RESERVED FOR PASS CONDITION)
(18)
RESERVED FOR E
RELIEF RE UESTS)
(19)
(RESERVED FOR OTHER RELIEF REQUESTS)
I (20)
Su lement Nn.
1 to NUREG-0737 Re uirements (a)
Three months after the staff issues its evaluation of Revision 2 to the CE Owners Group emergency procedure guidelines (CEN-152), dated May 8, 1984, APS shall provide a schedule for revising (i) the Procedure Generation Package to be in conformance with Revision 2 to CEN-152, as modified by the staff's evaluation, and (ii) the emergency operating procedures to be in conformance with the revised Procedure Generation Package.
(b)
(Reserved for DCRDR license condition)
(c)
- By February 28, 1985, APS shall submit a safety analysis for the safety parameter display system
( Item I.D.2) which includes the bases for parameter selection.
The system shall not be used by the operators until the staff has approved its use.
(d)
By May 31, 1985, APS shall implement the provisions of Regulatory Guide 1.97, Revision 2, as described in the APS submittal dated April 14, 1983 and modified by APS letters August 1, 1984, December 5, 1984 and December 5,
1984.
(21)
Radiochemistr Laborator (Section 7.3. 1.5(3),
Emerqenc Plan)
APS shall maintain and operate the Palo Verde, Unit 2 radiochemistry laboratory as part of the Palo Verde, Unit 1 facility under this Part 50 license authorization, in accordance with the commitments made in their letter ANPP-30937, dated October 24, 1984, until the Unit 2 facility is issued a Part,50 license.
D.
(Reserved for Appendix J Exemption)
E; The licensees shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to the authority of 10 CFR 50.54(p).
The approved plans, which contain Safeguards Information as described in 10 CFR 72.21, are collectively entitled "Palo Verde Nuclear Generating Station Security Plan" Amendment 4, dated March 1983 (transmittal letter dated August 19, 1983) including a Chapter 8 contingency plan, (Note:
The March 1983 submittal of Amendment 4 replaces all previous submittals to become the document of record)
Amendment 5 dated December 2, 1983, Amendment 6 dated March 1984 <transmitt~. letter dated June 17, 1984),
and-Amendment 7 dated October 19'84 (transmittal letter dated November --15, 1984),
and "Palo Verde Nuclear Generating Station Training and gualification Plan" dated February 1, 1980, as revised November 20, 1981.
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F.
The licensees shall report any violations of the requirements contained in Section 2 Items C.(1), C.(3) through C.(26) of this license.
The initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with the provisions of 10 CFR 50.72 with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b),
(c) and (e);
G.
~'.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as
- amended, to cover public liability claims; and I
This license is effective as of the date of issuance and shall expire at midnight on
. (40 years after the date of issuance}.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosures:
Harold R. Denton, Director Office of Nuclear Reactor Regulation 1.
Attachment I (to be provided)
- 2. -
Operating Staff Experience Requirements 3.
Appendix A-Technical Specifications (to be provided) 4.
Appendix B-Environmental Protection Plan 5.
Appendix C-Antitrust Conditions Date of Issuance:
I 1
I ij i
ATTACHMENT 2 Palo Verde Nuclear Generating Station, Unit 1
Operating License NPF-34 0 eratin Staff Ex erience Re uirements APS shall have a licensed senior operator on each shift who has had at least six months of hot operatinq experience on a
same type plant including at least six weeks at power levels greater then 20% of full power, and who has had startup and shutdown experience.
For those shifts where such an indivdual is not available on the plant staff, an advisor shall be provided who has had at least four years of power plant experience, including two years of nuclear plait experience, and who has had at least one year of experience on shift as
'=-a 'licensed senior operator at a similar type facility.
Use of advisors who were licensed only at the RO level will be evaluated on a case-by-case basis.
Advisors shall be trained on plant procedures, technical specifications and plant systems, and shall be examined on these topics at a level sufficient to to assure familiarity with the plant.
For each shift, the remainder of the shift crew shall be trained in the role of the advisors.
The training of the advisors and remainder of the shift crew shall-be completed prior to initial criticality.
Prior to initial criticality, APS shall certify to the NRC the names of the advisors who have been examined and have been determined to be competent to provide advice to the operating shifts.
These advisors, or fully trained and qualified replacements shall be retained until the experience levels identified in the first sentence above have been achieved.
Any replacement advisors shall be certified by APS prior to these individuals being placed on shift.
The NRC shall be notified at least 30 days prior to the date APS proposes to release the advisors from further service.
sl II
ASSESSMENT OF THE EFFECT OF LICENSE DURATION ON THE MATTERS DISCUSSED N
L R
N L
PALO N
RGNRTINGST I, UN, AND3.
INTRODUCTION The Final Environmental Statement (FES) for the operation of the Palo Verde Nuclear Generating Station, Units I, 2 and 3
(PVNGS 1-3) was published in February 1982.
At that time it was staff practice to issue operating licenses
.for a period of 40 years from the date of issuance of the construction permit.
This was approximately 30 years of operating life.
However, since the applicants have requested in their applicatinn that the operating licenses (OL) for PYNGS 1-3 then under consideration by the staff, have a duration of 40 years from the date of OL issuance, an assessment contained herein is made for those issues affected by the 40-year duration.
DISCUSSION The staff reviewed the PVNGS 1-3 FES to determine which aspects condidered in the FES are affected by the duration of the operating license.
In general, the FES assesses various impacts associated with operation of the facility in terms of annual impacts and balances these against the anticipated annual energy production benefits.
- Thus, the overall assessment and conclusions would not be dependent on specific operating life.
There are,
- however, two areas in which a specific operating life was assumed.
These are as follows:
1.
Radiological assessment are based on a 15-year, plant midlife.
2.
Uranium fuel cycle impacts are based on 30 years of operation.
EVALUATION The staff's appraisal of the significance of the use of 40 years of operations rather than 30 as it affects the two areas above is presented in the following discussions:
1.
Radioloqical Assessment
- The NRC staff calculated dose comitments to t e uman popu ation residinq around nuclear power reactors to assess the impact on people from radioactive material released from these reactors.
The annual dose commitment is calculated to be the dose that would be received over a 50-year period followino the intake of radio-activity for one year under the conditions that would exist 15 years after the plant began operation.
The 15-year period is chosen as representinq the midpoint of plant operation and is incorporated into the dose models by allowing for buildup of long life radionuclides in the soil. It affects the estimated doses only for radionuclides ingested by humans that have half-lives greater than a few years.
For a plant licensed for 40 years, increasing the buildup period
from 15 to 20 years would increase the dose from long life radionuclides via the ingestion pathways by 10% at most.
It would have, much less effect on dose from shorter life radionuclides.
Table C-4 of the PVNGS 1-3 FES indicates that the estimated doses via the ingestion pathways are well below the regulatory design objectives.
For example, the ingestion dose to the thyroid from PVNGS Unit 1 is 1.8 mrem/yr compared to an Appendix I design objective of 15 mrem/yr.
- Thus, an increase of even as much as 10% in these pathways would remain well below the Appendix I guidelines and would not be significant.
2.
Uranium Fuel Cycle Im acts - The impacts of the uranium fuel cycle are
~'se on years o
operation of a model LWR.
The fuel requirements for the model LWR are assumed to be one initial core load and 29 annual refuel-ings (approximately 1/3 core).
The annual fuel requirement for the model LWR averaged out over a 40-year operating life (1 initial core and 39 refuelings of approximately 1.3 core) would be reduced slightly as compared to the annual fuel requirement averaged for a 30-year operating life.
The net result would be approximately 1.5% reduction in the annual fuel requirement for the model LWR.
This small reduction in fuel requirements would not lead to significant changes in the impacts of the uranium fuel cycle.
The staff judges that there would not be any changes to PVNGS 1-3 FES Table 5.16 (S-3) that would be necessary in order to consider 40 years of operation.
If anything, the value in Table 5. 16 become more conservative when a 40-year period of operation is considered.
CONCLUSIONS The staff has reviewed the PVNGS 1-3 FES and determined that only two of the areas related to its NEPA analysis discussed in the statement were tied directly to a 30-year operating period.
Based on the reasons discussed in the sections
- above, the staff has concluded that the impacts associated with a 40-year license duration are not significantly different from those associated with a 30-year license duration and are not significantly different from those assessed in the PVNGS 1-3 FES.
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