ML19331C229

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Amends 43 & 26 to Licenses DPR-53 & DPR-69,respectively, Updating Organization Charts & Safety Committee Membership Per Recent Reorganization
ML19331C229
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/31/1980
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19331C230 List:
References
NUDOCS 8008140415
Download: ML19331C229 (46)
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BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated July 24, 1979, as supplemented June 24, 1980, conplies 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 I; B.

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

There is reasonable assurance (1) that the act eities authorized by this amendment can be conducted without enc.ongering 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 common 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachrent to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-53 is hereby i

amended to read as follows:

l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are hereby incorporated in the i

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

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3.

This 11. cense amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY C0fS11SSION S'

Robert. Clark, Chie Operating Reactors Branch #3 Division of Licensing Attachment':

Changes to the Technical Specifications Date of Issuance: July 31, 1980 i

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ATTACHMENT TO LICEtSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. DPR-53

. DOCKET NO. 50-317 Replace the!following pages of the Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corre-sponding overleaf pages are also provided to maintain document completeness.

Appendix A Pages 6-1 6-2 6-3 6-6 6-7 6-8 6-9 6-12 6-13 6-14 6-20 Appendix B Pages 5.1-1 5.2-1 5.4-1 5.5-1 I

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall facility operation and shall delegate in writing the succession to this responsi-bility 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:

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 tmergency.

CALVERT CLIFFS - UNIT 1 6-1 Amendment No. fl. 43

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

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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 the fuel loading.
    • Assumes each indivipsal is licensed on each unit.
  1. Sh,1ft 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 cred members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.1.

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CALVERT CLIFFS - UNIT 1 6-5 l

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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum for comparable positions, except for qualifications of ANSI N18.1-1971 I

the Radiation Safety Engineer who shall meet or exceed the qualifications l

of Regulatory Guide 1.8, September 1975.

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

Training and Technical Services and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

A training program for the Fire Brigade shall be maintained under 6.4.2 the direction of the General Supervisor - Training and Technical Services

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and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.

6.5 REVIEW AND AUDIT PLANT OPERATIONS AND SAFETY REVIEW COMI:TTEE (POSRC

6. 5.1
FUNCTION, The POSRC shall function to ad. vise the Plant Superintendent on 6.5.1.1 all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POSRC chall be composed of the:

Plant Superintendent Chairman:

General Supervisor - Operations General Supervisor - Electrical and Controls Member:

Member:

General Supervisor - Chemistry Member:

Principal Engineer - Plant Engineering Nuclear Member:

General Foreman - Maintance and Modifications Member:

Supervisor - Nuclear Fuel Management s

Member; General Supervisor - Radiation Safety General Supervisor - Training and Technical Services Member:

Member:

ALTERNATES _

All alternate members shall be appointed in writing by the 6.5.1.3 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.

6-6 Anendment No. 25,43 CALVERT CLIFFS - UNIT 1

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

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

RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes therato as determined by the Plant Superintendent to affect l

nurlear safety.

b.

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

c.

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

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

e.

Investigation of all violations of the Technical Specifications including the preparation and fory:arding of reports covering evaluation and recommendations to prevent recurrence to the Manager - Nuclear Power Department and to the Chairman of the l

Off Site Safety Review Committee, f.

Review all written reports requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

g.

Review of facility operations to detect potential safety hazards.

h.

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

i.

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

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Off Site Safety Review Committee.

l CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 75,30,4; i

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

Recomend to the Plant Superintendent written approval or l

a.

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.

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 Manager -

I Nuclear Power Department and the Off Site Safety Review Committee of disagreement between the POSRC and the Plant Superintendent; however, the Plant Superintendent shall have j

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 Manager - Nuclear Power Department and l

Chairman of the Off Site Safety Review Comittee.

6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

FUNCTION 6.5.2.1 The Off Site Safety Review Comittee shell function to provide in:1ependent review and audit of designated activities in the I

areas of:

a.

nuclear power plant operations l

b.

nuclear engineering c.

chemistry and radiochemistry d.

metallurgy and non-destructive examination l

e.

instrumentation and control f.

radiological safety l

mechanical and e?ectrical engineering g.

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quality assurance practices l

l CALVERT CLIFFS - UNIT 1 6-8 Amendment No.43 l

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ADMINISTRATIVE CONTROLS COMPOSITION I

6.5.2.2 The OSSRC shall be composed of at least seven members, includina the Chairman. Members of the OSSRC may be from the Supply Division or '

other BGAE organization or from orgainizations external to BG&E and shall j

collectively have expertise in all of the areas of 6.5.2.1.

QUALIFICATIONS t

6.5.2.3 The Chairman, members and alternate members of the OSSRC shall be appointed in writing by the Vice President - Supply and shall have an academic degree in engineering or a physical science, or the equiva-lent, 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 i

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 I

have line responsibility for operation of the plant.

CALVERT CLIFFS - UNIT 1 6-9 Amendment No. 43

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9 ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The OSSRC shall review:

a.

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

c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or this Operating License.

e.

Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

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

g.

All written reports requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

h.

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

i.

Reports and meetings minutes of the POSRC.

e CALVERT CLIFFS - UNIT 1 6-10 m

ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the OSSRC.

These audits shall encompass:

a.

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

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b.

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

c.

The results of actions taken to correct deficiencies occurring in 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 50, at least once per 24 months.

e.

The Facility Emergency Plan and implementing procedures at least once per 24 months.

f.

The Facility Security Plan and implementing procedures at least once per 24 months.

g.

Any other area of facility operation considered appropriate by the OSSRC or the Vice President-Supply.

h.

The Facility Fire protection Program and implementing pro-cedures at least once per 24 months.

i.

An independent fire protection and loss prevention program I

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 pre-vention program shall be performed by a qualified outside fire consultant at least once per 36 months.

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

CALVERT CLIFFS - UNIT 1 6-11 Amendment No. 26 i

ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of OSSRC activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each OSSRC meeting shall be prepared, approved and forwarded to the Vice President-Supply within 14 days 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-Supply within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President-Supply and to the management positions responsible for the areas audited within 30 days af ter completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 5.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the POSRC and submitted to the OSSRC and the Manager - Nuclear Power Department.

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CALVERT CLIFFS - UNIT 1 6-12 Amendment No. 43 l

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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 f acilty shall be p aced in at least HOT STANDBY within a.

one hour.

The NRC Operations Center shall be notified by telephone as soon b.

The Manager - Nuclear as possible and in all cases within one hour.

Power Department 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 be reviewed by the POSRC. This report shall describe (1) app-c.

licable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

The Safety Limit Violation Report shall be submitted to the Commission d.

the OSSRC and the Manager - Nuclear Power Department within 14 days of the violation.

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

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

Regulatory Guide 1.33, November,1972.

b.

Refueling operations, Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

Emergency Plan implementation.

e.

f.

Fire Protection Program implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed hy the POSRC and approved by the Plant Superintendent prior to implementation and reviewed periodically L

l as set forth in administrative procedures.

CALVERT CLIFFS - UNIT 1 6-13 AmendmentNo./[,43 O

ADMINISTRATIVE C0h'TROLS

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

a.

The intent of the originial procedure is not altered.

b.

The change is ' approved by two members of the plant management

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' staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the POSRC and approved by the Plant Superintendent within 14 days of implementation.

6.9 REPORTING REQUI?.EMENTS ROUTINE REPORTS AhD 9"00RTABLE OCCURRENCES 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 testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The startuo report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design oredictions 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.

l CALVERT CLIFFS - UNIT 1 6-14 Amendment No. $/,43 l

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f ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION The following records shall be retained for at least five years:

6.10.1 Records and l'ogs of facility operation covering time interval a.

at each power level.

Records and logs of principal maintenance activities, inspections, b.

repair and replacement of principal items of equipment related to nuclear safety.

All REPORTABLE OCCURRENCES submitted to the Commission.

c.

Records of surveillance activities, inspections and calibrations d.

required by these Technical Specifications.

Records of reactor tests and experiments.

e.

Records of changes made to Operating Procedures.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests h.

and results.

Records of annual physical inventory of all sealed source i.

material of record.

The following records shall be retained for the duration of the 6.10.2 Facility Operating License:

Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final a.

Safety Analysis Report.

Records of new and irradiated fuel inventory, fuel transfers b.

and assembly burnup histories.

t Records of facility radiation and contamination surveys.

c.

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ADMINISTRATIVE CONTROLS d.

Records of radiation exposure for all individuals entering radiation control areas.

e.

Records of gaseous and liquid radioactive material released to the environs.

f.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

g.

Records of training and qualification for current members of the plant staff.

h.

Records of in-service inspections perfomed pursuant to these Technical Specifications, i.

Records of Quality Assurance activities identified in the NRC approved QA Manual as lifteime records.

J.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the POSRC and the OSSRC.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

't 6.12 HIGHRADIATIOkAREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:

A high radiation area in which the intensity of radiation is a.

greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.

l CALVERT CLIFFS - UNIT 1 6-20 Amendment No. 27, (3

5.1 Responsibility The Plant Superintendent, Calvert Cliffs, has the direct responsibility to l

assure compliance with the specifications presented in Section 2.0.

The Chief Environmental Engineer, Electric Engineering Department, has th,e direct responsibility to assure compliance with the specific.uions presented in Sections 3.0 and 4.0.

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i Calvert Cliffs Unit 1 5.1-1 Amendment No. 43 Calvert Cliffs Unit 2 Amendment No. 26

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ELECT RIC TEST ELECTRIC ENGINEERING OUALITY ASSURANCE NUCLEAR POWER I

PLANT OPER ATIONS I

AND SAFETY REVIEW COMMITTEE CHIEF I

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AND TEST ENGINEER PLANT SUPERINTENDENT """j STAFF CALVERT CLIFFS

^b "1 a1 89 na Ob Nb FIGURE 5.2 - 1 MANAGEMENT ORGANIZATION CHART RELATING TC ENVIRONMENTAL MATTERS CALVERT CLIFFS NUCLE AR POWER PLANT BALTIMORE & G AS ELECTRIC COMPANY

5.4 Actions to be Taken if a Limiting Condition for Operation is Exceeded 5.4.1 Occurrences which exceed a limiting condition for operation shall be promptly reported to the Plant Superintendent, or his designated alternate, l

who, in turn shall report to the Chairman of the Off-Site Safety and Review Committee, or his designated alternate.

5.4.2 The Chairman, or his designated alternate, of the Off-Site Safety and

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it.w Committee shall promptly initiate a review of the occurrences and sub-sequently have a written report prepared. This report shall include an evalua-tion of the cause of the occurrence and recommendations for appropriate action to prevent or reduce the probability of a recurrence.

5.4.3 Copies of all such reports shall be submitted to the Chairman of the Off-Site Safety and Review Committee for review.

5.4.4 The Vice-President, Supply shall report all such occurrences to the NRC as specified in Section 5.6.2.a.

Calve-t Cliffs Unit i

.'-I Amendment No.43 Amendment No.26 Calvert Cliffs Unit 2

5.5 Operating Procedures Tha syste=s which,are directly involved with the fulfill:ent of the environ = ental taennical specifications shall be operated in accordance vith approved operating proce dure s.

5.5 1 On-Site Environ = ental Monitoring Progra=

All vritten operating procedures, and changes thereto, which pertain to specifica-tions in Section 2.0 shall be reviewed by a =e=ber of the plant staff and approved by the ?lant Superintendent prior to implementation, except as provided in the following paragraph:

Ts=porar/ changes to operating procedures which do not change the intent of the original procedure may be made provided such changes e.re approved by tvo licensed s2nior reactor operators, one of who= shall be the Shift Supervisor.

Such changes shal.1 be documented and subsequently reviewed by the Plant Operations and Safety R2viev Co==ittee and approved by the Plant Superintendent.

5.5 2 off-site Environ = ental Monitoring Progrs=s All vritten operating procedures and changes thereto, which pertain to specifica-tions in Sections 3.0 and h.0, shall be reviewed by the Inviron= ental Engineering Group, Electric Engineering Depart =ent and approved by the Chief Environ = ental Engineer prior to i=ple=entation, except as provided belov:

T =pora:7 changes to operating procedures vnich do =ot change the intent of the criginal procedure =ay be made provided such changes are app:-oved by the project 1soder as specified in the operating procedure.

Such changes shall be subsequently reviewed by the Environ = ental Engineering Group and approved by the Chief Environ-mental Engineer.

Amendment No. 43 Calvert Cliffs Unit 1 5.5-1 Calvert Cliffs Unit 2 Amendment No. 26

/

UNITED STATES NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D. C. 20555

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BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedJuly 24, 1979, as supplemented June 24, 1980, 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 I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comm-ission; 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 common 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachr.ent to this license amendment, and paragraph 2.C.2 of Facility Opertting License No. DPR-69 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 26, are hereby incorporated in the license.

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

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

FOR THE NUCLEAR REGULATORY C0ftMISSION h

Robert A. Clark, Chief Operating Reactors Branch f3 Division of Licensing

Attachment:

Changes to the

-Technical Specifications Date of Issuance: July 31, 1980

e AMENDMENT TO LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE NO. DRP-69 DOCKET NO. 50-318 Replace the following pages of the Appendix A and B Technical Specifications with the enclosed pages.

Tne revised pages are identified by Amendment number and contain vertical lines ir.dicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Appendix A Pages 6-1 6-2 6-3 6-6 6-7 6-8 6-9 6-12 6-13 6-14 6-20 Appendix B Pages 5.1-1 Figure 5.2-1 5.4-1 5.5-1 4

6.0 ADMINISlRATIVE CONTROLS 6.1 Resp 0NSIBILITY 6.1.1 The Plant Superintendent shall oe responsible for overall facility operation and shall delegate in writing the succession to t51s responsi-bility 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:

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, 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.

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 reguired for other essential functions.during a fire emergency.

CALVERT CLIFFS - UNIT 2 6-1

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  • 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 requirenents 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 J

i CALVERT CLIFFS - UNIT 2 6-5

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUAllFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiation Safety Engineer who shall meet or exceed the qualificati'ons l

of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training procram for the facility staff shall be maintained under the direction of the General Supervisor -

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Training and Technical Services and shall meet or sxceed the require ents and recomendations of Section 5.5 of ANSI NIS.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintr.ined ender the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code -

1975.

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

FUNCTION 6.5.1.1 The POSRC shall fun tion to advise the Plant Superintendent on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POSRC shall be composed of the:

Chaiman:

Plant Superintendent Member:

General Supervisor - Operations

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Member:

General Supervisor - Electrical and Controls Member:

General Supervisor - Chemistry Member:

Frincipal Engineer - Plant Engineering Nuclear Member:

General Foreman - Maintenance and Modifications Member:

Supervisor - Nuclear Fuel Management Member:

General Supervisor - Radiation Safety Member:

General Supervisor - Training and Technical Services 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 A:nendment No. JJ, 26 m.'

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ADMINISTRATIVE CONTR01.5 MEETTNG FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month and as convened by the POSRC Chairman or his designated alternate.

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

RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:

a.

Review of 1) all proceaures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect l

nuclear safety, b.

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

c.

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

d.

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

Investigation of all violations of the Technical Specifica-tions including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager - N0 clear Power Department and to the Chairman of the Off Site Safety Review Committee.

f.

Review all written reports requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

g.

Review of facility operations to detect potential safety hazards.

h.

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

i.

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

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Off Site Safety Review Committee.

l CALVERT CLIFFS - UNIT 2 6-7 AmendmentNo.77,/i,;

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ADMINISTRATIVE CONTROLS AUTHORITY s

6.5.1.7 The Plant Operations and Safety Review Committee shall:

a.

Recommend to th'e Plant Superintendent written approval or disap-l proval 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 questicn.

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 Manager -

Nuclear Power Department and the Off Site Safety Review Committee of disagreement between the POSRC and the Plant Superintendent; however, the Plant Superintendent 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 Manager - Nuclear Power Department J

and Chairman of the Off Site Safety Review Committee.

6.5.2 0FFSITESAFETYREVIEWCOMMITTEE10SSRC)

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 f

c.

chemistry and radiochemistry d.

metallurgy and non-destructive examination l

e.

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices CALVERT CLIFFS - UNIT 2 6-8 Amendment No. 26 I

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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 Supply Division or other BG5E organization or from organizations 2xternal to BGSE.

QUALIFICATIONS 6.5.2.3 The Chairman, members and alternate members of the OSSRC shall be. appointed in writing by the Vice President - Supply and shall have 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.

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1 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, No more than a minority meeting the requirements of Specification 6.5.2.3.

of the quorum shall have line responsibility for operation of the plant.

CALVERT CLIFFS - UNIT 2 6-9 Amendment No. 26 l

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ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The OSSRC shall review:

a.

The safety evaluations for 1) changes to procedures, equipment or 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 wnich involve an unreviewed safety question as defined in Section 50.59,10 CFR.

c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or this Operating License.

e.

Violations of codes, regulations, orders, Technical Specifications, 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 written reports requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

h.

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

i.

Reports and meetings minutes of the POSRC.

O CALVERT CLIFFS - UNIT 2 6-10

ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the OSSRC.

These audits shall encompass:

a.

The conformance of facility 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 the entire facility staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in 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 Qui.lity Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

The Facility Emergency Plan and implementing procedures at e.

least once per 24 months.

f.

The Facility Security Plan and ' implementing procedures at least once per 24 months.

g.

Any nther area of facility operation considered appropriate by the OSSRC or the Vice President-Supply.

h.

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

i.

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.

l

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

CALVERT CLIFFS - UNIT 2 6-11 Amendment No. 11

ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of OSSRC activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each OSSRC meeting shall be prepared, approved and forwarded to the Vice President-Supply within 14 days following each meeting.

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b.

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

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President-Supply and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Comission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Comission shall be reviewed by the POSRC and submitted to the OSSRC and the Manager - Nuclear Power Department.

l CALVERT CLIFFS - UNIT 2 6-12 Amendment No. 26 g

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

The facilty shall be placed in at least HOT STANDBY within a.

.ne hour.

b.

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

The Manager - Nuclear Power Department 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 c.

shall be reviewed by the POSRC.

This report shall describe (1) app-licable circumstances preceding the violation, (2) effects of the violation upon facility cogonents, systems or structures, and (3) corrective action taken to prevent recurrence.

The Safety Limit Violation Report shall be submitted to the Comission, d.

the OSSRC and the Manager - Nuclear Power Department within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be estab1ished, implemented and main-tained covering the activities referenced below:

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

Regulatory Guide 1.33, November,1972.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

Emergency Plan implementation.

e.

f.

Fire Protection Program 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 Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.

Amendment No. /[,26 CALVERT CLIFFS - UNIT 2 6-13

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

The intent of,the originial procedure is not altered.

a.

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 aooroved by c.

the Plant Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6. 9.1 In addition to the applicable r'eporting 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 sumary 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 pr <er level, (3) installation of fuel that has a different design or hat been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, tnermal, 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 i

of the operating conditions or characteristics obtained during the test l

program and a comparison of these values with design predictions and s peci fications. 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 comiitments shall be included in this report.

heendment No./[,26 CALVERT CLIFFS - UNIT 2 6-14

ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a.

Records and logs of facility operation covering time interval at each power level.

, b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE OCCURRENCES submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments, h.

Records of sealed source and fission detector leak tests and results.

1.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Records and drawing changes reflecting facility design modifi-l cations made to systems and equipment described in the Final Safety Analysis Report, b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

I c.

Records of facility radiation and contamination surveys.

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CALVERT CLIFFS - UNIT 2 6-19 Amendment No.14

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ADMINISTRATIVE CONTROLS.

d.

Records of radiation exposure for all individuals entering radiation control areas.

e.

Records of gaseous and liquid radioactive material released to the environs.

f.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

g.

Records of training and qualification for current members of the plant staff.

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h.

Records of in-service inspections performed pursuant to these Technicai Specifications, i.

Records of Quality Assurance activities identified in the NP.C approved QA Manual as lifetime records.

J.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the POSRC and the OSSRC.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:

a.

A high radiation area in which the intensity of radiation is greater than 100 mrem /hr but les? than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation

. monitoring device which continuously indicates the radiation dose rate in the area.

CALVERT CLIFFS - UNIT 2 6-20 Amendment No. JA,26

5.1 Responsibility Calvert Cliffs, has the direct responsibility to The Plant Superintendent, assure compliance with the specifications presented in Section 2.0.

The Chief Environmental Engineer, Electric Engineering Department, has the direct responsibility to assure compliance with the specifications presented in Sections 3.0 and 4.0.

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Calvert Cliffs Unit 1 5.1-1

. Amendment No.43 Calvert Cliffs Unit 2 Amendment No. 26

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o 5.4 Actions to be Taken if a Limiting Condition for Operation is Exceeded 5.4.1 Occurrences which exceed a limiting condition for operation shall be promptly reported to the Plant Superintendent, or his designated alternate, l

who, in turn shall report to the Chairman of the Off-Site Safety and Review Committee, or his designated alternate.

5.4.2 The Chairman, or his designated alternate, of the Off-Site Safety and Review Committee shall promptly initiate a ieview of the occurrences and sub-sequently have a written report prepared. This report shall include an evalua-tion of the cause of the occurrence and recommendations for appropriate action to prevent or reduce the probability of a recurrence.

5.4.3 Copies of all such reports shall be submitted to the Chairman of the Off-Site Safety and Review Committee for review.

5.4.4 The Vice-President, Supply shall report all such occurrences to the NRC as specified in Section 5.6.2.a.

1 Calvert Cliffs Unit 1 5.4-1 Amendment No. 43 Calvert Cliffs Unit 2 Amendment No. 26 e,

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5.5 Operating Procedures The syste=s which are directly involved with the fulfillnent of the environmental tochnical specifications shall be operated in accordance with approved operating procedures.

5.5 1 on4ite Environmental Monitoring Program All vritten operating procedures, and changes thereto, which pertain to specifica-tiens in Section 2.0 shall be reviewed by a member of the plant staff and approved by the Plant Superintendent prior to implementation, except as provided in the following paraEraph:

Ta=porary changes to operating procedures which do not change the intent of the original procedure may be made provided such changes are approved by two licensed s::nior reactor operators, one of whom shall be the Shift Supervisor.

Such changes shall be documented and subsequently reviewed by the plant Operations and Safety R2 view Com=ittee and approved by the Plant Superintendent.

5.5 2 Off-Site Environmental Monitoring Programs All vritten operating procedures and changes thereto, which pertain to specifica-tions in Sections 3 0 and h.0, shall be reviewed by the Envires= ental Engineering Group. Electric Engineering Department and approved by the Chief Environ = ental Ihgineer prior to imple=entation, except as provided belev:

Tsmporary changes to operating procedures which do not change the intent of the original procedure may be made provided such changes are approved by the project lander as specified in the operating procedure.

Such changes shall be subsequently rcviewed by the Environmental Engineering Group and approved by the Chief Environ-nental Engineer.

Calvert Cliffs Unit 1 5.5-1 Amendment No.43 Calvert Cliffs Unit 2 Anendment No.26 l

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