ML16341D402

License DPR-82 for Facility

ML16341D402
Person / Time
Site:	Diablo Canyon
Issue date:	08/26/1985
From:	Harold Denton Office of Nuclear Reactor Regulation
To:
Shared Package
ML16341D403	List: ML16341D402 ML16341D404 ML16342B143
References
NUDOCS 8509060366
Download: ML16341D402 (14)

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 FACILITY OPERATING LICENSE License No.

DPR-82 1.

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

A.

The application for licenses by Pacific Gas and Electric Company (PG8E) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 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 Diablo Canyon Nuclear Power Plant, Unit 2 (the facility), has been substantially completed in conformity with Provisional Construction Permit No.

CPPR-69 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 regulations of the Commission set forth in 10 CFR Chapter I, except as exempted from compliance in Section 2.D below; E.

The Pacific Gas and Electric Company is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.

The Pacific Gas and Electric Company has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements", of the Commission's regulations; 8509060366; 850S2h PDR'; i'ADOCK'5000323 '

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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 Facility Operating License No. DPR-82, subject to the conditions for protection of the environment set forth herein, is in accordance with applicable Commission regulations governing environmental reviews (10 CFR Part 50, Appendix D and 10 CFR Part 51) and all applicable requirements have been satisfied; and I.

The receipt, possession, and use of source, byproduct, and special nuclear material as author ized 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 Commission in its Memorandum and Order (CLI-85-14) dated August I, 1985, the license for fuel loading and low power testing, Facility Operating License No. DPR-81, issued on April 26, 1985, is superseded by Facility Operating License No. DPR-82, hereby issued to Pacific Gas and Electric Company to read as follows:

A.

This License applies to the Diablo Canyon Nuclear Power Plant, Unit 2, a pressurized water nuclear reactor and associated equipment (the facility), owned by PGSE.

The facility is located in San Luis Obispo County, California, and is described in PG&E s Final Safety Analysis Report as supplemented and amended, and the Environmental Report as supplemented and amended.

B.

Subject to the conditions and requirements incorporated

herein, the Commission hereby licenses the Pacific Gas and Electric Company:

( I)

Pursuant to Section 104(b) of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities", to

possess, use, and operate the facility at the designated location in San Luis Obispo County, California, in accordance with the procedures and limitations set forth in this license; (2)

Pursuant to the Act and 10 CFR Part 70, 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 Final Safety Analysis Report, as supplemented and amended; (3)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 radiation monitoring equipment calibration, and as fission detectors in amounts as required;

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(4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 or instrument calibration or associated with radioactive apparatus or components; and (5)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 incor-porated below:

(I)

Maximum Power Level The Pacific Gas and Electric Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (1005 rated power) in accordance with the conditions specified herein.

(2)

Technical S ecifications (SSER 32, Section 8)* and Environmental rotectson an The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of which are attached

hereto, are hereby incorporated in this license.

PGSE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Initial Test Pro ram (SSER 31, Section 4.4. 1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.

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l1 y1i denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

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(4)

Fire Protection (SSER 31, Section 9.6.1 and SSER 32, Section 10) a ~

PG&E shall maintain in effect all provisions of the approved fire protection program as discussed in its Final Safety Analysis Report, in PG&E's December',

1984 Appendix R

Report, and in the NRC staff's Fire Protection Evaluation in Supplements 8, 9, 13, 23, 27 and 31 to the Diablo Canyon Safety Evaluation Report, subject to provisions b.

and c. below.

b.

PG&E shall make no change to features of the approved fire protection program which would decrease the level of fire protection in the plant without prior approval of the Commission.

To make such a change, PG&E must submit an application for license amendment pursuant to 10 CFR 50.90.

c.

PG&E may make changes to features of the approved fire protection program which do not decrease the level of fire protection without prior Commission approval, provided:

( 1) such changes do not otherwise involve a change in a license condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59);

and (2) such changes do not result in failure to carry out the fire protection program approved by the Commission prior to license issuance.

PG&E 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 program 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.

(5)

NUREG-0737 Items Each of the following conditions shall be completed to the satisfaction of the NRC as indicated below.

Each condition references the appropr iate Section in SER Supplements.

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I.D.l Detailed Control Room Desi n Review (SSER 31, ection PG&E shall comply with the requirements of Supplement 1

to NUREG-0737 for the conduct of a Detailed Control Room Design Review (DCRDR) in accordance with a schedule acceptable to the NRC staff.

b.

II.E.4.2 Containment Isolation De endabilit (SSER 31, ection 1

PG&E shall limit the 12-inch vacuum/overpressure relief valve opening to less than or equal to 50 degrees.

(6)

Emer enc Pre aredness SSER 31, Section 4.23.2 and SSER 32, ection In the event that the NRC finds that the lack of 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.

(7)

Masonr Walls (SSER 31, Section 4.7)

Prior to start-up following the first refueling outage, PG&E shall (1) evaluate the differences in margins between the staff criteria as set forth in the Standard Review Plan and the

'criteria used by the licensee, and (2) provide justification acceptable to the staff for those cases where differences exist between the staff's and PG&E's criteria.

(8)

Reactor Tri S stem Reliabilit - Generic Letter 83-28 (SSER 31, ection PG&E shall submit responses to and implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in the PG&E letters dated January 24, and March 13, 1985.

(9)

Steam Generator Tube Ru ture Anal sis (SSER 31, Section 4.25)

Prior to restart following the first refueling outage, PG&E shall submit for NRC review and approval an analysis which demonstrates that the steam generator tube rupture (SGTR) analysis presented in the FSAR is the most severe case with respect to the release of fission products and calculated doses.

Consistent with the analytical ass'umptions, PG&E shall propose all necessary changes to the Technical Specifications, (Appendix A) to this license.

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(10) Pi ewa Structure DE and DDE Anal sis (SSER 32, Section 4)

Prior to start-up following the first refueling outage PGIIE shall complete a confirmatory analysis for the pipeway structure to further demonstrate the adequacy of the pipeway structure for load combinations that include the design earthquake (DE) and double design earthquake (DDE).

Exem tion (SSER 31, Section 6.2.6)

An exemption from certain requirements of Appendix J to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 9.

This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.

Therefore, this exemption previously granted in Facility Operating License No.

DPR-81 pursuant to 10 CFR 50. 12 is hereby reaffirmed.

The facility will operate, with the exemption authorized, in conformity with the application, as

amended, the provisions of the Act, and the regulations of the Commission.

Ph sical Protection SSER 31 and SSER 32)

PGSE 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) and 10 CFR 50.90.

These plans, which contain Safeguards Information as described in 10 CFR 73.21, are entitled:

"Diablo Canyon Power Plant Physical Security Plan," with revisions submitted through August 30, 1984; "Diablo Canyon Power Plant Guard Training and gualifi-cation Plan," with revisions submitted through August 29, 1984; and "Diablo Canyon Power Plant Safeguards Contingency Plan," with revisions submitted through August 29, 1984.

Antitrust PG8E shall comply with the antitrust conditions in Appendix C to this license.

~Re ortin Except as otherwise provided in the Technical Specifications or Environmental Protection

Plan, the licensee shall report any violations 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 followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c),

and (e).

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Financial Protection PGSE shall have and maintain financial protection of such type and in such amounts as the Coranission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I.

Term of License This License is effective as of the date of issuance and shall expire at midnight on December 9, 2010.

FOR THE NUCLEAR REGULATORY COMMISSION Attachments:

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Appendix A-2.

Appendix B-3.

Appendix C-Harold R. Denton, Director Office of Nuclear Reactor Regulation Technical Specifications (NUREG-1151)

Environmental Protection Plan Antitrust Conditions Date of Issuance:

August 26, 1985 1

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