ML20126M208

Forwards Revised Draft Full Power License to Ensure Accuracy.Comments Requested

ML20126M208
Person / Time
Site:	Limerick
Issue date:	06/10/1985
From:	Novak T Office of Nuclear Reactor Regulation
To:	Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
NUDOCS 8506200258
Download: ML20126M208 (15)

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I UUN 101985 LB#2 Reading BGrimes Docket File EHylton Docket No. 50-352 EJordan NRC PDR RMartin Mr.EEdward G. Bauer, Jr.

Local PDR Vice President & General Counsel Philadelphia Electric Company Vogler, OELD 2301 Marke.t Street PRC System Philadelphia, Pennsylvania 19101 ACRS (16)

NSIC JPartlow

SUBJECT:

LIMERICK GENERATING STATION, UNIT 1 DRAFT LICENSE

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Enclosed is a revised draft copy of the full power license for Limerick Unit 1.'

It is provided for your information and coment to ensure that it accurately j

reflects the commitments required of you as described in the F3AR, SER and other documentation.

y We request that you examine the draft license and provide any comments in writing at the earliest practical time.

M Should you have questions regarding this draft license, please contact the Limerick Project Manager Robert E. Martin at (301) 492-4937 Sincerely, oristaal signed bye Thomas M. Novak, Assistant Director for Licensing

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Division of Licensing

Enclosure:

As stated

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g NUCLEAR REGULATORY COMMISSION 53 ij WASHINGTON. D. C. 20555 T....../

JUN 101985 Docket No. 50-352 Mr. Edward G. Bauer, Jr.

Vice President & General Counsel Philadelphia Electric Company 2301 Market Street 7hiladelphia, Pennsylvania 19101

SUBJECT:

LIMERICK GENERATING STATION, UNIT 1 DRAFT LICENSE Enclosed is a revised draft copy of the full power license for Limerick Unit 1.

It is provided for your information and comment to ensure that it accurately reflects the commitments required of you as described in the FSAR, SER and other documentation.

We request that you examine the draft license and provide any comments in writing at the earliest practical time.

Should.you have questions regarding this draft' license, please contact the Limerick Project Manager Robert E. Martin at (301) 492-4937.

Sincerely, N

Thomas M. Novak, Assistant Director for Licensing Division of Licensing

Enclosure:

As stated cc: See next page 9

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I Mr. Edward G. Bauer, Jr.

Limerick Generating Station Philadelphia Electric Company Units 1 & 2 cc: Troy B. Conner, Jr., Esquire Mr. Marvin I. Lewis Conner and Wetterhahn 6504 Bradford Terrace 1747 Pennsylvania Ave, N.W.

Philadelphia, Pennsylvania 19149 Washington, D. C.

20006 Zori G. Ferkin Frank R. Romano, Chairman Assistant Counsel Air & Water Pollution ~ Patrol Governor's Energy Council 61 Forest Avenue 1625 N. Front Street Ambler, Pennsylvania 19002 Harrisburg, Pennsylvania 17105 Federic M. Wentz Charles W. Elliott, Esquire County Solicitor Brose & Poswistilo,1101 Bldg.

County of. Montgomery 325 N. 10th~ Street Courthouse

.19404 Easton, Pennsylvania 18402 Norristown, Pennsylvania Eugene J. Bradley Ms. M. Mulligan Philadelphia Electric Company Limerick Ecology Action Associate General Counsel 762 Queen St.

2301 Market Street Pottstown, Pennsylvania 19464 Philadelphia, Pennsylvania 19101 Mr. Vincent Boyer Mr. Karl Abraham Senior Vice President Public Affairs Officer Nuclear Operations Region I Philadelphia Electric Company U.S. Nuclear Regulatory Commission 2301 Market Street 631 Park Avenue Philadelphia, Pennsylvania 19101 King of Prussia, PA 19806 Mr. Suresh Chaudhary Thomas Gerusky, Director Resident Inspector Bureau of Radiation Protection U.S. Nuclear Regulatory Comission Dept. of Enviromental Resources P. O. Box 47 5th Floor, Fulton Bank Bldg.

Sanatoga, PA 19464 Third and Locust. Streets Harrisburg, Pennsylvania 17120 James Wiggins, SR. R.I.

U. S. Nuclear Regulatory Comission P. O. Box 47 Sanatoga, Pennsylvania 19464~

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o a Sugannan, Denworth & Hellegers Director, Pennsylvania Emergency 16th Floor Center Plaza.

Management Agency 101 North Broad Street Philadelphia, Pennsylvania 19106.

Basement, Transportation &

Safety Building Harrisburg, Pennsylvania 17120 Robert L. Anthony Angus Love, Esq.

Friends of the Earth 107 East Main Street Delaware Valley Norristown, Pennsylvania 19402 103 Vernon Lane, Box 186 Moylan, Penrsylvania 19065 Martha W. Bush Helen F. Hoyt, Chainnan Deputy City Solicitor Administrative Judge Municipal Services Bldg.

Atomic Safety & Licensing Board 15th.and JFK Blvd.

U.S. Nuclear Regulatory Connission Phildelphia, Pennsylvania 19107 Washington, D. C.

20555 David Wersan, Esq.

Dr. Jerry Harbour Assistant Consumer Advocate Administrative Judge

. Office of Consumer Advocate Atomic Safety & Licensing Board 1425 Strawberry Square U.S. Nuclear Regulatory Commission Harrisburg, Pennsylvania 17120 Washington, D. C.

20555 Steven P. Hershey, Esq.

Dr. Richard F. Cole Connunity Legal Services, Inc.

Administrative Judge Law Center North Central - Bevry Bldg. Atomic Safety & Licensing Board 3701 North Board Street U.S. Nuclear Regulatory Connission Philadelphia, Pennsylvania 19140 Washington, D. C.

20555 Mr. J. T. Robb, NS-1 Mr. Spence W. Perry, Esq.

Philadelphia Electric Company Associate General Counsel 2301 Market Street Federal Emergency Management Agency Philadelphia, Pennylsvania 19101 Room 840 500 C St., S.W.

Timothy R. S. Campbell, Director Washington, D. C.

20472 Department of Emergency Services 14 East Biddle Street West Chester,~ Pennsylvania 19380 i-j l

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NUCLEAR REGULATORY COMMISSION a

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PHILADELPHIA ELECTRIC COMPANY

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DOCKET N0 50-352 LIMERICK GENERATING STATION, UNIT 1 FACILITY OPERATING LICENSE License f.o. NFF-39 1.

The Nuclea'..egulatory.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 1 (the facility) has been substantially completed in conformity with Construction Pennit No. CPPR-106 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 Comision (except as exempted from compliance in Section 2.0. below);

D.

There is reasonable assurance: (1) 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 Comission's regulations set forth in 10 CFR Chapt'er I (exc~ept as exempted from c' ppliance in Section 2.0.

o below);

E.

The licensee is technically qualified to engage in the activities

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authorized by this license in accordance with the Comission's regula-tions 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 comon defense and security or to the health and safety 'of the public; e

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After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs cnd censiocring available alternativcs, the issuance of this Facility Cperating License No. NPF-39, 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 thti Commission's regulations and all applicable requirements have been, satisfied; an'd 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 Partial Initial Decisions issued by the Atemic Safety and Licensing Board dated F. arch 8,1983, August 29, 1984, and May 2,1985, and the Licensing Board Orders dated t'ay 9,1965' arid Itay 24, 1985 and the Decision of the Appeal Boaro dated September 26, 1954, rcgarding this facility, and approval by the Nuclear Regulatory Cemission at a treeting on June

, 1985 the license for Fuel Loa' ding and Low Power.

Testing, License No. NPF-27, issued on October 26, 1984, is superseced by Facility Operating License NPF-39 hereby issued to the Philadelphic Elcctric Company (the licensce), to read as follows:

A.

This license applies to the Limerick Generating Station, Unit 1, a boiling water nuclear reactor and associated equipment, owned by Philadelphia Electric Company. The facility is located en the licensee's site in Montgomery and Chester Counties, Pennsylvania on the banks.of

'the Schuylkill River approxirrately 1.7 miles southeast cf the city. limits of Pottstown, Pennsylvania and 21 miles northwest of the city liutts of Philadelphia, Pennsylvania, and is described in the licensee's Final Safety Analysis Report, as supplemented and arrendcd, and in the licensee's Environmental Peport-0perating License Stage, as sq.plemented ano ar,1 ended.

B.

Subject to the conditions and requirements incorporated herein, the Comission hereby licenses Philadelphia Electric Cerpany:

(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to pos-sess, use, and operate the facility at the designated location in hontgomery 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 rcquired for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; l

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. CPOS' Ln d L (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 naterial as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitor-ing equipment calibration, and as fission detectors in amcunts as required;

.(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 ccnp' nents; and o

(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 mey be produced by the cperation of the facility.

C.

This license shall be deemed to contain and is subject to the cor.ci-tions specified in the Comission's rerulations set forth in 10 CFR s

Chapter I (except as exempted frcm 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 Ccmission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is" authorized. to operate the facility ct reactor core power levels not in excess of 3293 megawatts thennal (100% rated power) in accordance with the ccncitions specified herein.

(2) Deferred Items The items identified in Attachnent 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this licens,e.

(3) Technical Specifications and Envirormental Protection Plan The Technical Specifications contained in Appendix A and the En-vironmental Protection Plan contained in Appendix B, both of which are attacht.d hereto, are hereby incorporated into this license.

The licensee shall operate the facility in accordance with the c

l Technical Specifications and the Environmental Protection Plan.

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. 7, m.1 m l$Y $ $ L (4') Fire Protection (Section 9.5, SSER-2) a.

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 thrcugh Revision 34 and as approved in the SER through Supplement 2, and in the Fire Protection Evaluation Report through Revision 6, subject to provisions b and c below.

b.

The licensee shall make no change to features of the approved fire protection program which woulo decrease the level of fire protection in the plant withcut prior approval of the Commission. To make such a change the licensee must subuit an application for license amendment pursuant to 10 CFP,50.90, c.

The licensee may make changes to features of the approved fire protectic~n 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 con-dition 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 reke such records available to NRC inspectors upon rcquest. All changes to the approved program made without prior Commission opproval shall be reported to the Director of the Office of Nuclear Regulation, together with supporting analyses, annually.

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

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The licensee shall provide a stairway for fire bricade dCCess from the turbine building to the Unit 1 cable spreading recm via the Unit 2 cable spreading rcom 6nd the static inverter room prior to startup following the first refueling outage.

(5) Qualification of Personnel (Section 13.1.2.2, SER)

The licensee shall have on each shif t operators that. meet the requirements described in Attachment 2.

(6) Emergency Response Capabilities (Generic Letter 82-33, bupplement 1 to 14UREG-0737)

(a) Detailed Control Room Design Review Task Analysis and Control Room Inventory (Sect! ion 18, SSER-3)

The results from the Limerick plant specific task analysis to identify control roon operator tasks and information/ control requirements for emergency operations, including a complete description of the method, data, and documentation, shall be completed and reported to the staff by'the end of June 1985. This ettort shcIl also include a comparison of the display and control., require-ments with a control room inventory to identify nissing displays and controls.

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(b) Safety Parameter Display System The licensee shall have the Safety Parameter Display System operable within 30 days af ter the ccmpletion of the 100-Hour Warranty Run at 100 percent of rated power.

(7) Post - Ftcl Lc6 ding Initial Test Program (Section 14 SER)

Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFP 50.59 shall be reported in accordance with CO.h (b) within one fronth of such change.

(8)

Inservice Ins)ection Program (Section 5.2.4.3 and 6.6.3, SE 1 and SSER-2 )

The licensee shall submit the inservice inspecticn program by October 2ti,1985 for i4RC staff review and approval.

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M. p@M L d py, (9) Salem ATWS Event, Generic Letter 83-28 (Section 15.8, SSER-2),

The licensee shall implement the requirements of Generic Letter 83-28 on a schedule which is consistent with that given in its November 10, 1983, and liay 8,1984 letters as supplemented by its letter of June

, 1985.

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[ Subject to change]

(10) Turbine System liaintenance Program (Section 3.5.1.3, SER)

The licensee shall submit a turbine system maintenance prog' ram by October 26, 1987.

Prior to review and approval of that program by the llRC staff, the licensee shall volumetrically-inspect all low pressure turbine rotors at the second refueling outage and every other (alternate) refueling outage thereaf ter.

(11) Reactor Enclosure Cooling Water and Chilled Water Isolation Valves (Section 6.2.4.2, SER and SSER-3)

The licensee shall, prior to startup following the first refuel-ing outage, provide automatic and diverse isolation signals to the reactor enclosure cooling water in board and outboard isolation valves in the supply and return lines to the recirculation punps and the drywell chilled water outboard isolation velves in the supply and return lines.

(12)RemoteShutdownSystem(Sections 7.1.4.4, 7.4.2.3, SER and Section 7.4.2.3, SSER-3 and SSER-5)

The licensee shall, prior to startup following the first refueling outage, have completed modificaticos to the existing remote shutdown system to provide a redundant safety-releted rtethod of achieving safe shutdcwn conditions without liftine leads or adding jumpers.

The nodifications to be completed sfall be those described in the licensee's letters dated April 18 and 22, 1565 which allow for the operation of the B RHR purp, the B RHR Sh pump and the B ESU purp from the respective pump breaker ccmpartments by the installation of transfer switches. The licensee shall perform necessary tests prior to startup following the first refueling outage to derenstrate the operability of the modified systen.

(13) Operation with Partial Feedwater Heating at End-of-Cycle (Section 15.0, SER)

The facility shall not be operated with partial teeowater heating for the purpose of extending the nomal fuel cycle.

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os MN l (14) Hydrogen Reconibiner Isolation (Section 6.2.4.2, SER ano SSER-1 erd SSER-3) ihe licensee shall, prior to startup following the first refuel-ing outage, install and test an additional automatic isolaticn valve in each of the hydrogen recorc.biner lines penetrating the primary containment.

(15) Refueling Floor Volume Connection to Standby Gas Treatment System (Section 6.2.3, SSER-2 and SSER-3)

Prior to any movement of irradiated fuel within the refueling floor volume the licensee shall completc and test all modifi-cations required to connect the refueling floor volume to standby gas treatment system. During the interiu period, the licensee.shall not remove the reactor pressure vesst_1 head prior to the !!RC staff review and approval.

'(16) Emergency Planning Procedures Subject to 44 CFR Part 350 In the event the NRC finds that the lack of prcgress in comple-tion of the procedures in the Federal Emergency llanagement Agency's final rule, 44 CFR Part 350, is an indication that a major substantial probleu exists in achieving or maintainirg en adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

D.

The facility requires exemptions from certain recyirements of 10 CFP Part 50. These include (a) exemption frca General Design Criteria (GDC) 61 of Apper. dix A, cperation of that portion of ttc standby gas treatment system ($GTS) that serves the refueling arer until the first refueling (Section 6.2.3 of SSER-2 and SSER-3), (b) exemption from GDC-56 of Appendix A, the requirement for additional autonatic containment isolation valves fcr the hydrogen recombiner linet, and the requirement for automatic isolation of existing isolation velves in the Drywell Chilled Water (DCU) ar.d the keactor Enclosure Cooling Water (RECW) systems until prior to startup following the first refetling cutage (Section 6.2.4.2 of the SER, SSER-1 and SSER-3), (c) exenption from GDC-19 of Appendix A, as related to the requirement for rederdar.t Tcmoteshutdowncapability(Section7.4.2.3ofSSER-3andSSER-5),(d) exemption t

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b from the requirement of paragraph III.D.E.(b)(ii) of Appendix J, the testing of containment air locks at times when the contairrent integrity is not required (Section 6.2.6.1 of the SER and SSER-3),

(e) exemption for the requirements of paragraphs II.H.4. and III.C.E of Appendix J, the leak rate testing of the Hain Steam Isolation Valves (f*SIVs) 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 S.SER-3), (f) exerption from the requirement of paragraphs II.H.1 and III.B.2 of Appendix J, the local leak rate testing of the Traversing Incore Prohe Shear Valves (Section 6.2.6.2 of the SER and SSER-3),(g) a one-time exeuption from the requircraent of Appendix J to perform local leak rate testing on seven Residual Heat Removal Relief Valves (Section 6.2.6.1 of SSER-3) and (h) exemption from requirer.ient of 10 CFR Part 50.44, the inerting of' containment six months after initiel criticality (Section 6 of SSER-5). These exemptions are authorized by law and will not endanger life or property or the cor.Taon defense ar.d security and are otherwise.in the public, interest. Therefore these exemptions are hereby granted pursuant to.10 CFR 50.12. With the granting of these exemptions the facility will operate, to the extent authorized herein, in confomity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission.

The Atomic Safety (ASLBP No.and Licensing Board has, in Orders dated May 9 and llay 24, 1985 81-465-07 OL), granted an exemption, pursuant to 10 CFR 50.47(c)(1), from the requiren.ent of 10 CFR 50.47(a) and (b) for a period of time any potential contentions of the inmates of the State Correctional Institute of Graterford, Pennsylv6nia are considered by the Board. The Board concludcd that the issuance of a full power license to the Applicent during the exemption will not be inimical to the comon defense and security or to the health arc

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safety of the public. Consequently, the Board authcrized the issuance of a full power license.

E.

The licensee shall fully implement and maintain in effect all provisions of the Comission-approved physical security, guard training and qualification, and safeguards contingency plans, inclucing all amend-ments and revisions rade pursuant to the authority of 10 CFR 50.50 and 10 CFR 50.54(p), which are part of the license. Thcsc plans, which contain Saf egaurds Infornation protected under 10 CFF.73.21, are entitled:

" Limerick Generating Station Physical Security Plan," Limerick Generating Station Plant Security Personnel Training and Qualification Plan," and "Lincrick Generating Station Safeguards Contingency Plan."

1 F.

Exce'pt as otherwise p.rovided in the Technical Specificatiu.s or Environt.iental Protection Plan, the licenste shall report any violations of the requirements contained in Section 2.C of this license ir, the following manner:

initial notification shall be made within 24 ' hours to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in 6ccordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

G.

The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.,

H.

This license is effective as of the date of issuance and'shall expire at midnight on October 26, 2024 FOR THE NUCLEAR REGULATORY COPMISSION Harold R. Denton, Director Office of Nuclear Reactor Fr.gulation Attachr.ents/ Appendices:

1.

Attachments 1-2 2.

Appendix A - Technical Specifications (NUREG-

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3.

Apperdix B - Environi.. ental Protection Plan Date of Issuance:

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0,p IT ATTACHNENT 1 ggh h To NPF 39 The attachment identifies itons which must be completed to the satisic.cticn of the staff in accordance with the operational modes or conditions identified below.

1.

OUTSTAf;CINGiTEftTOB'EACCOMPLISHEDPRIORTOINITIALLYINERTINGTHE CONTAINMENT AS REQUIRED BY TEChkICAL SPECIFICAT10hs 3/4.6.6.3 AND 3/4.10.5 a.

Complete' the modifications to the liquid' nitrogen vaporization faciliti and the containment inerting system described in.the licensee's letter dated September 26, 1984 or alternate modificatiens detemined acceptable followin0 an evaluation per 10 CFR 50.59 (IE Bulletin 84-01)

In the event alternate modifications are used, described these modifications and their supporting bases in a report to NRC Region I wi. thin thirty days of their implementation.

1 2.

OUTSTANDING '!TEl45 TO BE CORRECTED BY THE' FIRST REFUELING OUTAGE a.

Seal the conduits to instrunents in the pipe tunnel.

(Inspection Report 50-352/04-27. Item 04) b.

Complete the actions for Construction Deficiency Repcrt (24-00'-10

" Water accumulation in aiesel fuel oil tanks.")

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c.

Incorporate environmental qualification requirements into the I

preventive maintenance program to provide for timely overbt.ul/ replace-r.;cnt of ccrpenents.

(InspectionReport50-352/b5-03, Item 9) i i

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O ATTACHMENT 2 To ilPF-39 This attachment identifies the shift crerating. staff experience requircments.

At all times the plant is in an cperating condition other than cold shutcown or refueling, the licensee shall have a licensed senior operator on each shif t who has had at least six months of. hot operating experience on a same type plant, including at least six weeks at p'ower levels greater than 20% of full pcs.er, and.

who has had startup and shutdown experience. For'those shifts where such an individual is not available on the plant staff, an advisor shall be provided who has had at least four years of power plant experience, inclucir.g two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility. Advisors, as a minimum, shall be trained on plant procedures, technical specifications and plant systems,'. and shall be examined on these topics at a level sufficient to assure familiarity with the plant. These advisors or suitably qualiticd replacements shall be retained until at least one of the senior operators on each shift has the required experience. The NRC shall be notifieo at least 30 days prior to the release of any special assigned advisors.

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