ML20248E554

Forwards License NPF-85 Issued to Philadephia Electric Co for Limerick Unit 2,per 890923 Request

ML20248E554
Person / Time
Site:	Limerick
Issue date:	09/28/1989
From:	Clark R Office of Nuclear Reactor Regulation
To:	Anthony R ANTHONY, R.L.
References
NUDOCS 8910050282
Download: ML20248E554 (2)

Text

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4 September 28, 1989 4

Docket No. 50-353 n.

I-Mr. Robert L. Anthony -

Box 186 Moylt.n, Pennsylvania -19065

Dear Mr. Anthony:

As requested by your postcard of September 23, 1989, enclosed is a copy of Operating License NPF-'85 issued to the Philadelphia Electric Company for f Limerick Unit 2.

Sincerely, Odgintal signed by Richard J. Clark Richard .1. Clark, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

License NPF-85 DISTRIBUTION:

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. September ~28, 1989

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-Docket No.'50-353 t

. Mr. Robert L. Anthony Box 186' g 'Noylan, Pennsylvania. 19065

Dear Mr. Anthony:

As requested by your postcard of September 23, 1989, enclosed is a copy

'of Operating License NPF-85 issued to the Philadelphia Electric Company for Limerick linit 2.

Sincerely,

. . . , l R . C1 rk, Project Manager Pi:oject Dir torate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

License NPF-85 -

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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-85

1. The Nuclear Reguietory Comission (the Comission or the NRC) has .found that:

A. The application for license filed by Philadelphia Electric Company (the licensee) complies with the standards and requirements of.the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifica-tions to other agencies or bodies have been duly made; B. Construction of the Limerick Generating Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-107 and the application, as amended, the provisions of the Act and the regulations of the Comission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.0. 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 corducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below);

E. The licensee is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements."

of the Comission'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; Gr f

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-2 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-85, 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 Comission's regulations-and all applicable requirements have been satisfied; and.-

I.

The receipt, possession, and use of source, byproduct and special L nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40.and 70.

2. Based on the foregoing findings and the Decision of the Atomic Safety and Licensing ~ Board, LBP-85-25, dated July 22, 1985, the Comission's Order dated July 7,1989, and the Comission's Memorandum and Order dated August 25, 1989, regarding this facility, Facility Operating License NPF-85.is hereby issued to the Philadelphia Electric Company (the ifcensee), to read as follows:

A. This license applies to the Limerick Generating Station, Unit 2, a boiling water nuclear reactor and associated equipment, owned by Philadelphia Electric Company. The facility is located on the licensee's site in Montgomery and Chester Counties, Pennsylvania on the banks of the Schuylkill River approximately 1.7 miles southeast of the city limits of Pottstown, Pennsylvania and 21 miles northwest of the city limits of Philadelphia, Pennsylvania, and is described in the licensee's Final Safety Analysis Report, as supplemented and amended, and in the licensee's Environmental Report-0perating License Stage, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein, the Comission hereby licenses Philadelphia Electric Company:

(1). Pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Montgomery and Chester Counties, Pennsylvania, i,n 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 to 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; Y . _ _ _ _ _ _ . - -. - - -- . _ _ _ _ _ _ . _ _ _ _ _ _ _ ___ _

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b (4)"' Purhuant to the Act and_10 CFR Parts 30, 40' and 70, to receive, 0  ; possess. and use'in amounts as- required any byproduct;-source. ,'

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or special nuclear material without restriction to chemical or P

- physical: form, for sample analysis or instrument' calibration or-E / 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.

' Thislicenseshallbedeemedtocontaina'ndiis-subjecttothe

- conditions specified in the Commissions regulations set forth in 10 L CFR Cha o below) and pterisI-(except subject to'all_. as exempted applicable fromprovisions compliance in Section of the Act and 2.D.

to F, 'the rules, regulations, and orders of the Commission now or-F hereafter in effect; and is subject to the additional conditions

specified'or incorporated below:

S (1)'MaximumPower' Level E

Philadelphia Electric Company is. authorized to operate the facility at reactor core power levels of 3293 megawatts thermal i (100 percent rated power).in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in_ Appendix A and the

, 1 Environmental ~ Protection Plan contained in Appendix B, are hereby incorporated into this license. PECo shall operate the facility in accordance with the Technical Specifications and.the Environmental Protection Plan.

(3) Fire Protection (Section 9.5. SSER 2)*

The licensee shall maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Revision 58 and~ '

as approved in the SER through Supplement 9, and in the Fire Protection Evaluation Report through Revision 12, subject to the following provisions a and b below:

a. The licensee 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 the licensee must submit an application for license amendment pursuant to 10 CFR 50.90.

• The parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

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b. The licensee may make changes to features of the approved fire protection program which do not decrease the level of fire protection without prior Comission approval after such features have been installed as approved, provided 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). However, the licensee shall maintain, in an auditable form, a current record of all such changes including an evaluation 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 Comission approval shall be reported to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses, annually.

(4) Physical Security and Safeguards The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans previously approved by the Comission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Limerick Generating Station, Units 1 & 2, Physical Security Plan," with revisions submitted through October 31,1988; " Limerick Generating Station, Units 1 & 2, Plant Security P,ersonnel Training and Qualification Plan," with revisions submitted through October 1,1985; and

" Limerick Generating Station, Units 1 & 2, Safeguards Contingency Plan," with revisions submitted through November 15, 1986.

D. The facility requires exemptions from certain requirements of 10 CFR j

Part 50 and 10 CFR Part 70. These include (a) exemption from the requirement of paragraph III.D.2.(b)(11) of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3)

(b) exemption from the requirements of paragraphs II.H.4 and III.C.2 of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemption.from the requirements of paragraph III.C.3 of Appendix J that the measured MSIV leak rates be included in the sumation for the local leak rate test (Section 6.2.6.1 of SSER-3), (c) exemption from the requirement of paragraphs II.H.1 and III.C.2 of Appendix J, l

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U' the localfleak rate testing of the Traversing intore Probe Shear Yalves-(Section 6.2.6.1 of the SER~and SSER-3) (d)anexemption from the. schedule requirements of 10 CFR 50.33lk)(1) related to' availability of funds for decommissioning the facility (Section 22.1, SSER 8) and (e) exemption from the requirement of 10 CFR Part.

50.44, the inerting of containment six mo'ths after initial F n criticality (Section 6.2.5 of SSER 9). The special circumstances regarding exemptiors (a), (b) and (c) are identified in Section.s 6.2.6.1 of the SER and SSER 3.- An exemption from the. criticality -

monitoring requirements of 10 CFR 70.24 was previously granted with NRC materials license No.-SNM-1977. issued November 22, 1988. The

' licensee is hereby exempted from the requirements of 10 CFR 70.24 -

insofar as this reoufrement applies to the handling and storage of fuel assemblies held under this ifcense.

L These exemptions are authorized by law, wili hot present an undue risk to the pubite health and safety and au consistent with the comunon defense and security. The exemptions in items a, b, c, d and e above are granted pursuant to 10'CFR 50.12. With these exemptions, 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 of the Commission.

E. 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 day)s i

-and(e).

F. The licensee 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.

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This license.is effective as of the date of issuance and shall expire at midnight on June 22, 2029.

FOR THE NUCLEAR REGULATORY COMMISSION SP -

s Thomas E. Murley, Director Office of Nuclear Reactor Regulation-__

Enclosures:

1. Appendix A - Technical Specifications (NUREG-1376)

2. Appendix B - Environmental Protection Plan Date of Issuance: August 25, 1989 GG

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