ML20246G202

Forwards License NPF-85,authorizing Operation of Plant at Reactor Power Levels of 3,293 Mwt

ML20246G202
Person / Time
Site:	Limerick
Issue date:	08/25/1989
From:	Varga S Office of Nuclear Reactor Regulation
To:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20246G199	List: ML20246G202 ML20246G207 ML20247D533 ML20247D545
References
NUDOCS 8908310249
Download: ML20246G202 (5)

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W Docket No. 50-353 August 25, 1989 fp 4

... Mr. George A. Hunger, Jr.

A  : Director-Licensing, NC 5-2A-5 Philadelphia Electric Company w Correspondence Control Desk 955 Chesterbrook Boulevard Wayne, Pennsylvania 19087-5691

SUBJECT:

ISSUANCE OF FACILITY OPERATING LICENSE NPF-85 FOR THE LIMERICK GENERATING STATION, UNIT 2 The U.S. Nuclear Regulatory Comission (NRC) has issued the enclosed Facility Operating License NPF-85, together with Technical Specifications and an Environmental Protection Plan for the Limerick Generating Station, Unit 2.

License No. NPF-85 authorizes operation of the Limerick Generating Station, '

Unit 2, at reactor power levels of 3293 megawatts thermal (100 percent rated power).

Enclosed is a copy of a related notice, the original of which has been .

forwarded to the Office of the Federal Register for publication.

Two signed copies of Amendment No. 6 to Indemnity Agreement No. B-101 which covers the activities authorized under License No. NPF-85 are also enclosed.

Please sign both copies and return one copy to this office.

Supplement No. 9 to the Safety Evaluation Report (SSER 9) was prepared in support of issuing the enclosed license. Enclosed is a preprinted copy of SSER 9. Twenty (20) bound copies will be sent to you in the near future.

Sincerely,

/5/

Steven A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Facility Operating License NPF-85

2. Federal Register Notice

3. Amendment No. 6 to' Indemnity l Agreement No. B-101  !

4 Supplement No. 9 (SSER-0991) to l the Safety Evaluation Report cc w/ enclosures:

See next page i DISTRIBUTIObl: w/ enclosures [

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... ..... August 25, 1989 Docket No. 50-353 Mr. George A. Hunger, Jr.

Director-Licensing, MC 5-2A-5 Philadelphia Electric Company Correspondence Control Desk 955 Chesterbrook Boulevard Wayne, Pennsylvania 19087-5691

SUBJECT:

ISSUANCE OF FACILITY OPERATING LICENSE NPF-85 FOR THE LIMERICK GENERATING STATION, UNIT 2 The U.S. Nuclear Regulatory Comission (NRC) has issued the enclosed Facility Operating License NPF-SS, together with Technical Specifications ard an Environmental Protection Pl.an for the Limerick Generating Station, Unit 2.

License No. NPF-85 authorizes operation of the Limerick Generating Station, Unit 2, at reactor power levels of 3293 megawatts thermal (1C0 percent rated power).

Enclosed is a copy of a related notice, the original of which has been forwarded to the Office of the Federal Register for publication.

Two signed copies of Amendment No. 6 to Indemnity Agreement No. B-101 which covers the activities authorized under License No. NPF-85 are also enclosed.

Please sign both copies and return one copy to this office.

Supplement No. 9 to the Safety Evaluation Report (SSER 9) was prepared in support of issuing the enc'losed license. Enclosed is a preprinted copy of SSER 9. Twenty (20) bound ccpies will be sent to you in the near future.

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t-eb.'Varha, rect Division of Reactor Pr 4 ts I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Facility Operating License NPF-85

2. Federal Fecister Notice

3. Amendment No. 6 to Indemnity Agreement No. B-101

4. Supplement No. 9 (SSER-0991) to the Safety Eveluation Report cc w/ enclosures:

See next page

3 T-Mr. George A. Hunger, Jr.

Philadelphia Electric Company Limerick Generating Station Units 1 & 2 cc:

Troy B. Conner, Jr., Esquire Conner and Wetterhahn Mr. Ted Ullrich 1747 Pennsylvania Ave., N.W. Manager - Unit 2 Startup i Washington, D. C. 20006 Limerick Generating Station P. O. Box A Mr. Rod Krich, 52A-5 'Senatoga, Pennsylvania 19464 i Philadelphia Electric Company i 955 Chesterbrook Blvd. Mr. John Doering Wayne, PA 19087-5691 Superintendent-Operations

' Limerick. Generating Station Mr. Charles W. Elliott P. O. Box A  !

Pe>wistilo, Elliott and Elliott Sanatoga, Pennsylvania 19464 325 N. 10th Street Thomas Gerusky, Director Easton, Pennsylvania 18042 {

Bureau of Radiation Protectio'n j Mr. Graham M. Leitch, Vice President PA Dept. of Environmental Resources

• Limerick Generating Station P. O. Box 2063 Post Office Box A Harrisburg, Pennsylvania 17120 Senatoga, Pennsylvania 19464 Single Point of Contact P. O. Box 11880 Mr. James Linville Harrisburg, Pennsylvania 17108-1880  !

U.S. Nuclear Regulatory Commission Mr. Philip J. Duca Region I 475 Allendale Road Superintendent-Technical King of Prussia, PA 19406 Limerick Generating Station P. O. Box A Mr. Thomas Kenny Sanatoga, Pennsylvania 19464 Senior Resident Inspector US Nuclear Regulatory Commission Mr. Bruce Blanchard, Director P. O. Box 596 Office of Environmental Project Review Pottstown, Pennsylvania 19464 U.S. Department of the Interior 18th and C Streets N.W. j Mr. John S. Keeper Washington, D.C. 20240 i

Senior Vice President-Nuclear l Philadelphia Electric Company Pennsylvania Public Utility Commission 2301 Market Street Conrnonwealth of Pennsylvania Philadelphia, Pennsylvania 19101 P. O. Box 3265 i Harrisburg, Pennsylvania 17120 Environmental Protection Agency Mr. Gregory C. Dunlap Segion III Deputy General Counsel )

841 Chestnut Street Office of General Counsel Ph11acelonia, Pennsylvania 19107 333 Market Street. 17th Floor  !

Harrisburg, PA 17120 l 4

Morton B. Margulies, Chairman Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Conunission Washington, D.C. 20555 l

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eg .s g a Mr. George A. Hunger, Jr. - 2- Limerick Generating Station:

Philadelphia Electric Company Units 1 & 2 cc:

Dr. Jerry Harbour Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission Washington, D.C. 20555 l Frederick J. Shon, Esq.

Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 O

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'*' U 100% LICENSE FOR LIMERICK GENERATING STATION, UNIT 2 ,o NPF-85 DATED: August 25..1989 i'

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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353

'llMERICK GENERATING STATION, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-85

1. The Nuclear Regulatory Comission (the Commission 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 tha

' Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter 1, 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. Thc f acility 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 2,0. below);

D. There it reasonable assurance: (i) that the activities authorized by this operating liter.se can be conducted without endangering the health and safety of the public, and (ii) that such activities will be corducted 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. The licensee is technically qualified to engage in the activities authorized by this license in accordance with the Comission's l regulations set forth in 10 CFR Chapter I; l .

F. The licensee has satisfded the applicable provisions of 10 CFR Part l 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 uf the public;

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2 f 4' H. After weighing the environmental, economic, technical, and other knefits 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 Environinental:

Protection Plan attached as Appendix B,. is in accordan't trith 10 CFR Part 51 of the Comission's re.gulations and all applicable-requirements have been satisfied; and j I.

The receipt, possession, and use of source, byprJduct and special 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 licensee), 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 en 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 Analy, sis Report, as supplemented and amended, and in the licensee's Environmental Report-Operating License Stage, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein, the Commission 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 Montgemery and Chester Counties, Pennsylvania, 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 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;

L \ s 3-(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 tp the Act and 10 CFR Parts 30, 40 end 70, to possess, but not separate, such byproduct and special neclear materials nas 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 (except as exempted from compliance in Section 2.D.

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

(2) Technical Specifications The Technical Specifications contained in Appendix A and the 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.

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• 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 Commission 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 unroviewed safety question (see 10 CFR 50.59). However, the licersee 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 co ,

j program made without prior Commission approval' proved shall be reported to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses, annually.

(4) Physical Security ar.d Safeguards The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans previousiy approved by the Commission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(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 Personnel 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 Part 50 and 1.0 CFR Part 70. These include (a) exemption from the  !

requirement of paragraph III.D.2.(b)(fi) of Appendix J, the testing of containment air locks at times when the containment l

integrity is not required (Section 6.2.6.1 of the SER and SSER-3) j (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 Yalves (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 summation 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, 4

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5-the' local Vaives (Section leak' rate of-the 6.2.6.1 testingSER ofand theSSER-3 Traversing)'Incore Probe Shesr

, (d) an exemption c from the schedule. requirements of 10 CFR 50.33(k)(1) related to availability of funds.for decommissioning the facility (Section 22.), SSER 8) and (e) exemption from the requirement of 10 CFR Part 50.44, the inerting of containment.six months after initial l criticality (3ection 6.2.5 of SSER 9 The:special circumstances reg:rdingexemptions(a),(b)and(c)). are identified in Sections y.

6.2.6.1 of the SER and SSER 3. An exemption froin the' criticality monitoring requirements of 10 CFR 70.24 was prevlously granted with NRC materials' license ho. SNM-1977 issued November 22, 1988. The licensee is hereby exempted from the requirements of 10 CFR 70.24 - <

insofar as this requirement applies to the handling and storage of  !

fuel assemblies held under this license. '

These exemptions are authorized by law, will not present an undue <

risk to the public health and' safety, and are consistent with the comon 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 Comission. I 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 days in

.accordance with the procedures described in 10 CFR.50.73(b), (c),

and (e).

F. The licensee shall have and maintain financial protection of such type and in such amounts as the Comission 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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FOR THE NUCLEAR REGULATORY COMMISSION-

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l> Thomas E. Muriey, Director Office of Nuclear Reactor Regulation

Enclosures:

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

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

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

1 FOR THE NUCLEAR REGULATORY COMMISSION l l l

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Thomas E. Murley, Director Office of Nuclear Reactor Regulation {

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Enclosures:

1. Appendix A - Technical Specifications (N'.' REG-1376)

2. Appendix B - Environmental Protection Plan Date of Issuance:

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

FOR THE NUCLEAR REGULATORY COMMISSION L.

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. 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 '

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. . NUREO-1376 ,

4 Technical Specifications  !

Limerick Generating Station, C nit No. 2 Docket No. 50-353 I i

Appendix "A" to '

License No. NPF-85 .

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Issued by the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation August 19S9 hlh' h

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