ML20237C213

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License NPF-74 for Facility.Schedule for Completing OL Items for NRC Satisfaction Listed on Encl
ML20237C213
Person / Time
Site: Palo Verde 
Issue date: 11/25/1987
From: Murley T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237C216 List:
References
NUDOCS 8712210136
Download: ML20237C213 (7)


Text

_ _ _ _ - -

l-4 40p9'o UNITED STATES

+8" I,,n NUCLEAR REGULATORY COMMISSION g

'4 E WASHINGTON, D. C. 20555

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ARIZONA PUBLIC SERVICE COMPANY SALT RIVER PROJECT AGRICULTURAL IMPROVEMENT AND POWEP DISTRICT EL PAS 0 ELECTRIC COMPANY SOUTHERN CALIFORNIA EDIS0N COMPANY PUBLIC SERVICE COMPANY OF NEW MEXIC0 LOS ANGELES DEPARTMENT OF WATER AND POWER SOUTHERN CALIFORNIA PUBLIC POWER AUTHORITY DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 FACILITY OPERATING LICENSE License No. NPF-74 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for license filed by Arizona Public Service Company on behalf of itself and the Salt River Project Agric.ultural 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 regulations 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 3 (facility) has been substantially completed in conformity with Construction Permit No. CPPR-143 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 regulations of the Commission (except as exempted from compliance in Section 2.D below);

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);

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E.

Arizona Public Service Company

  • is technically qualified to engage in the activities authorized by this operating license in accordance with the Comission'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 Indemnity 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 after considering available alternatives, the issuance of this Facility Operating License No. NPF-74, 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 require-ments 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.

Pursuant to approval by the Nuclear Regulatory Comission at a meeting held on November 25, 1987, the license for fuel loading and low power testing, License No. NPF-65, issued on March 25, 1987, is superseded by Facility Operating License No. NPF-74 hereby issued to the 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 (licensees) to read as follows:

A.

This license applies to the Palo Verde Nuclear Generating Station, Unit 3, a pressurized water reactor and associated equipment (facility) owned by the licensees. The facility is located on the licensees' site in Paricopa County, Arizona and is described in the licensees' Final Safety Analysis Report, as supplemented and amended; in the related CESSAR Final Safety Analysis Report, as supplemented and amended through Amendment No. 8; and in their Environmental Peport, as supplemented and amended.

  • Arizona Public Service Company is authorized to act as agent for 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, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

I

- I B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) 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' Final Safety Analysis Report, as supplemented and amended, and the CESSAR Final Safety Analysis Report, as supplemented and amended through Amendment No. 8; (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, as sealed sources for reactor instrumentation and i

radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, APS to receive, possess, and use in amounts required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument 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.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth 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:

- (1) 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 (100% power) in accordance with the conditions specified herein and in Attachment 1 to this license. The items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protecticn 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)

Initial Test Program (Section 14, SER and SSER 2)

Any changes in the initial test program described in

~

Section 14 of the FSARs (Palo Verde and CESSAR) made in accordance with the provisiens of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.

l D.

APS has previously been granted an exemption from Paragraph III.D.2(b)(ii) of Appendix J to 10 CFR Part 50. This exemption was previously granted in Facility Operating License NPF-65 1

l pursuant to 10 CFR 50.12.

With the granting of this exemption, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations j

of the Commission.

1 E.

APS shall fully implement and maintain in effect all provisions of J

i l

the physical security, guard training and qualification, and safeguards contingency plans previously approved by the Commission

{

and all amendments and revisions to such plans made pursuant to the j

authority of 10 CFR 50.90 and 10 CFR 50.54(p). By letter dated l

December 26, 1986, APS has incorporated Palo Verde Unit 3 into the l

previously approved plans. The plans, which contain Safeguards l

Information protected under 10 CFR 73.21, are entitled:

"Palo Verde 1

l Nuclear Generating Station Security Plan," with revisions submitted through March 10, 1987, including a Chapter 8 Contingency Plan, and "Palo Verde Nuclear Generating Station Guard Training and Qualification Plan," with revisions submitted through December 7, 1984 F.

APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:

APS may make changes to the approved fire protection program without approval of the Comission only if those changes would q

not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G.

Except as otherwise provided in the Technical Specifications or the Environmental Protection Plan, APS shall report any violations 1

of the requirements contained in Section 2.C of this license in the following manner:

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 /> to the NRC Operations Center via the Emergency Notification System, with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and.(e);

H.

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 March 25, 2027.

FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:

1.

2.

Appendix A -

Technical Specifications 3.

Appendix B -

Environmental Protection Plan 4.

Appendix C -

Antitrust Conditions Dae of Issuance:

November 25, 1987

l November 25, 1987 l

1 ATTACHMENT 1 l'

PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 OPERAlING LICENSE NPF-74 This attachment identifies items that'must be completed to the NRC staff's i

satisfaction in accordance with the schedule identified below, i

1.

Prior to entering Mode 1 for the first tir.e, APS shall:

a.

Have completed a review of the surveillance procedures applicable to the change of mode and determined that the procedures demonstrate the operability of the required systems with the respect to all acceptance criteria defined in the Technical Specifications.

1 i

b.

Have dispatched written notification to the NRC Regional l

Administrator, Region V, that the action defined in (a), above, has been completed for Mode 1.

l l

2.

The post accident sampling system shall be operable prior to exceeding i

5% power.

l 3.

APS shall implement an augmented vibration monitoring program for each of the four reactor coolant pumps that includes the following elements:

a.

Every four hours, monitor and record vibration data on each of the four reactor coolant pumps.

1 b.

On a daily basis, perform an evaluation of the pump vibration i

data obtained in a above, by using an appropriately qualified l

engineering individual.

1 c.

When any one vibration monitor on the reector coolant pumps indicates a vibration level of 8 mils or greater, the Nuclear Regulatory Commission shall be notified within four hours via the Emergency Notification System.

In addition, when the vibration i

on any pump exceeds 8 mils due to a shaft crack or unknown

)

cause, within four hours the affected pump shall have its orbit j

and spectra continuously monitored and evaluated by an l

appropriately qualified individual.

j l

d.

When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 10 mils or greater, within one hour, initiate action to place the unit in at least HOT STANDBY within the next six hours, and at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

In addition the affected pump shall be secured after entering HOT STANDBY.

l l

i 8

2 e.

On a daily basis a spectrum analysis shall be performed on the reactor coolart pump shaft vibration data and shall be evaluated for trends by using an individual qualified in that technique. The evaluation shall consist of comparing the running speed (1xRPM).and twice running speed (2xRPM) spectral components to limits computed from the baseline vibration. The limits shall be based on the lowest of:

(a) 1.6 times the baseline value, (b) the mean plus three standard deviations, 2 mils for the 2xRPM component, or (d) 6milsfor1xRPMcomponent.G)Whentheamplitudeexceedsanylimit, further analysis shall be performed. This aralysis shall consist of an inspection of the amplitude versus time picts for a steadily increasing trend, and a review of other plant data which might explain the change in amplitude.

If it is confirmed that the trend is not caused by plant or pump conditions unrelated to a shaft crack, the trend shall be extrapolated manually and/or by computer to predict the tirre at which the vibration is expected to reach 10 mils.

If the projected time for reaching 10 mils is one week or less, within one hour, initiate action to place the Unit in at least HOT STANDBY within the next six hours and at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

In addition the affected pump thall be secured after entering HOT STANDBY.

The Regional Administrator, Region V may relax or rescind, in yriting, any of the above vibration monitoring conditions upon a showing by the licensees of good cause.

4.

Within 90 days of the commencement of the Palo Verde Unit 2 first refueling outage, the licensee shall submit a report to the NRC concerning the inspection of the Unit 2 reactor coolant pumps. This report shall include inspection results, an evaluation of the Unit I and Unit 2 pump shaft degradation findings and proposed actions to be taken with respect i

I to Unit 3 continued operation.

5.

APS shall install rnodified reactor coolant pump shafts during the first refueling outage which include the modifications described in Figure DES-3 of the attachments to the licensees' November 5, 1987 letter.

S'In the event new limit methods are chosen, they shall be evaluated by the licensee to assure that the new methods are ecual to or better than the above method. The Commission shall be advised within one week if new methods are chosen.

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