ML20154R433

License NPF-45 Authorizing Operation Not to Exceed 5% Full Power

ML20154R433
Person / Time
Site:	Perry
Issue date:	03/18/1986
From:	Harold Denton Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154R435	List: ML20154R433
References
NUDOCS 8603280354
Download: ML20154R433 (11)

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CLEVELAhD ELECTRIC ILLUMINATING CCOPANY DUQUESNE LIGHT COMPANY CHIC EDISON COMPANY PENHSYLVANIA POWER COMPANY TOLEDO EDISON CCFPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-45 1.

The Nuclear Regulatory Connission (the Connission) has found the:

A.

The application for license filed by the Cleveland Electric.

Illuminating Comceny* (CEICO) acting on behalf of itself and as agent for the Dcquesne Light Ccmpany, Ohio Edison Company, Pennsylvania Fower Company and the Toledo Edison Company (licensees) complies with the standards and requirements of the Atomic Energy Act of' 1954, as amended (the Act), and the Connission's regulatiens set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;-

8.

Construction of the Perry Nuclear Power Plant. Unit No.1 (the facility) has been substantially completed in ccnformity with Construction Permit Ho. CPFR-148 and the application, as arxr.dec'.

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 Ccm-

- mission, (except as exempted from compliance in Section 2.0 below);

D.

There-is reasonable assurar.ce:

(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 Connission's regulations set Section 2.0. below)pter I (except as exempted from compliance in forth in 10 CFR Cha i

• Cleveland Electric Illuminating Company is authori:ed to act as agent for Duquesne Light Company, Ohio Edison Company, Pennsylvania Fcwer Ccmpany and the Toledc Edison Company, and has exclusive responsibility and control over the physical construction, operaticn and maintenance of the facility.

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E.-

The Cleveland Electric Illeninating Company is technically quulified to engage in the activities autberi:ed by this license in accordance with the Comissier's regulations set forth in 10 CFR Chapter I; F.

The licensees have satisfied the applicable previsions of 10 CFR Part.140 " Financial Prctection 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; h.

Af ter weighing the environmen'tal, economic, technical and other bene-tits of the facility against envircorrental and other costs and con-sidering available alternatives, the issuance of this Facility Oper-ating License No. NPF-45, subject te 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; ur.c I.

The receipt, possession, and use nf source, byproduct and special nu-clear material as authorized by this license will be in accordance with the Ccm ission's regulations in 10 CFR Parts 30, 40 and 70.

2.

Based on the foregoing findings and the Partial Initial Decisions issced December 2,1983 and September 3,1985, by the Atomic Safety and Licensing Boaro regarding this facility, Facility Operating License No. NPF-45, is hereby issued to the Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Cocpany ari Toleco Edison Company (the licensees) to read as follows:

A.

The license applies to the Perry Nuclear Power Plant, Unit No.1, a boiling water nuclear reactor and associated equipment (the facility),

owned by the Cleveland Electric Illuminating Ccirpany, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Comp 6ny and the Toledo Edison Ccmpany. The facility is located cn the shore of Lake Erie in Lake County, Ohio, approximately 35 miles ncrtheast of Cleve-land, Ohio and is described in the licensees' Final Safety Aralysis Report, as supplemented and amended, anG in the licensees' Envircn-mental Report, as supplemented and amended.

B.

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

(1)

The Cleveland Electric Illuminating Company. (CEIC0) pursuant to Section 103 of the.Act and 10 CFR Part 50, to pcssess,.use and operate the facility at the designated 1ccation in Lake County, Ohio, in accordance with the precederes and linitations set forth in this license;

- (2)

Duquesne Light Company, Ohio Edison Ccmpany, Pennsylvania Pcrer Company and Toledo Edison Ccmpany, te possess the facility at the designated location in Lake County, Ohio, in acccrdar.ce with the proccdures and limitations set forth in this-license; (3)

CEICO, pursuant to the Act ard 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitaticns for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amerded; (4)

CEICO, 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 such as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibratier, and as fission detectors in amounts as required; (5) CEICO, pursuant tc the Act and 10 CFR Parts 30, a0 and 7C, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material withcut restriction to chem-ical or physical form, for sample analysis or instrument cali-bration or assuciated with radioactive apparatus or components; and (6) CEICO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to pcssess, but not separate, such byprcduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to ccntain and is subject to the certiticns specified in the Commission's regulations set torth in 10 CFR Chapter I and is subject to all applicable provisions of the Act 'and to the rules, regulations, and orders of the Comission ncw or hereafter in effect; and is subject to the additional conditions specified or inccrpcraten below:

(1) Meximum Power Level CEICO is authorized to operate the facility at reactor core pcher levels not in excess of 3579 megawatts themal (100% power) in accordance with the conditions specified herein and in Attach-ment I to this license. The items identified in Attachment 1 to this license shall be conipleted as specified. Attachment 1 is hereby incorporated into this license. Pending Commission ap-preval, this license is restricted to power levels not to exceeo 5 percent of full power (178 megawatts thermal);

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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B,- both.of

_ hich are attached hereto, are hereby incorporated into this w

license. CEICO shall operate the facility in a'ccordance with the Technical Specifications.and the Environmental Protection i

Plan.

(3)

Antitrust Conditions Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company and the Toledo Edison Company shall comply with the antitrust conditions delineated in Appendix C to this license; Append 1x' C is hereby incorporated into this license.

.(4) Post-Fuel Loading Initial Test Program (Section 14, SSER #31*

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.

(5) Inservice Inspection Program (Section 6.6.3, SSER #7) j-

-Within six (6) months after exceeding 5% of rated thermal power, CEICO shall sub. nit the Initial Inservice Inspection Program required by 10 CFR 50.55(a) for the NRC staff's review and approval, j

(6)

Fire Protection (Section 9.5, SER, SSER #1, 2, 3, 4, 7 and 8) i CEICO shall comply with the requirements of the fire protection program.as specified in Attachment 2.

Attachment 2 is~ hereby incorporated into this license.

(7)

Detailed Control Room Design Review (Section 18, SSER #7 and 8)

CEICO shall implement the activities remaining to complete the Detailed Control Room Design Review and correct all human engineering discrepancies (HED's) identified in Attachment 3. is hereby incorporated into this license.

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• The parenthetical notation following the title of many ifcense conditions denotes the section of the Safety Evaluation Report-(SER) and/or its supple-ments wherein the license condition is discussed, i'

1

. (8)

Emergency Planning (Section 13.3, SSER #7)

(a) Prior te exceeding 5% of rated therrai power, CEICO shall obtain letters of agreement from all school cistricts for the supply of buses for evacuation purposes.

(b) Prior to exceeding 5% of rateo thermal power, CEICO shall verify that the training of fire protection personnel in radiological monitoring and decontamination precedures are completed and verify that the necessary decontanination equipment has been provided at the fire department facilities for each reception center.

(c) In the event that the NR0 finds that the lack of progress in completion of the procedures in the Federal Emergency lianagement Agency's final rule (44 LFR Pert 350) indicates that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR 50.54(s)(2) will apply.

(9)

TDI Diesel Generator Reliability (Section 9.6.3, SSER #6 & L)

CEICO shall comply with the requirennts identified in Attachment 4 relative to the Transamerica Celcval. Inc., diesel. engines. is hereby incorporated into this license.

(10) Hydrogen Control Preliminary Design (ASLB MSO, Septmber 3.1985)

(a) Pricr to exceeding 5% of rated thermal power, CEICO shall have made further confimatory analysis of equipment in the containment that has not been qualified for pressure survivability, or has rarrow margin of pressure surviv-ability. The equipment includes containment vacuum breakers, hydrcger mixing ccmpressor and discharge check valves.

(b) Prior to exceeding 5% of rated thermal power, CEICO shall ensure that written proceobres are available for operation of the hydrogen igniter system.

D._ CEICO is exempted frcm the Section III.D.2(b)(ii) containment airlock testing requirements of Appendix J to 10 CFR Part 50, due to the special circumstance described in Section 6.2.6 of SER Supplement flu. 7 authorized by 10 CFR 50.12(a)(2)(iii). This exemption is authorized by law, will not present an undue risk to the public health and safety and is consistent with the ccrreon defense and security. The exemption is hereby granted 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 amer.dec, the provisions of the Act, and the rules and regulations of the Commission.

. E.

CEICO shall fully implement and maintain in effect all provisions cf the Comission-approveo physical security, guard training ard cyclifi-cation, and safeguards contingency plans. including all amendments and revisions made pursuant to the authority of 10 CFR 50.90 and IC CFR50.54(p). The plans, which contain Safeguards information pro-tected under 10 CFR 73.21, are entitled: " Perry Nuclear Pcwer Plant Security Plan," with revisions submitted thrcugh November 25, 1985;

" Perry Nuclear Fower Plant Security Force Training anc Qun11tication Plan," with revisions submitted through Septenber 27, 1965; and " Perry Nuclear Power Plant Safeguards Contingency Plan" (Chapter 8 of the Security Plan), with revisions submitted through October 22, 1985.

F.

Except as otherwise provided in the Technical Specifications or Envi-ronmental Protection Plan, CEICO shall report any violations of the requirements contained in Section 2.C of this licer.se in the following manner: initial notification shall be made within 24 hcurs to the NRC Operations Center via the Emergency Notificaticn System with written followup within thirty (30) days in accordance with the procecures described in 10 CFR 50.73(b), (c) and (e).

G.

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, te cover i

public liability claims.

H.

This license is effective as of the date of issuance and shall expire at midnight on March,18, 2026.

FOR THE NUCt. EAR REGut.ATORY COMMISS1014 f

k Harold R. Denton, Director Office of liuclear Reactor Regulation l-Attachments / Appendices:

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1. - 4 2.

Appendix A - Technical Specifications (NUREG-1162) 3.

Appendix B - Environmental Protection Plan 4.

Appendix C - Antitrust Conditiens Date of Issuance: MAR 181986

ATTACHMENT 1 This attachment identifies specific items which must be completed to tne Commission's satisfaction in accordance with.the operational models as identified below.

A.

The preoperational tests and testing exceptions identified in the attachment to the February 27, 1986 letter from Mr. Edelman to James G. Keppler shall be completed in accordance with the scheduled comitments contained in that attachment.

B.

The following open or unresolved items 'must be resolved prior to entering the mode indicated:

l 1.

CEI shall complete installation of all raceway separation barriers l

required to meet IEEE 384-1974 independence requirements (Inspection l

Report 50-440/85-018, Item 01). Complete prior to initia.1 criticality.

2.

CEI shall provide its program for evaluation of the audibility problems encountered on evacuation of personnel from high noise areas.

IE Bulletin 79018 (Inspection Tracking No. 50-440/79018-BB). Complete prior to initial cri ticality.

3.

CEI shall obtain, install, and test IEEE Class IE qualified isolation transformers in the power supply for Division 3 APRM circuits.

Complete prior to exceeding 5% power.

4.

CEI shall complete a verification of System Operation Instructions (501) in accordance with the schedule set forth in a letter from l

Edelman to Keppler dated March 4, 1986.

5.

CEI shall complete all phases of the Instrument Valve Lineup Verifi-cation Special Project Plan 1401 in accordance with the schedule set forth in a letter from Murray R. Edelman to James G. Keppler, dated l

March 14, 1986.

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ATTA^iMENT 2 TO NPF-45 FIRE PROTECTION PROGRAM REQUIREMENTS CEICO shall comply with the following requirements of the fire protection program:

1.

CEICO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Perry (Nuclear Power Plant and asNUREG-approved in the Safety Evaluation Report and Supplement Nos. I thru 9 thereto, subject to the following provisions:-

a.

CEICO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

ATTACHMENT 3 TO NPF-45 DETAILED CONTROL ROOM DESIGN REVIEW CEICO shall comply with the following requirements related to the Detailed Control Room Design Review (DCRDR):

1.

Prior to exceedilig five percent of thermal rated power, t.he licensee shall implement corrections to human engineering discrepancies per comitments in the October 14, 1985 letter from M. R. Edelman (CEICO) to B. J. Youngblood (NRC) and February 19, 1986 letter from Mr. R. Edelman (CEICO) to W. R. Butler (NRC) and shall, per commitment in an October 2,1985 letter from M. R. Edelman to B. J. Youngblood (NRC), provide for.NRC review:

a.

Results of a human factors survey of comunications equipment in the control room and at the remote shutdown facilities 1

b.

Results of the interim sound surveys in the control room and at the remote shutdown facilities

.c.

Results of the augmented process for verifying that selected improvements provide the necessary correction and do not introduce new human engineering discrepancies d.

Commitments and implementation schedules for correction of human engineering discrepancies identified in the above results or justifications for decisions not to correct or to partially correct them.

2.

Prior to startup following the first refueling outage, the licensee shall implement corrections to human engineering discrepancies p-commitments in the January 10, 1985 Detailed Control Room Design l

Review Sumary Report, in the October 2,1985 letter from M. R.

Edelman (CEICO) to B. J. Youngblood (NRC), and in 'the October 14, 1985 Supplement to the Detailed Control Room Design Review Sumary Report and shall provirie for NRC review results of the final sound surveys in the control room and at the remote shutdown facilities.

Additionally, CEICO shall complete the validation of the Perry Nuclear Power l-Plant Emergency' Instructions, and issue a sumary report, prior to achieving initial criticality.

ATTACHMENT 4 TO NPF-45 TRANSAMERICA DELAVEL INC. (TDI) DIESEL ENGINE REQUIREMENTS CEICO shall comply with the following requirements related to the TDI diesel engines:

1.

Changes to the maintenance and surveillance program for the TDI diesel engines, as identified and approved by the NRC staff in the supplemental safety evaluation report in the letter dated November 5, 1985, shall be subject to the provisions of 10 CFR 50.59.

2.

Crankshafts shall be inspected as follows:

The oil holes and fillets of the three main bearing journals subject to the highest torsional stresses (Nos. 4, 6, 8) shall be examined with fluorescent liquid penetrant and, as necessary, eddy current, during each 5 year major disassembly. The same inspections on oil holes and fillets shall be performed on at least three crankpin journals between journals 3 and 8.

3.

Cylinder blocks shall be inspected at intervals calculated using the cumulative damage index (CDI) model and using inspection methodol-ogies described by Failure Analysis Associates, Inc., (FaAA) in the report entitled "Cesign Review of TDI R-4 Series Emergency. Diesel Generator Cylinder Blocks" (FaAA-84-9-11) dated December 1984.

Liquid penetrant inspection of the cylinder liner landing area shall be perfonned anytime liners are removed.

4.

The engines shall be rolled over with the airstart system and the cylinder stopcocks open prior to any planned starts, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after. engine shutdown and then rolled over once again approximately 24 h'ours after each shutdown. In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> periods noted above, that engine need not be i

rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to 4

service. The origin of any water detected in the cylinders must be detennined and any cylinder head which leaks due to a crack shall be replaced. No cylinder heads that contain a through-wall weld repair where the rapair was perfonned from one side only shall be used on the engines.

5.

If inspecticn of either TDI engine reveals cracks in the crankshaft or in-the cylinder block between stud holes of adjacent cylinders, this condition shall be reported promptly to the NRC staff and the l

affected engine (s) shall be considered inoperable. The engines shall not be restored to " operable" status until the proposed disposition

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and/or corrective actions have been approved by the NRC staff.

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2 6.

Operation beyond the first refueling outage shall require staff approval based on the staff's final review of the Owners Group generic findings and of the overall implementation status of Owners Group recommendations at Perry.

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