ML20136J567

Amends 110 & 93 to Licenses DPR-53 & DPR-69,respectively, Revising Tech Specs to Reflect Corporate Reorganization, Changes to Titles of Individuals & Elimination of Member from Plant Operations Safety Review Committee

ML20136J567
Person / Time
Site:	Calvert Cliffs   (DPR-053, DPR-069)
Issue date:	12/30/1985
From:	Thadani A Office of Nuclear Reactor Regulation
To:	Baltimore Gas & Electric Co (BGE)
Shared Package
ML20136J571	List: ML20136J567 ML20137A324
References
DPR-53-A-110, DPR-69-A-093 NUDOCS 8601140064
Download: ML20136J567 (36)

Text

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g UNITED STATES 3

g NUCLEAR REGULATORY COMMISSION 7,

WASHINGTON, D. C 20555 E

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%,.....f BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore, Gas & Electric Company (the licensee) dated November 1,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; 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 Connission's regulations; D.

The issuance of this amendment will not be inimical to the connon i

defense and security or to the health and safety of the public; and

.i E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have j

been satisfied.

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G601140064 e51230 DR ADOCK 05 j7

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.110, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR TH NUCLEAR REGULATORY COMISSION

/ (L9w Asho C'.'Thadant, Ofrector PWR oject Directorate #8 Division of PWR Licensing-8

Attachment:

Changes to the Technical Specifications Date of Issuance: December 30, 1985

6.0 ADf11N!STRATIVE CONTROLS 6.1' RESPONSIBILITY 6.1.1 operation and skall delegate in writing the succession to this responsib1$

l during his absence.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

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

c.

At least two licensed Operators shall be present in the control room during reactor start-up scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor, e.

All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of both units (4 members) or any personnel required for other essential functions during a fire emergency.

CALVERT CLIFFS - UNIT 1 6-1 Amendment No. 28./fl.110 1

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CALVERT CLIFFS - UNIT 1 6-3 Amendment No. JJ,21,2$,$8,76,110 l

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

Condition of Unit 1 - Unit 2 in MODES 1, 2,1 or 4 LICENSE APPLICABLE MODES CATEGORY 1, 2. 3 & 4 5&6

.e 50L**

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3 Shift Technical Advisor 1##

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Condition of Unit 1 - Unit 2 in MODES 5 or 6 LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 50L**

2 1*

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3 2

Non-Licensed 3

3 Shift Technical Advisor 1##

0 CALVERT CLIFFS - UNIT I Amendment No. NJ,f g 6-4 B

TABLE 6.2-1 (Continued)

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS during fuel reloading.

• • Assumes each individual is licensed on each unit.

1. Shift crew composition 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 of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.1.

1. 1. The STA shall be qualified / serve as follows:

(1) With one unit in MODE 5 or 6, and the other unit in MODE 1, 2 3 or 4 the SOL holder other than the Shift Supervisor shall serve as the STA.

(2) With one unit defueled and the other unit in MODE 1, 2, 3 or 4, the STA shall be an SOL holder in addit.on to the one SOL required.

(3) With both units in MODE 1, 2. 3 or 4, the STA shall be an SOL holder in addition to the two 50Ls required.

As an alternative to the above, the STA may be an individual with the following minimum qualifications: a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

CALVERT CLIFFS - UNIT 1 6-5 Amendment No. 53,106 9

9

i 8

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS

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,6.3.1 Each member of the facility staff shall meet or exceed the mininum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the j

Radiation Safety Engineer who shall meet or exceed the qualifications of j

Regulatory Guide 1.8 September 1975, and (2) the Shift Technical Advisor who shall have a Bachelor's Degree or equivalent in a scientific or engineering j

discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

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6.4 TRAINING

!l 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Nuclear Training and shall meet or exceed the requirements and recomendations of 1

Section 5.5 of ANSI N18.1-1971 and Appendix "A'.' of 10 CFR Part 55, as applicable.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Quality Control and Support and shall meet i

i or exceed the requirements of Section 27 of the NFPA Code-1975.

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6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW Com!TTEE (POSRC)

FUNCTION 6.5.1.1 The POSRC shall function to advise the Manager-Nuclear Operations on all matters related to nuclear safety.

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COMPOSITION 1

6.5.1.2 The POSRC shall be composed of the:

Chairman:

Manager-Nuclear Operations l

Member:

General Supervisor - Operations Member:

General Supervisor - Electrical and Controls i

Member:

General Supervisor - Chemistry i

Member:

General Supervisor - Mechanical Maintenance l

Member:

General Supervisor - Technical Services Engineering Member:

l General supervisor - Radiation Safety Member:

General Supervisor - Plant and Project Engineering l

l ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternater, shall participate as voting members in POSRC activities at ahy one time.

i m uu6 CLIFFS - UNIT 1 6-6 Amendment No. 28.AJ.lA,82,85, 110 i

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i ADMINISTRATIVE CONTROLS f

MEETING FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month and as convened j

by the POSRC Chairman or his designated alternate.

j QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chairman or his designated l

alternate and four members including alternates.

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RESPONSIBILITIES j

6.5.1.6 The POSRC shall be responsible for:

i j

a.

Rsview of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as j

determined by the Manager - Nuclear Operations to affect nuclear safety. l I

b.

Review of all proposed tests and experiments that affect nuclear I

i safety.

j c.

Review of all proposed changes to Appendix "A" Technical Specifications.

i d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications includ-e.

ing the preparation and forwarding of reports covering evaluation and i

recomendations to prevent recurrence to the Vice President Nuclear 4

i Energy and to the Chairman of the Off Site Safety Review Committee.

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f.

Review of all REPORTABLE EVENTS.

i Review of facility operations to detect potential safety hazards.

I g.

h.

Performance of special reviews investigations or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review Comittee.

t i

1.

Review of the Plant Security Plan and implementing procedures and shall j

submit recommended changes to the off site safety Review comittee.

l t

J. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Off Site Safety Review Comittee.

i k.

Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 255 of the Ifmits of Specification 3.11.1.2. 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation, recomendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Manager-Nuclear Operations and the off Site Safety Review Comittee.

I 1.

Review of changes to the PROCESS CONTROL PROGRAM and the 0FFSITE DOSE I

CALCULATION MANUAL.

CALVERT CLIFFS - UNIT I 6-7 Amendment No. 26,38,$3,94,/M,110 4

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Comittee shall:

a.

Recomend to the Manager-Nuclear Operations written approval l

or disapproval of items considered under 6.5.1.6(a) through (d)above, b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

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-c.

Nuclear Energy and the Off Site Safety Review Comittee of disagree-ment between the POSRC and the Manager-Nuclear Operations; however, the Manager-Nuclear Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Energy and Chainnan of the l

Off Site Safety Review Comittee.

o 6.5.2 0FF SITE SAFETY REVIEW COMITTEE (OSSRC)

FUNCTION

~

6.5.2.1 The Off Site Safety Review Comittee 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 and non-destructive examination e.

Instrumentation and cortrol f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices CALVERT CLIFFS - UNIT 1 68 Amendment No. H. 110

ADMINISTRATIVE CONTROLS i

COMPOSITION 3

6.5.2.2 The OSSRC shall be composed of at least seven members, including the Chairman. Members of the OSSRC may be from the Nuclear Energy Division i

or other BG&E organization or from organizations external to BG&E and shall collectively have expertise in all of the areas of 6.5.2.1.

QUALIFICATIONS J

6.5.2.3 The Chairman, members and alternate members of the OSSRC shall be

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appointed in writing by the Vice President - Nuclear Energy and shall have l

an academic degree in engineering or a physical science, or the equivalent, and in addition shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1.

No more than two alternates shall participate as voting members in OSSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the OSSRC Chainnan to provide expert advice to the OSSRC.

f MEETING FREQUENCY 6.5.2.5 The OSSRC shall meet at least once per six months.

4 4

I QUORUM 6.5.2.6 The quorum of the OSSRC necessary for the performance of the 055RC review and audit functions of these Technical Specifications shall consist of more than half the OSSRC membership or at least four members, whichever is greater.

• This quorum shall include the Chairman or his appointed alternate and the OSSRC members, including appointed alternates, meeting the require-ments of Specification 6.5.2.3.

No more than a minority of the quorum shall have line responsibility for operation of the plant.

4 I

CALVERT CLIFFS - UNIT 1 6-9 Amendment No. D,

110

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The OSSRC shall review:

The safety evaluations for 1) changes to procedures, equipment a.

.or systems and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.5g, 10 CFR.

t Proposed tests or experiments which involve an unreviewed c.

safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or this Operating License.

Violations of codes, regulations, orders Technical Specifications, e.

license requirements, or of internal pmcedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

g.

All REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency iri some aspect of design or operation of safety related structures, systems, or components.

1.

Reports and meetings minutes of the P03RC.

CALVERT. CLIFFS - UNIT 1 6-10 Amendment No. 94

l ADMINISTRATIVE CONTROLS j

)

AUDITS t

6.5.2.8.1 Audits of facility activities shall be perfomed under the cog-i nizance of the OSSRC.

These audits shall encompass:

i The conformance of facility operation to provisions contained within i

a.

I the Technical Specifications and applicable license conditions at-least once per 12 months.

I b.

The perfomance, training and qualification of the entire facility j

staff at least once per 12 months.

The results of actions taken to correct deficiencies occurring in c.

facility equipment, structures, systems or method of operation that j

affect nuclear safety at least once per 6 months.

a d.

The performance of activities required by the Quality Assurance j

Program to meet the criteria of Appendix "B",10 CFR Part 50, at i

least once per 24 months.

e.

Deleted.

f.

The Safeguards Contingency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR 73.40(d).

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j g.

Any other area of facility operation considered appropriate by the l

OSSRC or the Vice President-Nuclear Energy.

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h.

The Facility Fire Protection Program and implementing procedures at l

least once per 24 months, i

1.

An independent fire protection and loss prevention program inspection i

and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire i

j protection firm.

l

j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant i

at least once per 36 months.

i; k.

I The radiological environmental monitoring program and the results thereof at ' east once per 12 months, i

1.

The 0FFS!TE DOSE CALCULATION MANUAL and impismenting procedures at least once per 24 months.

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I The PROCES$ CONTROL PROGRAM and implementing procedures for procer.-

m.

sing and packaging of radioactive wastes at least once per 24 months.

t j

n.

The performance of activities required by to.; t,s..cy Assurance Program for effluent and environmental monitoring at least once per i

12 months.

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CALVERT CLIFFS - UNIT 1 6-11 Amendment No. 28,82,195,110 t

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ADMINISTRATIVE CONTROLS 6.5.2.8.2 Review of facility activities shall be performed under the cognizance of the OSSRC.

These reviews shall encompass:

The Facility Emergency Plan and implementing procedures at least a.

once per 12 months in accordance with 10 CFR Part 50.54(t).

AUTHORITY 6.5.2.9 The 055RC shall report to and advise the Vice President-Nuclear Energy l on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of 055RC activities shall be prepared, approved and distributed as indicated below:

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

forwarded to the Vice President Nuclear Energy within 14 days following each meeting.

l b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President-Nuclear Energy within 14 days following completion of the review.

Audit reports encompassed by Section 6.5.2.8 above, shall be c.

forwarded to the Vice President-Nuclear Energy and to the manage-ment positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTA8LE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA8LE EVENTS:

The Commission shall be notified and a report submitted a.

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

Each REPORTABLE EVENT shall be reviewed by the POSRC and the results of this review shall be submitted to the 055RC and the Vice President-Nuclear Energy.

CALVERT CLIFFS - UNIT 1 6-12 Amendment No. A8,82.7A.198.110

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

The facility shall be placed in at least HOT STANDBY within one hour.

a.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President-l Nuclear Energy and the OSSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I A Safety Limit Violation Report shall be prepared. The report shall c.

be reviewed by the POSRC. This report shall describe (1) applicable cir,cumstances preceding the violation, (2) effects of the violatien upon 'acility components, systt:ms or structures, and (3) corrective

• actio.. taken to prevent recurrence.

d.

The Safety Limit Violation Report sha11 be submitted to the Comission, the OSSRC and the Vice President-Nuclear Energy I

within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

The applicable procedures recommended in Appendix "A" of a.

Regulatory Guide 1.33 Revision 2 February 1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation, f.

Fire Protection Program implementation.

g.

The amount of overtime worked by plant staff members performing safety related functions must be limited in accordance with the NRC Policy Statement on working Hours (Generic Letter No. 8212).

h.

PROCESS CONTROL PROGRAM implementation.

1.

OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above and changes thereto shall be reviewed by the POSRC and approved by the Manager Nuclear Operations prior to implementation and reviewed periodically as set forth in administrative procedures.

CALVERT CLIFFS - UNIT 1 6 13 Amendment No. 26,0.75.82. # 5. 110

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

The intent of the original procedure is not altered.

a.

I b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, The change is documented, reviewed by the POSRC and approved by c.

the Manager-Nuclear Operations within 14 days of implementation, j

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

I

$TARTUP REPORT i

6.9.1.1 A sunnary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, amenenent to the license involving a planned increase in power i

(3) installation of fuel that has a different desi l,

factured by a different fuel supplier, and (4) modjn or has been manu-(

i fications that may l

have significantly altered the nuclear, thermal, or hydrautic perfor-mance of the plant.

l 6.9.1.2 The startup report shall address each of the tests identified t

in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test l

program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other connitments shall be included in this report.

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I CALVERT CLIFFS - UNIT 1 6-14 Amendment No. 29,$3,82,74.A W,110 t

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ADMINISTRATIVE CONTROLS I

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b.

A high radiation area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.1.a.

i above, and in addition locked barricades shall be provided to l

prevent unauthorized entry into such areas and the keys shall be l

1 maintained by the Supervisor-Radiation Control Operations and the l

j Operations Shift Supervisor on duty under their separate administra-1 tive control.

l 6.13 SYSTEM INTEGRITY The licensee shall implement a program to reduce leakage from systems outside i

containment that would or could contain highly radioactive fluids during a serious transient or accidsnt to as low as practical levels. This program shall include the following:

1 1

l I

1.

)

Provisions establishing preventive maintenance and periodic visual inspection requirements, and i

2.

Leak test requirements for each system at a frequency not to j

exceed refueling cycle intervals.

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6.14 100!NE MONITORING 5

i The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under

]

accident conditions. This program shall include the following:

I 1.

Training of personnel, i

l 2.

Procedures for monitoring, and l

l 3.

Provisions for maintenance of sampling and analysis equipment, l

=

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6.15 PROCESS CONTROL PROGRAM (PCP) l I

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6.15.1 The PCP shall be approved by the Commission prior to implementation.

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4.15.2 Licensee initiated changes to the PCP:

1.

S'ha11 be submitted to the Comission in the Semiannual Radioactive i

Effluent Release Report for the period in which the change (s) was l

made. This submittal shall contains i

(

An evaluation supporting the premise that the change did not a.

i reduce the overall conformance of the solidified waste product i

to existing criteria for solid wastest and I

CALVERT CLIFFS - UNIT I 6 21 Stddt/Jp/2//pf//M/

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j Amendment No. Jff, j

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ADMINISTRATIVE CONTROLS b.

A reference to the date and the POSRC meeting number in which the change (s) were reviewed and found acceptable to the POSRC.

2.

Shall become effective upon review by the POSRC and approval of the Manager-Nuclear Operations.

6.16 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.16.1 The ODCM shall be approved by the Comission prior to implementation.

6.16.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the comission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.

This submittal shall contain:

Sufficient information to support the rationale for the change.

a.

Information submitted should consist of a package of those pages of the ODCH to be changed with each page numbered and.

provided with a change number and/or change date together with appropriate analyses or evaluations justifying the change (s);

b.

A detennination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detenninations; and t

Documentation of the fact that the change has been reviewed c.

and found acceptable by the FOSRC.

2.

Shall become effective upon review by the POSRC and approval of the Manager-Nuclear Operations.

l 6.17 MAJOR QHANGIS T0 RA0!0 ACTIVE LIOVID. GASEOUS AND SOLID WASTE 7 tie 4YMEst~ SYSTEMS

~

6.17.1 Licensee initiated major changes to the radioactive waste systems (liquid. gaseous and solid) shall be reported to the Comission in the Semi-annual Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contains A description of the equipment, components and processes involved, a.

b.

Documentation of the fact that the change including the safety analysis was reviewed and found acceptable by the P0$RC.

' " CALVERT ClarFS - UNIT 1 6 22 Amendment No. H 5)99, 110

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U::lTED STATES g

NUCLEAR REGULATORY COMMISSION r.

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%,.....f BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.93 License No. DPR-69 The Nuclear Regulatory Comission (the Comission) has found that:

A.

The app 11 cation for amendment by Baltimore Gas & Electric Company (the ifcensee) dated November 1,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter !!

8.

The facility will operate in confonnity with the application, the l

provisions of the Act, and the rules and regulations of the i

Comissions C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the pubite, and (11) that such activities will be 3

conducted in compliance with the Comission's regulationst i

)

D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the pub 11cl and 1

E.

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

i i

f

.e

. ~

2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-69 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION f

W Asho' d. Thadani, Director PWR Droject Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 30, 1985 e

e

9 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Manager-Nuclear Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

62 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

Each on duty shift shall be composed of at least the minimum a.

shift crew composition shown in Table 6.2-1.

~

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor, At least two licensed Operators shall be present in the c.

control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

All CORE ALTERATIONS after the initial fuel loading shall be e.

directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of both units (4 members) or any personnel required for other essential functions during a fire emergency.

CALVERT CLIFFS - UNIT 2 6-1 Amendment No. 26, 93 J

f

9 r._

Chairman tri of the Board

-1 I

C l President l n

n i

y Vice President Vice President Vi:e President General Services 8

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connection and

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-t Responsibility For Fire i

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Manager r--

Manager Manager Manager Manager Manager l Real Estate &

r-Jl 055RC j Nuclear Nuclear Quality Assurance Nuclear Electric Office Services r-

-*.. Operations Engineering Services

& Stali Services Maintenance Test I

e I

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a Director r -- ' ---, ;

General l5taffl l5taffl l Staff l l5taffl l 5taff l N

Security lPO5RC,P Supervisor Services

........a Operations Fire Prevention tJnit Assistant General R

Supervisor Nuclear i

g Security 1

s et 2

FIGURE 6.2-1 o

MANAGEMENT ORGANIZATION CHART M*

CALVERT CLIFF 5 NUCLEAR POWER PLANT BALTIMORE GAS & ELECTRIC COMPANY

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.I TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

)

l Condition of Unit 2 - Unit 1 in MODES 1. 2. 3 or 4 LICENSE APPLICABLE MODES CATE M Y

1. 2. 3 & 4 5&6 50L**

2 2*

OL**

3 3

Non-Licensed 3

3 Shift Technical Advisor 1##

If#

c.

Condition of Unit 2 - Unit 1 in MODES 5 or 6 LICENSE APPLICABLE MODES CATEGORY

1. 2, 3 & 4 5&6 SQL**

2 1*

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3 2

l Non-Licensed 3

3 Shift Technical Advisor lif 0

CALVERT. CLIFFS. UNIT 2 6-4 Amendment No. 36. 30

TABLE 6.2-1 (Continued)

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS during fuel reloading.

• • Assumes each individual is licensed on each unit.

1. Shift crew composition 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 of on duty shift crew members provided inmediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.7.1.

1. 1. The STA shall be qualified / serve as follows:

(1) With one unit in MODE 5 or 6, and the other unit in MODE 1, 2, 3 or 4, the 50L holder other than the Shift Supervisor shall serve as the STA.

(2) With one unit defueled and the other unit in MODE 1, 2, 3 or 4, He the STA shall be an SOL holder in addition to the one SOL required.

(3) With both units in MODE 1, 2, 3 or 4, the STA shall be an SOL holder in addition to the two SOLs required.

As an alternative to the above, the STA may be an individual with the following minimum qualifications: a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

l l

i l

CALVERT CLIFFS - UNIT 2 6-5 Amendment No. 36,87 i

l

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor ~ Nuclear Training l

and shall meet or exceed the requirements and recomrnendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55, as applicable.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Quality Control and Support and shall meet l

or exceed the requirements of Section 27 of the NFPA Cade-1975.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

FUNCTION 6.5.1.1 The POSRC shall function to advise the Manager-Nuclear Operations on l

all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POSRC shall be composed of the:

Chairman:

Manager-Nuclear Operations l

Member:

General Supervisor - Operations Member:

General Supervisor - Electrical and Controls Member:

General Supervisor - Chemistry Member:

General Supervisor - Mechanical Maintenance Member:

General Supervisor - Technical Services Engineering Member:

General Supervisor - Radiation Safety Member:

General Supervisor - Plant and Project Engineering l

ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in POSRC activities at any one time.

CALVERT CLIFFS - UNIT 2 6-6 Amendment No. JJ,26,36,ff,68, 93

ADMINISTRATIVE CONTROLS MEETING FREQUENCY The POSRC shall meet at least once per calendar month anb as convened 6.5.1.4 by the POSRC Chairman or his designated alternate.

QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chainnan or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:

Review of 1) all procedures required by Specification 6.8 and changes a.

thereto, 2) any other proposed procedures or changes thereto as j

determined by the Manager-Nuclear Operations to affect nuclear safety.

(

b.

Review of all proposed tests and experiments that affect nuclear safety.

Review of all proposed changes to Appendix "A" Technical Specifications, c.

d.

Review of all proposed changes or modifications to plant systems or -

equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications includ-e.

ing the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President-Nuclear Energy and to the Chairman of the Off Site Safety Review Committee.

f.

Review of all REPORTABLE EVENTS.

Review of facility operations to detect potential safety hazards.

g.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review

/

Connittee.

1.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Off Site Safety Review Connittee.

j. Review of the Emergency Plan and implementing procedures and shall submit reconnended changes to the Off Site Safety Review Connittee.

k.

Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the Ifmits of Specification 3.11.1.2, 3.11.2.2 or 3.11'.2.3, including the preparation of reports covering evaluation, reconnendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Manager-Nuclear Operations and the Off Site Safety Review Committee.

l.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

i CALVERT CLIFFS - UNIT 2 6-7 Amendment No. JJ.J5,26,75, Nf,93

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Committee shall:

Recommend to the Manager-Nuclear Operations written approval or a.

disapproval of items considered under 6.5.1.6(a) through (d) above.

l b.

Render determinations in writing with regard to whether or not

~

each item considered under 6.5.1.6(a) through (d) above constitutes an unreviewed safety question.

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 -

c.

Nuclear Energy and the Off Site Safety Review Committee of disagree-ment between the POSRC and the Manager-Nuclear Operations; however, the Manager-Nuclear Operations shall have responsibility for resolu-tion of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Energy and Chairman of the Off Site Safety Review Committee.

l 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

FUNCTION 6.5.2.1 The Off Site Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering chemistry and radiochemistry c.

d.

metallurgy and non-destructive examination instrumentation and control e.

f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices i

CALVERT CLIFFS - UNIT 2 6-8 Amendment No. 26, 93

ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The OSSRC shall be composed of at least seven members, including the Chairman.

Members of the OSSRC may be from the Nuclear Energy Division or l

other BG&E organization or from organizations external to BG&E.

QUALIFICATIONS 6.5.2.3 The Chairman, members and alternate members of the OSSRC shall be appointed in writing by the Vice President - Nuclear Energy and shall have an l

academic degree in engineering or a physical science, or the equivalent, and in addition shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1.

No more than two alternates shall participate as voting members in OSSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the OSSRC Chairman to provide expert advice to the OSSRC.

MEETING FREQUENCY 6.5.2.5 The OSSRC shall meet at least once per six months.

QUORUM 6.5.2.6 The quorum of the OSSRC necessary for the performance of the OSSRC review and audit functions of these Technical Specifications shall consist of more than half the OSSRC membership or at least four members, whichever is greater. This quorum shall include the Chairman or his appointed alternate and the OSSRC members, including appointed alternates, meeting the require-ments of Specification 6.5.2.3.

No more than a minority of the quorum shall have line responsibility for operation of the plant.

L CALVERT CLIFFS - UNIT 2 6-9 Amendment No. 26, 93

ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The OSSRC shall review:

The safety evaluations for 1) changes to procedures, equipment or a.

systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

Proposed tests or experiments which involve an unreviewed safety c.

question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in 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 normal and expected performance of plant equipment that affect nuclear safety.

g.

All REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systens, or components.

1.

Reports and meeting: minutes of the POSRC.

CALVERT CLIFFS - UNIT 2 6-10 Amendment No. 75

ADMINISTRdTIVECONTROLS 1

AUDITS 6.5.2.8.1 Audits of facility activities shall be performed under the cog-nizance of the OSSRC.

These audits shall encompass:

The conformance of facility operation to provisions contained within a.

the Technical Specifications and applicable Ifcense conditions at least once per 12 months.

b.

The performance, training and qualification of the entire facility staff at least once per 12 months.

The results of actions taken to correct deficiencies occurring in c.

facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.

The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR Part 50, at least once per 24 months.

e.

Deleted, f.

The Safeguards Contingency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR 73.40(d).

g.

Any other area of facility operation considered appropriate by the OSSRC or the Vice President. Nuclear Energy.

l h.

The Facility Fire Protection Program and implementing procedures at least once per 24 months.

1.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing

?

either qualified offsite licensee personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

k.

The radiological environmental monitoring program and the results thereof at least once per 12 months, l.

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

The PROCESS CONTROL PROGRAM and implementing procedures for proces-m.

sing and packaging of radioactive wastes at least once per 24 months.

The performance of activities required by the Quality Assurance n.

i Program for effluent and environmental monitoring at least once per 12 months.

CALVERT CLIFFS - UNIT 2 6-11 Amendment No. JJ,g), AC/, 93

ADMINISTRATIVE CONTROLS 6.5.2.8.2 Review of facility activities shall be performed under the cognizance of the OSSRC.

These reviews shall encompass:

The Facility Emergency Plan and implementing procedures at least a.

once per 12 months in accordance with 10 CFR Part 50.54(t).

AUTHORITY 6.5.2.9 The OSSRC shall report to and advise the Vice President - Nuclear Energy on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 as indicated below: Records of OSSRC activities shall be prepared, approved and distri Minutes of each OSSRC meeting shall be prepared, approved and a.

forwarded to the Vice President - Nuclear Energy within 14 days l

following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President - Nuclear Energy within 14 days following completion of the review.

Audit reports encompassed by Section 6.5.2.8 above, shall be c.

forwarded to the Vice President - Nuclear Energy and to the manage-

]

ment positions responsible for the areas audited within 30 days after completion of the audit.

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

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

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

Each REPORTABLE EVENT shall be reviewed by the POSRC and the results of this review shall be submitted to the OSSRC and the Vice President - Nuclear Energy.

CALVERT CLIFFS - UNIT 2 6-12 Amendment No. 26,65,7E,$5, 93

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

The facility shall be placed in at least HOT STANDBY within one hour.

a.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President -

Nuclear Energy and the OSSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A Safety Limit Violation Report shall be prepared. The report shall c.

be reviewed by the POSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, the OSSRC and the Vice President - Nuclear Energy l

within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

a.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

i g.

The amount of overtime worked by plant staff members performing safety related functions must be limited in accordance with the NRC Policy Statement on working Hours (Generic Letter No. 82-12).

h.

PROCESS CONTROL PROGRAM implementation.

j 1.

OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each pro ~cedure and administrative policy of 6.8.1 above and changes thereto shall be reviewed by the POSRC and approved by the Manager-Nuclear Operations prior to implementation and reviewed periodically as set forth in administrative procedures.

CALVERT CLIFFS - UNIT 2 6-13 Amendment No.JJ,25,55,55,86,93 I

l

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:

a.

The intent of the original procedure is not altered.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

E The change is documented, reviewed by the POSRC and aooroved by c.

the Manager-Nuclear Operations within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS

6. 9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT

6. 9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in power level.

(3) installatio.n of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modi.fications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values s

of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and speci fications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details re, quired in license conditions based on other commitments shall be included in this report.

f

._a CALVERT CLIFFS - UNIT 2 6-14 AmendmentNo.J5.26,65.75,?/.;93

l ADMINISTRATIVE CONTROLS

~

b.

A high radiation area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.1.a. above, and in addition locked barricades shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained by the Supervisor-Radiation Control Operations and the Operations Shift Supervisor on duty under their separate administrative control.

l 4

6.13 SYSTEM INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall inclnfe the following:

1.

Provisions establishing preventive maintenance and periodic j

visual inspection requirements, and f

2.

Leak test requirements for each system at a frequency not j

to exceed refueling cycle intervals.

t i

6.14 IODINE MONITORING i

The licensee shall implement a program which will ensure the capability to accurately determine the airborne fodine concentration in vital areas under accident conditions. This program shall include the following:

1.

Training of personnel.

2.

Procedures for monitoring, and l

3.

Provisions for maintenance of sampling and analysis equipment.

6.15 PROCESS CONTROL PROGRAM (PCP) 6.15.1 The PCP shall be approved by the Comission prior to implementation.

6.15.2 Licensee initiated changes to the PCP:

l 1.

Shall be submitted to the Comission in the Semiannaul Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

CALVERT CLIFFS - UNIT 2 6-:

9tdd//J9/ N/894 Amendment 36,53, 77,86, M, g3 1

l t-

ADMINISTRATIVE CONTROLS An evaluation supporting the premise that the change did not a.

reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and b.

A reference to the date and the POSRC meeting number in which the change (s) were reviewed and found acceptable to the POSRC.

2.

Shall become effective upon review by the POSRC and approval of the Manager-Nuclear Operations.

6.16 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.16.1 The ODCM shall be approved by the Commission prior to implementation.

~

6.16.2 Licansee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the chan e(s) was made effective. This submittal shall contain:

Sufficient information to support the rationale for the change.

a.

Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a change number and/or change date together with appropriate analyses or evaluations justifying the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; ano Documentation of the fact that the change has been reviewed and c.

found acceptable by the POSRC.

2.

Shall become effective upon review by the POSRC and approval of the Manager-Nuclear Operations.

6.17 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.17.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Semi-annual Radioactive Effluent Release Report for the period in which the modi-fication to the waste system is completed. The discussion of each change shall contain:

A description of the equipment, components and processes involved.

a.

b.

Documentation of the fact that the change including the safety analysis was reviewed and found acceptable by the POSRC.

i CALVERT CLIFFS - UNIT T' 6-22 Amendment No. 86,/g, 93

_ _ _