ML20066B471

Amend 36 to License NPF-58,authorizing Both Cleveland Electric Illuminating Co & Centerior Svc Co to Act as Agents for Other Licensees

ML20066B471
Person / Time
Site:	Perry
Issue date:	12/31/1990
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20066B473	List: ML20066B471 ML20066B475
References
NUDOCS 9101080017
Download: ML20066B471 (18)

Text

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UNITE D STATES

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NUCLEAR REGULATORY COMMISSION r.<

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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.

DOCKET NO. 50 440 PERRY NUCl. EAR POWER PLANT, UNIT NO 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. NPF-58 1.

The Nuc' var Regulatory Commission (the Commission) has founo that:

A.

The application for amendment by The Cleveland Electric illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated July 17, 1990, as supplemented by letter dated November 30, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the congnon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Conunission's regulations and all applicable requirements have been satisfied.

2.

Accordingly Facility Operating License No. NPF-58 is amended as fo l',0ws :

1.

Add Centerior Service Company to the title of the NPF-58 license to read:

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2 CLEVELAND ELECTRIC ILLUMINATING COMPANY CENTER 10R SERVICE COMPANY DUQUESNE LIGHT COMPANY l

OHIO EDISON COMPANY l

PENNSYLVANIA POWER COMPANY-l TOLEDO EDISON COMPANY DOCKET NO. 50-440 PE_RRY NUCLEAR POWER PLANT, UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-58 11.

Add Centerior Service Company and revise the footnote to paragraph 1.A as follows:

1.

TheNuclearRegulatoryCommission(theCommission) has found that:

A.

The application for license filed by the Cleveland Electric 111uminating Company * (CEICO) and Centerior Service Company acting on their own behalf and as agents for the Duquesne Light Company, Ohio Edison Company, Pennsy(lvania Power Company and the Toledo l

Edison Company licensees) 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; The footnote shculd read:

i

• cieveland tlectric Illuminating Company and Centerior Service Company (both of which are wholly-owned subsidiaries of Centerior Energy Corporation) are authorized to act as agents for Duquesne l

Light Company, Ohio Edison Company, Pennsylvenia Power Company and the Toledo Eoison Company, and have exclusive responsibility and control over the physical construction, operation arid i

maintenance of the facility.

Centerior Service Company was added as a licensee by Amendment No.

36

U !!!. Add Centerior Service Company to paragraph 2 as follows:

2.

Based on the foregoing findings regarding this facility, the Partial-Initial Decisions issued December 2,1983 and September 3, 1985 by the Atomic Safety and Licensing Board in re facility (affirmed by ALAB-841 dated July 25, 1986) gard to this and pursuant to approval by the Nuclear Regulatory Comission at a meeting on -

hovember 7,1986 Facility Operating License No. NPF-58, which supersedes the license for fuel loading and low power testing, License No. NPF-45, issued on March 18, 1986, is hereby issued to the Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company and Toledo Edison Company (the licensees) to read as follows:

11 Add a footnote to paragraph 2.B.(1) as follows:

B.

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

(1) TheClevelandElectricIlluminatingCompany(CEICO)*

pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Lake County, Ohio, in accordance with the procedures and limitations set forth in-this license;

• The CEICO nuclear organization reports to Centerior Service Company.

V.

2.C.(3) paragraph 2.C.(3) by identifying the existing paragraph as Revise

.a. and adding new paragraph 2.C.(3).b. as follows:

(3) Antitrust Conditions a.

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; Appendix C is hereby-incorporated into this license.

b.

Centerior Service Company (CSC) shall comply with the antitrust conditions delineated in Appendix C to this. license as if named therein.

CEICO is responsible and accountable for the actions of CSC to the extent that CSC's actions contravene the antitrust-license conditions in Appendix C to this license.

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{ 1 VI. Revise paragraph 2.C.(2) to read as follows:

(2) Technical Specifications

-The Technical specifications contained in Appendix A and the Environnental Protection Plan contained in Appendix B, as revised through Amendment No. 36 are hereby incorporated into this license. The Cleveland Electric Illuminating Cogany shall operate the facility in accordance with the Technical Specifications and the Environmental. Protection Plan.

3.

This license amendment is effective as of its date of issuance.

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John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects _III/IV/V i

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical l

Specifications and License I

Date of issuance:

December 31, 1990 1

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ATTACHMENT TO LICENSE AMENDMENT NO. 36 1

4 FACILITY OPERATING LICENSE NO. NPF-58 i

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DOCKET NO. 50-440 i

i Replace the following sages of the Appendix "A". Technical Specifications with the attached pages.

T1e revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are i

provided to maintain document completeness.

Remove Insert 6-1

6-1 6-9 6 "

6-10 6-10 6-11 6-11 6-13 6-13 6-15 6-15 Retyped license pages 1, 2 and 4 are also provided for convenience.

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY i

1 6.1.1 The General Manager. Perry Plant Operations Department, shall be responsible for overail unit operation and shall delegate in writing the

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succession to this responsibility during his absence.

6.1.2 The Shift Supervisor or. during his absence from the control room, a designated individual-shall be responsible for the control room contnand function. A management directive to this effect. signed by-the.Vice.

President - Nuclear shall be reissued to all station personnel on an-

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annual basis.

e 6.2 ORGANIZATION

=I 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS i

Onsite and offsite organizations shall be established for' unit operation and corporate management, respectively. The onsite and offsite organiza-tions shall include the positions for activities affecting the safety of the nuclear power plant.-

a.

Lines of authority, responsibility. and communication shall be j',

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established and defined from the highest management levels 1

through intermediate levels to and including'all operating 4

organization positions. These relationships shall be documented and' updated, as appropriate. in-the form of organization charts, functional descriptions of departmental responsibilities and.'

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relationships. and job descriptions for key personne11 positions.

or in equivalent forms of documentation.

These requirements l

shall be documented in the'USAR and updated in accordance with 1

10 CFR 50.71(e).

b.

The General Manager. Perry Plant Operations Department-(PP00),

shall be responsible for overalll unit safe operation and shall have control over those onsite activities necessary for safe-operation and maintenance of the plant, c.

The Vice President - Nuclear shall-.have corporate l

responsibility for overall plant nuclear' safety and shall-take any measures needed to ensure: acceptable perfonnance of the staff in operating.-maintaining, and:providing. technical support to the plant to ensure nuclear safety, d.

The individuals who train the operating staff =and those who carry out health physics and quality: assurance functions-may report;to the appropriate onsite manager; however, they shall1 have sufficient organizational. freedom to ensure their independ-ence,from operating pressures.

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p PERRY'- UNIT 1-6-1 Amendment No..

Y7. 36

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l ADMINISTRATIVE CONTROLS u

6.2.2 UNIT STAFF a.

Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in OPERA-TIONAL CONDITION 1, 2 or 3, at least one licensed Senior Operator-shall be in the control room; c.

A Health Physics Technician

• shall be on site when fuel is in the reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by eithe a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibil-ities during this operation; and e.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physics technicians, auxiliary operators, and key mainte-nancepersonnel).

The amount of overtime worked by unit staff members perfonning safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

• The Health Physics Technician may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided imediate action is taken to fill the required positions.

PERRY - UNIT 1 6-2 Amendment Nn. 13

(.Nextpageis-6-6) k

1i ADMINISTRATIVE CONTROLS

, QUORUM

6. 5.1. 5 The quorum of the PORC necessary for-the perfonnance of the PORC responsibility and authority provisions of-these Technical Specifications shall consist of the Chairman or his designated alternate and at least four members including' alternates.

1 RESPONSIBILITIES l

6.5.1.6 The PORC shall be responsible for:

a.

Review of all Administrative Procedures; b.

Review of the sdfety evaluations for (.1) proposed procedures /

instructions (2) changes to procedures / instructions, equipment, systems or facilities, and (3) tests or experiments._ performed under the provisions of 10 CFR 50.59 to: verify.-that such actions do not-constitute an unreviewed cafety question; c.

Review'of proposed procedures / instructions and changes to. procedures /

instructions, equipment, systems or facilities which involve an unreviewed safety question as defined.in!10 CFR 50.59; d.

Review of proposed tests or experiments'which invo1ve an unreviewe'd

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safety question as defined in 10 CFR 50.59;~

e.

Review of proposed changes to Technical Specifications or-the Operating License; f.

Investigation of all violations of the Technical Specifications including the preparation and forwarding-of, reports covering evalua-l tion and recomrdendations to prevent recurrence to theLVice President:-

1 Nuclear and to the Nuclear Safety Review Committee;

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g.

Review of all REPORTABLE EVENTS; h.

Review of-the plunt Security Plan and' Security Contingency Instruc -

tions; l

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Review of the Emergency Plan and implementing instructions; i

j.

Review of changes to the PROCESS:CONTR01. PROGRAM, the OFFSITE DOSE CALCULATION MAN'JAL, and-Radwaste Treatment Systems; J!

k.

Review of any accidental, unplanned or uncontrolled radinactive release including the preparation of reports _ covering evaluation.-

recommendations, and disposition of,the corrective action to prevent recurrence and the forwarding:of these reports to-the General

Manager, Perry ; Plant' Operations Department.(PP00)-and,the Director,-

Perry Plant Techr:ical Department.-(PP_TD),: the Nuclear Safety-Review -

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Committee ana 'the Vice Presidentu-; Nuclear ;

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Review of Unit operations Lto detect potedtial hazards to nuclear-

-safety; Investigations or analysis of special subjects ar requested by the m.-

l Chairman of-the Nuclear Safety Review Comittee; and -

% view of:the Fire Protection Program and implementing procedures.

n.

t PERRY - UNIT 1 6-9 Amendment No.D P8/, 36 -

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

6. 5.1. 7 The PORC shall:

a.

Recorrinend in writing to the General Manager. PP0D/ Director, PPTD, approval or disapproval of items considered under Specifications 6.5.1.6a. through e.,

h.,

i., J., and k., above prior to their implementation; b.

Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6b. through e.,

above, constitutes an unreviewed safety question; and c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -

Nuclear and the Nuclear Safety Review Committee of disagreement

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between the PORC and the General Manager, Perry Plant Operations Department; however, the General Manager, Perry Plant Operations Department, shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility provisions of these Technical Specifications.

Copies shall be provided to the Vice President - Nuclear and the Nuclear Safety Review l

Committee.

6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)

FUNCTION 6.5.2.1 The NSRC shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy, e.

Instrumentation and control, f.

Radiol.ogical safety, g.

Mechanical and electrical engineering, b.

Quality assurance practices and administrative controls, and i.

Nondestructive testing.

The NSRC shall report to and advise the Vice President - Nuclear on those l

areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.

PERRY - UNIT 1 6-10 Amendment No. 22, 36 i

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ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 -The membership of the NSRC shall be composed of at least eight person-nel appointed byL the Vice President - Nuclear to provide collective experience l

and competency in the following areas; Nuclear power plant operations Nuclear engineering Chemistry and radiochemistry Metallurgy Nondestructive testing Instrumentation and control r

Radiological. safety Mechanical and electrical engineering i

Administrative controls and quality assurance practices The_ Chairman, appointed by the.Vice President - Nuclear shall have"10 years-

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of power plant experience, of which.3' years shall be-nuclear power plant experience. The.NSRC members shall' hold a bachelors' degree in an engineering '

or physical science field, or equivalent experience,.and a minimum ~of 5' years:

of technical experience of which a minimumiof 3 years shall be in one or more-of the disciplines in-Specification 6.5.2.1.- Competent alternates may be designated in advance and consultants may be used'for=in-depth _ expertise if desired by the committee.

ALTERNATES

_l 6.5.2.3 All alternate members shall be appoi_nted in writing:by the NSRC Chairman to serve on a temporary basist.however, no more than twotalternates shall participate as voting members in:NSRC activities at ~any one time.-

CONSULTANTS

- 6.5.2.4 Consultants shall be, utilized as determined by the:NSRC Chairman to a

provide. expert advice to the NSRC.

MEETING FREQUENCY 6.5.2.5 The:NSRC shall meet at least once per' calendartquarter during the=

initial year:of' unit-operation following fueluioading :and at pleast once -per 6 6,1onths thereafter.

QUORUM' 6.5.2.6.The quorum 1of the' NSRC necessary for_ the performance-of the-NSRC _

review and ~ audit functions of these Technical. Specifications ^ shalliconsist of the Chainnan'or his' designated alternate and at least four but.not less than-one-half of the NSRC members-including alternates. No"mo're than' a-minority-of-the quorum shall have line responsibility for operation-of the unit.

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PERRY - UNIT 1

.6-11.

. Amendment' No '36 q

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ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The NSRC shall be responsible for the review of:

a.

The safety evaluations for (1) changes *o procedures, instructions, equipment, or systems; and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; b.

Changes or proposed changes to procedures, instructions, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50,59; c.

Tests or experiments or proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.

Proposed changes to Technical Specifications or this Operating License; Violations of codes, regulations, orders, Technical Specifications, e.

license requirements, or of internal procedures or instructions having nuclear safety significance; f.

Significant operating abnormalities or deviations from nomal and expected performance of unit equipment that affect nuclear safety; g.

All REPOR1ABLE EVENTS; h.-

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and 1.

Reports and meeting minutes of the PORC.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRC.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least-once per 12 months; b.

The performance, training and qualifications of $a entire unit staff at least once per 12 months; c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; PERRY - UNIT 1 6-12 l

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1 a

ADMINISTRATIVE CONTROLS AUDITS (Continued) d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR Part 50, at least once per 24 months; The fire protection programmatic controls including the implementing e.

procedures at least once per 24 months by qualified licensee QA personnel; f.-

The fire protection equipment and program implementation at-least once per 12 months utilizing _either a qualified corporate licensee fire protection engineer (s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least every third year; g.

The ' radiological environmental monitoring program and the results thereof at least once per 12 months; h.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; i.

The PROCESS CONTROL PROGRAN and implementing procedures at least once per 24 months; j.

The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months; and k.

Any other area of unit operation considered appropriate by the NSRC or the Vice President - Nuclear.

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RECORDS, 6.5.2.9 Records of NSRC activities shall be prepared, approved, and distributed as indicated below:-

l Minutes of each NSRC meeting shall. be prepared, approved, and a.

forwarded to the Vice President - Nuclear within 14 days ~

l following each meeting, b.

Reports of reviews encompassed by Specification 6.5.2.7'shall be prepared, approved, and forwarded to the Vice President - Nuclear-within 14' days following cocoletion of the review.

l c.

Audit reports encompassed by Specification 6.5.2.8 thall be forwarded to the Vice President - Nuclear and to the manag'ement positions i

. responsible for the areas audited within 30 days after completion'of the audit by the auditing organization.

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l PERRY - UNIT 1 6-13 Amendment No'. 36

N$1, 9 i ADMINISTRATIVE CONTROLS-6.5.3 TECHNICAL REVIEW AND CONTROL-ACTIVITIES.

-6.5.3.1 Activities which affect' nuclear: safety shall be conducted as follows:

a, ' Procedures / instructions. required by Specification.6.8 and-~other -

procedures / instructions which affect plant nuclear safety, and-changes thereto, shall be prepared.1 reviewed and approved.

Each _

such procedure / instruction or procedure / instruction change shall..

be _ reviewed by a qualified. individual (s) -other: than the individual (s) which prepared the procedure / instruction.or procedure / instruction change, but who may be from.the same _section< as' the; individual (s) 3 which prepared the procedure / instruction or procedure / instruction i

change.

Instructions shall _be approved -by appropriate management personnel as designated in writing by PORC. Land approvedtby the-e appropriate managers, PerrycPlant : Departments. ~Both the' General

' Manager, PP00, and the Director,.PPTD, shall approve-Administrative Procedures.

b..

Proposed modifications to plant structures,- systems and components that affect nuclear safety shall_ be reviewed by/ individuals desig-nated by the Director, Nuclear Engineering' Department.

Each-such

_l modification shall be reviewed by-a qualified 11ndividual(s)1other-than the individual (s) whichjdesigned the modification. -but'who

-may be from;the same section~asithe'in'dividual(s) which designed:

the modifications.

Prop'osed modificationsito-plant structures, systems' andLcomponents that affect nuclear safety shallLbe reviewed by PORC and approved prior to implementation; by both _ the General Manager.-PP0D/ Director,PPTD.

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Proposed tests and experiments which affect plant. nuclear safety L

c.

j shall be'preparedi reviewed,-and approved.

Each such test-or=

1 experiment shall--be reviewed bysa qualified individual (s) other.,

j than'the individual (s)Lwhich prepared the proposedttest.or experi-1 z

ment. - Proposed tests and ' experiments 9shal11be approved before 1

implementation by:both:the GeneralLManager,lPP0D/ Director PPTD.

l d.

$ actions _ responsible for reviews, including cross-disciplinary re ti ews, perf ormed 71 n? acco rda nce fwi th1.S pec i fi ca ti on s D 6. 5. 3. l a. J a nd.

6.5.3.lc., shall be designated in: writing by PORC;and approved byJ the General,Mana er, PP00, or the Director, PPTD, as+ appropriate.

l The individual (s 'erforming the review'shall meet or exceed the p

qualification requirements of, appropriate.section(s) of! ANSI; N18.'l-l 19711

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- Each review shall include a determination pursuant toL10.CFR 50.59 of.

e.

whether or not the-potential for-an unreviewed2 safety questiontexistsL If'such a potential does exist, assafety evaluation ;per 10 CFR;50.59l.

'to' determine whether or not an unreviewed-safety!questionnisLinvolved" shall be performed.' PursuantJto 10 CFR 50.59,'NRC approval of:1tems; involving unreviewed safety questionsLshal_1 be obtained prior to:

implementation;;and-

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PERRY - UNIT 1.

6-14

. Amendment No. 221 w

span f i.

4 ADMINISTRATIVE CONTROLS ACTIVITIES (Continued).

f.

The Plant Security Plan and Emergency Plan, and; implementing instruc-tions, shall be~ reviewed at least once per 12 months.

Recommended changes to the-implementing instructions shall be approved by the Director, Nuclear Support Department, or Director, Perry Plant Technical Department,- as appropriate.

Recommended changes to the:

Plans-shall be-. reviewed pursuant to the requirements of Specifica-tion 6.5..l.6 and approved by' the General Manager, Perry. Plant i

Operations Department, and either the Director, Nuclear Support Department,. or the Director, Perry Plant Technical Department, as-1 appropriate.

NRC -approval shall be obtained as-appropriate.

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6. 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for: REPORTABLE EVENTS:

a.

The Commission shall be notified and. a report. submitted' pursuant -

to the requirements of Section 50.73 to 10 CFR Part 50,: and b.

Each REPORTABLE EVENT shall be reviewed by the PORC and the results -

of the review submitted to the-NSRC and the-Vice-President.- Nuclear.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be:taken in'the event a Safety Limit is violated:

The NRC' Operations Cente'r shallLbe notif_ied byt telephone as soon as a.

possible and in all' cases within 1-hour,.

.The Vice President -

1 Nuclear and the NSRC shall be -notified within-24 hours.

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j b.

A Safety, Limit Violation Report shall be prepared.

The report shall l

be reviewed by the'PORC. -This-reportishall describe (1) applicable circumstances. preceding -_the-violation, (2). ef.fects of' the violation-L upon unit components, systems, or~ st'uctures,l and (3)! corrective..

l action taken to prevent-recurrence.

E The Safety Limit Violation Report shalltbe submitted to the'Comiss_ ion,.

c.

the NSRC, and the Vice President

. Nuclear within 30 days of the viola tion..

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Critical: operation of the' unit snall' not be. resumed -until. authorized -

a by the' Commission.-

j 6.8 -PROCEDURES / INSTRUCTIONS AND PROGRAMS

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6.8.1 Written procedures / instructions shall be estab'lished.1 implemented, and-maintained covering the activities referenced below:

l The applicable procedures recommended inLAppendix A'of Regulatory l

a.

Guide 1.33,: Revision 2,- February:1978.

4 PERRY UNIT 1 6 Amendment No.1, 22,36 s

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ADMINISTRATIVE CONTROLS 6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS (Continued) b.

The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto, c.

Security Plan implementation.

d.

Emergency Plan implementation.

e.

PROCESS CONTROL PROGRAM implementation.

f.

OFFSITE DOSE CALCULATION MANUAL implementation, g.

Radiological Environmental Monitoring Program implementation, h.

Fire Protection Program implementation.

6.8.2 Each administrative procedure of Specification 6.8.1, and changes thereto, shall be reviewed by the PORC and shall be approved by the General Manager, PPOD, and the Director, PPTD, prior to implementation. All procedures / instructions shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes.

Temporary changes to procedures / instructions which do not change the intent of the approved procedures / instructions shall be approved for implementation by two members of the plant management staff, at least one of whom holds a Senior Operator license. These temporary changes shall be documented. The temporary changes shall be approved by the original approval authority within 14 days.

For changes to procedures / instructions which may involve a change in intent of the procedures / instructions, the original approval authority shall approve the change prior to implementation.

6.8.4 The following programs shall be established, implemented,- end maintained:

j a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those partions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the HPCS, RHR, RCIC, LPCS, feedwater leakage control system, the hydrogen analyzer portion of Combustible Gas Control, and post-accident sampling systems. The program shall include the following:

1.

Preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at refueling cycle intervals or less, i

PERRY - UNIT 1 6-16 Amendment No. 22 l

sa nou UNITED STATES

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g NUCLEAR REGULATORY COMMISSION l

WASHINGTON,0 C.20555

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CLEVELAND ELECTRIC ILLUMINATING company CENTERIOR SERVICE COMPANY l

DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY L

PENNSYLVANIA: POWER COMPANY I

TOLED0 EDISON COMPAN%

DOCKET NO. 50-440 PERRY. NUCLEAR POWER PLANT,- UNIT NO.1 FACILITY'0PERATING LICENSE' License No. NPF-58~

1.

The Nuclear Regulatory Comission (the Comission) _has.found that:

A.

_ The application -for -license filed by the Cleveland Electric Illuminating' Company * (CEICO)< and Centerior' Service Company _ acting l

on their own behalf'and as agents for the:Duquesne Light-Company,

-f Ohio Edison Company, Pennsylvania? Power 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 cComis,

sion's regulations set forth in'10 CFR Chapter ILand al1 required i

notifications to.other agencies or bodies shave been: duly made; 4

l B.

Construction _of the Perry Nuclear Power: Plant, dnit?Ho'.1 :(the l

L facility) has been substantially. completed inJconformity.with -.

Construction Permit No. CPPR-148 and the application, as. amended, the' provisions-of the Act, Land the regulations: of(thelComission; C.

.The facility.will operate in conformity:with the' application, as i

amended, the_ provisions'of,the Act, and the: regulations:of the Com-mission,-(except as exempted from compliance ~in?Section 2.DJbelow);:

D.

There is reasonable assurance: (1) that' the' activities -authorized by _

L) this operating license can be conducted without endangering-the health and safety of the public, and:(ii') that such activities will belconducted in compliance with the Comission's regulations: set forth in 10 CFR l'

-Chapter I (except as exempted from-compliance in Section 2.D below);

• Cleveland Electric Illuminating Company and-Centerior Service Compa y (both.off which are wholly-owned subsidiaries of Centerior Energy: Corporation are authorized to act as agents for Duquesne Light Company,_ Ohio Edison Ccmpany, Pennsylvania Power Company and the Toledo' Edison Company, and have exclusive l

responsibility and. control over the physical construction, operation and-maintenance of the facility.._Centerior Service _ Company was added as a licensee i

'by Amendment: No. 36.

Amendment No. 36

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E.

The Cleveland Electric Illuminating Company is technically-qualified to engage in the activities authorized by-this license in accordance a

with the Commission's regulations-set forth in-10 CFR Chapter I;-

F.

The licensees have satisfied the applicable provisions.of 10 CFR Part 140 " Financial-Protection Requirements and'-Indemnity Agreements,"

1 of-the Commission's regulations;.

G.

The issuance of this license will not be inimical to:the common defense.

O and security.or to the health and safety of the.public;.

j H.

After weighing the environmental, economic, technical and ottier bene-I fits of the facility against environmental and other costs and con-sidering available alternatives, the issuance of this Facility Oper--

ating. License No. NPF-58, subject to the conditions for protection of the environment set forth in the Environmental Protection 1 Plan: attached

~

o as Appendix B,.is in accordance with?10 CFR Part 51 of the Commission's regulations and all; applicable requirements 'have been-. satisfied; and 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 regarding this facility,-the' Partial-Initial:

Decisions. issued December 2,1983 and September 3,-1985 by? the' Atomic Safety and Licensing Board'in regard to this facility (affinned by ALAB-;

841 dated July 25,1986) and pursuant 'to approval by the Nuclear Regula-tory Comission-at a meetingTon November 7,;1986, Facility,0perating.

License Not NPF-58,. which supersedes the license for fuel. loading -and low power testing. License No.1NPF-45/ issued on March 18o 1986,71s1hereby issued to the Cleveland Electric Illuminating Company, Centerior Service.

Company, Duquesne Light. Company, Ohio Edison Company,- Pennsylvania Power Company'and Toledo Edison Companf (the licensees) to readLasifollows:

A.

The" license applies to the Perry _ Nuclear Power? Plant,' Unit No..'1, a i

' boiling water nuclear reactor and assocjated equipment (the facility).

-owned 1by the Cleveland! Electric : Illuminating' Company, Duquesne Light:

i Company, Ohio Edison Company oPennsylvania: Power Company and the' Toledo Edison Company. The facility isLlocated on the' shore of ' Lake :

-Erie in Lake County, Ohio,iapproximately. 35 miles: northeast of Cleve -

land, Ohio and is' described Lin the-licensees'L Final: Safety' Analysis-Report, as supplemented and:amendedbandiin the' licensees' Environ-mental 1 Report, ;as supplemented; and: amended.:

B.

Subject to the conditions and requirements incorporated herein, the

. Commission hereby licenses:.

(1) ' The Cleveland Electric ' Illuminating ConipanyL(CEIC0)* pursuantt 1l Lto Section.103 of;-theiAct and :10_CFR Part-50 Cto possess,=use?

and operate thel acility at the designated' location intLakei.

f County,-' Ohio, in accordance.withethe procedures andGlimitations,;

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' set:forth~in'this; license, s

• The CEICO. nuclear organization reports to Centerior Service-~Com' any.

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E Amendment Noi 36-

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- (2) Technical Specifications The Technical Specifications contained.in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through.

Amendment No. 36 are hereby. incorporated into this-license; Cleveland Electric -Illuminating Company shall _ operate-the facility in accordance-with the Technical Specifications and the Environmental Protection Plan, t

-(3) Antitrust Conditions l

a.-

Cleveland Electric. Illuminating : Company, Duquesne Light Company, l

0hio Edison Company, Pennsylvania Power Company and the Toledo Edison Company shall comply with the antitrust conditions-delineated in Appendix -C to this license; Appendix C:i_s hereby.

incorporated into this' license.

b.~

Centerior Service Company'(CSC) shall comply with the antitrust conditions delineated <in Appendix C-to this license as if named therein. - CEICO is responsible and accountable _ for the actions of CSC -to the extent that CSC's actions. contravene the' antitrust:

license conditions in Appendix C to-this~1icense.- '

i (4) Post-Fuel-Loading Initial Test Program (Section 14, SSER #3)* -

Any changes to the' Initial Test Program described in Section 14 of the FSAR made in accordanceLwith 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)

Within six (6) months after exceeding 5% of rated thermal power, CEICO shall submit the. Initial Inservice ' Inspection Program required by 10 CFR-50.55(a)1for the'NRCLstaff's rt 'ew and approval.

(6)

Fire Protection (Section 9.5, SER,- SSER #1,- 2,--3, 4.- 7 and 8)

.CEICO shall comply with the-following-. requirements-of the fire:

. protection pr.ogram: CEICO shall implement,and maintain.in-effect all -provisions of-the _ approved. fire protection program as descr.ibed -

in the Fina1> Safety Analysis, Report as amended,7 or the Perry-f Nuclear Power Plant ~ and as approved in-the Safety Evaluation

-Report -(NUREG-0887) dated May 1982 and Supplement Nos.1 thru 10 thereto, subject to the following Lprovisions:

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..

• The parenthetical notation following the title of many license conditions-denotes the section ofathe Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed;

' Amendment No. 36 q

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