ML20129D691

Amends 217 & 194 to Licenses DPR-53 & DPR-69,respectively, Implementing Changes to RETS IAW GL 89-01, Implementation of Programmatic for Radiological Effluent TS in Admin Controls Section of TSs & Relocation of Procedural..

ML20129D691
Person / Time
Site:	Calvert Cliffs
Issue date:	10/18/1996
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20129D157	List: ML20129D151 ML20129D691
References
GL-89-01, GL-89-1, NUDOCS 9610250108
Download: ML20129D691 (74)

Text

.-. -

gW4g p

4 UNITED STATES g

,g NUCLEAR REGULATORY COMMISSION o

e WASHINGTON. D.C. 2055fM1001

%[

BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 License No. DPR-53 i

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

1.

a A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 9,1995, as supplemented September 4,1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rulee and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 4

Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; 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 to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated June 9, 1995, as supplemented by letter dated September 4,1996, and reviewed in the staff's safety evaluation report dated October 18, 1996. This license is also hereby amended by page 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:

9610250108 961018 PDR ADOCK 05000317 P

PDR

2 2.

Technical Soecifications The Technical Specificatiors contained in Appendix A, as revised through Amendment No.217, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the licease.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days from the date of issuance.

Implementation shall include relocation of Technical Specification requirements to the appropriate licensee-controlled document as identified in the licensee's application dated June 9,1995, as supplemented September 4, 1996, and reviewed in the staff's safety evaluation report dated October 18, 1996.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 18, 1996

_m MUhg pt

[*

4 UNITED STATES j

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20$254001 49.....,o BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 194 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 9, 1995, as supplemented September 4, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter 1; 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 to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated June 9, 1995, as supplemented by letter dated September 4, 1996 and reviewed in the staff's safety evaluation report dated October 18, 1996. This license is also hereby amended by page changes to tLe 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:

?

l l 2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through i

Amendment No.194, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

t 3.

This license amendment is effective as of the date of its issuance and j

shall be implemented within 60 days from the date of issuance.

Implementation shall include relocation of Technical Specification requirements to the appropriate licensee-controlled document as identified in the licensee's application dated June 9,1995, as supplemented J

September 4,1996, and reviewed in the staff's safety evaluation report dated October 18, 1996.

,P FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director I

Project Directorate I-l Division of Reactor Projects - I/II 4

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 18, 1996 i

d I

4 9

l

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 217 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NOS. 50-317 Revise Appendix A as follows:

Remove Paaes Insert Paaes I

I IV IV V through VII V through VII VIII and IX VIII X through XII IX through XI XIII and XIV XII XV XIII XVI XIV 1-4 through 1-8 1-4 through 1-8 3/4 3-43 through 3/4 3-52 3/4 3-43 3/4 11-1 through 3/4 11-19 3/4 11-1 and 3/4 11-2 3/4 12-1 through 3/4 12-15 3/4 12-1 B 3/4 3-3 B 3/4 3-3 B 3/4 11-1 through B 3/4 11-6 8 3/4 11-1 B 3/4 12-1 and B 3/4 12-2 B 3/4 12-1 6-6 through 6-9 6-6 through 6-10 6-11 through 6-14 6-11 through 6-15

TABLE OF CONTENTS DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Defined Terms....................

1-1 Action 1-1 Axi al Shape Index..................

1-1 Azimathal Power Tilt - T,..............

1-1 Channel Calibration.................

1-1 Channel Check....................

1-2 Channel Functional Test...............

1-2 Containment Integrity................

1-2 Controlled Leakage 1-3 Core Alteration...................

1-3 Core Operating Limits Report (COLR).........

1-3 Dose Equivalent I-131................

1-3 E-Average Disintegration Energy...........

1-3 Engineered Safety Feature Response Time.......

1-3 Frequency Notation 1-4 Gaseous Radwaste Treatment System..........

1-4 Identified Leakage 1-4 Member (s) Of The Public...............

1-4 Offsite Dose Calculation Manual (ODCM) 1-4 Operable - Operability 1-5 Operational Mode 1-5 Physics Tests....................

1-5 Pressure Boundary Leakage..............

1-5 Purge-Purging....................

1-5 Rated Thermal Power.................

1-6 Reactor Trip System Response Time..........

1-6 Reportable Event 1-6 Shutdown Margin...................

1-6 Site Boundary....................

1-6 Source Check 1-6 Staggered Test Basis 1-6 Thermal Powe r....................

1-7 Total Integrated Radial Peaking Factor - P,.....

1-7 Total Planar Radial Peaking Factor - FI,.......

1-7 Unidentified Leakage 1-7 Unrestricted Area..................

1-7 Ventilation Exhaust Treatment System 1-7 Venting.......................

1-8 CALVERT CLIFFS - UNIT 1 I

Amendment No. 217

t TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION...................

3/4 3-9 4

3/4.3.3 MONITORING INSTRUMENTATION i

Radiation Monitoring Instrumentation 3/4 3-23 Meteorological Instrumentation 3/4 3-27 1

Remote Shutdown Instrumentation...........

3/4 3-30 4

Post-Accident Instrumentation............

3/4 3-33 Fire Detection Instrumentation 3/4 3-37 l

\\

i 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP And POWER OPERATION.............

3/4 4-1 HOT STANDBY.....................

3/4 4-2 Shutdown 3/4 4-4 3/4.4.2 SAFETY VALVES....................

3/4 4-6 3/4.4.3 RELIEF VALVES....................

3/4 4-7 l

3/4.4.4 PRESSURIZER.....................

3/4 4-9 3/4.4.5 STEAM GENERATORS 3/4 4-10 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..............

3/4 4-17 Reactor Coolant System Leakage 3/4 4-19 3/4.4.7 CHEMISTRY......................

3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY..................

3/4 4-24 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-28 Pressurizer.....................

3/4 4-32 Overpressure Protection Systems...........

3/4 4-33 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 And 3 Components........

3/4 4-37 CALVERT CLIFFS - UNIT 1 IV Amendment No. 217

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.11 CORE BARREL MOVEMENT 3/4 4-39 3/4.4.12 LETDOWN LINE EXCESS FLOW 3/4 4-41 3/4.4.13 REACTOR COOLANT SYSTEM VENTS 3/4 4-42 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - MODES 1, 2 and 3 (> 1750 PSIA) 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - MODES 3 (< 1750 PSIA) and 4....

3/4 5-7 3/4 5.4 REFUELING WATER TANK 3/4 5-8 3/4.6 CONTAINMCNT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY................

3/4 6-1 Containment Leakage.................

3/4 6-2 Containment Air Locks................

3/4 6-5 Internal Pressure..................

3/4 6-7 Air Temperature...................

3/4 6-8 Containment Structural Integrity 3/4 6-9 Containment Purge System 3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System 3/4 6-16 Containment Cooling System 3/4 6-18 3/4.6.3 IODINE REMOVAL SYSTEM................

3/4 6-20 3/4.6.4 CONTAINMENT ISOLATION VALVES 3/4 6-23 3/4.6.5 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers 3/4 6-25 Electric Hydrogen Recombiners - W..........

3/4 6-26 3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM 3/4 6-27 I

CALVERT CLIFFS - UNIT 1 V

Amendment No. 217 l

m TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 4

3/4.7.1 TURBINE CYCLE 4

Safety Valves....................

3/4 7-1 Auxiliary Feedwater System 3/4 7-5 l

Condensate Storage Tank...............

3/4 7-8 Activity 3/4 7-9 Main Steam Line Isolation Valves 3/4 7-11 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...

3/4 7-12 l

3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4 7-13 3/4.7.4 SERVICE WATER SYSTEM 3/4 7-14 3/4.7.5 SALTWATER SYSTEM 3/4 7-15 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM......

3/4 7-16 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM 3/4 7-20 3/4.7.8 SNUBBERS 3/4 7-23 i

3/4.7.9 SEALED SOURCE CONTAMINATION.............

3/4 7-30 l

3/4.7.10 WATERTIGHT 000RS 3/4 7-32 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............

3/4 7-33 Spray and/or Sprinkler Systems 3/4 7-37 l

Halon System 3/4 7-40 Fire Hose Stations 3/4 7-42 Yard Fire Hydrants and Hydrant Hose Houses 3/4 7-45 1

1 3/4.7.12 PENETRATION FIRE BARRIERS..............

3/4 7-47 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating......................

3/4 8-1 Shutdown 3/4 8-6 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating............

3/4 8-9 A.C. Distribution - Shutdown 3/4 8-11 D.C. Distribution - Operating............

3/4 8-13 D.C. Distribution - Shutdown 3/4 8-17 CALVERT CLIFFS - UNIT 1 VI Amendment No. 217 l

]

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE i

J 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................

3/4 9-1 3/4.9.2 INSTRUMENTATION...................

3/4 9-2 l

3/4.9.3 DECAY TIME 3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS 3/4 9-4 3/4.9.5 COMMUNICATIONS 3/4 9-6 l

3/4.9.6 REFUELING MACHINE OPERABILITY............

3/4 9-7 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING...

3/4 9-9 j

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION 3/4 9-10 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM 3/4 9-12 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-13 J

3/4.9.11 SPENT FUEL P0OL WATER LEVEL.............

3/4 9-14 j

3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM 3/4 9-15 3/4.9.13 SPENT FUEL CASK HANDLING CRANE 3/4 9-18 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES..........

3/4 9-19 1

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...................

3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS............

3/4 10-2 3/4.10.3 NO FLOW TESTS....................

3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT...............

3/4 10-4 3/4.10.5 COOLANT CIRCULATION.................

3/4 10-5 CALVERT CLIFFS - UNIT 1 VII Amendment No. 217 l

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASE0US EFFLUENTS Explosive Gas Mixture................

3/4 11-1 Gas Storage Tanks..................

3/4 11-2 3/4.12

[ DELETED]......................

3/4 12-1 l

CALVERT CLIFFS - UNIT 1 VIII Amendment No. 217 i

I

TABLE OF CONTENTS BASES SECTION PAGE 3/4.0 APPLICABILITY.................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL B 3/4 1-1 2

3/4.1.2 B0 RATION SYSTEMS B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-3 3/4.2 POWER DISTRIBllTION LIMITS 3/4.2.1 LINEAR HEAT RATE B 3/4 2-1 l

3/4.2.2, 3/4.2.3, and 3/4.2.4 TOTAL PLANAR AND I

INTEGRATED RADIAL PEAKING FACTORS - FJ,AND F; AND AZIMUTHAL POWER TILT - T, B 3/4 2-1 3/4.2.5 DNB PARAMETERS B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY i

FEATURES (ESF) INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION........ B 3/4 4-1 3/4.4.2 SAFETY VALVES.................... B 3/4 4-1

]

3/4.4.3 RELIEF VALVES.................... B 3/4 4-2 3/4.4.4 PRESSURIZER..................... B 3/4 4-3 1

3/4.4.5 STEAM GENERATORS B 3/4 4-3 4

1 CALVERT CLIFFS - UNIT 1 IX Amendment No. 217 l

TABLE OF CONTENTS BASES SECTION PAGE 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-5 l

3/4.4.7 CHEMISTRY...................... B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY.................. B 3/4 4-6 3.4.4.9 PRESSURE / TEMPERATURE LIMITS............. B 3/4 4-7 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-11 1

3/4.4.11 CORE BARREL MOVEMENT B 3/4 4-11 3/4.4.12 LETDOWN LINE EXCESS FLOW B 3/4 4-12 3/4.4.13 REACTOR COOLANT SYSTEM VENTS B 3/4 4-12 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEhS B 3/4 5-1 3/4.5.4 REFUELINGWATERTANK(RWT)

B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT................. B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS B 3/4 6-3 3/4.6.3 IODINE REMOVAL SYSTEM................ B 3/4 6-3 3/4.6.4 CONTAINMENT ISOLATION VALVES B 3/4 6-3 3/4.6.5 C0KEUSTIBLE GAS CONTROL............... B 3/4 6-4 3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM B 3/4 6-4 CALVERT CLIFFS - UNIT 1 X

Amendment No. 217 l

. -. _ =. -. - - -.

o i

4 TABLE OF CONTENTS 1

j BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION... B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM B 3/4 7-3 1

j 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-3 2

3/4.7.5 SALTWATER SYSTEM B 3/4 7-4 i

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...... B 3/4 7-4 l

3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM B 3/4 7-4 3/4.7.8 SNUBBERS B 3/4 7-4 l

3/4.7.9 SEALED SOURCE CONTAMINATION............. B 3/4 7-6 j

3/4.7.10 WATERTIGHT D0 ORS B 3/4 7-6 3/4.7.11 FIRE SUPPRESSION SYSTEMS B 3/4 7-6 3/4.7.12 PENETRATION FIRE BARRIERS.............. B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 1

3/4.9 REFUELING OPERATIONS 3

4 3/4.9.1 BORON CONCENTRATION................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION................... B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 REFUELING MACHINE OPERABILITY............ B 3/4 9-2 CALVERT CLIFFS - UNIT 1 XI Amendment No. 217 l

C TABLE OF CONTENTS BASES 9

SECTION PAGE 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING..... B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION

...... B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM...... B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL P00L WATER LEVEL........... B 3/4 9-3 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM......... B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE........... B 3/4 9-3 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES.......... B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS....................... B 3/4 10-1 3/4.10.3 NO FLOW TESTS.................... B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT............... B 3/4 10-1 3/4.10.5 COOLANT CIRCULATION................. B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 GASE0US EFFLUENTS.................. B 3/4 11-1 l

3/4.12

[ DELETED]...................... B 3/4 12-1 CALVERT CLIFFS - UNIT 1 XII Amendment No. 217

TABLE OF CONTENTS DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION....................

5-1

)

5.2 REACTOR CORE 5.2.1 Fuel As s embl i es...................

5-1 5.2.2 Control Element Assemblies 5-1 5.3 FUEL STORAGE 5.3.1 Criticality.....................

5-1 5.3.2 Drainage 5-2 5.3.3 Capacity 5-2 CALVERT CLIFFS - UNIT 1 XIII Amendment No. 217 l

1 TABLE OF CONTENTS ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 1

6.2 ORGANIZATION 6.2.1 Onsite & Offsite Organizations 6-1 6.2.2 Unit Staff 6-1 I

6.3 FACILITY STAFF QUALIFICATIONS............

6-3 1

1 l

6.4 PROCEDURES 6-3 6.5 PROGRA'45 AND MANUALS

]

6.5.1 Offsite Dose Calculation Manual (0DCM) 6-4 6.5.2 Post-Accident Sampling 6-5 6.5.3 Primary Coolant Sources Outside Containment.....

6-5 6.5.4 Technical Specification Bases Control Program....

6-5 l

6.5.5 Radioactive Effluent Controls Program........

6-6 6.5.6 Containment Leakage Rate Testing Program 6-8 l

6.6 REPORTING REQUIREMENTS 6.6.1 Occupational Radiation Exposure Report 6-9 l

6.6.2 Annual Radiological Environmental Operating Report 6-9 l

6.6.3 Radioactive Effluent Release Report.........

6-10 l

6.6.4 Monthly Operating Report 6-10 l

6.6.5 Core Operating Limits Report (COLR).........

6-11 l

J 6.6.6 Pressurizer PORV and Safety Valve Report 6-15 l

1 1

l CALVERT CLIFFS - UNIT 1 XIV Amendment No. 217

1.0 DEFINITIONS FREQUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

GASEOUS RADWASTE TREATMENT SYSTEM 1.16 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluent by collecting Primary Coolant System offgases from the Primary System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.17 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to the Secondary System.

MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain the radioactive effluent controls, radiological environmental monitoring activities, and descriptions of the information CALVERT CLIFFS - UNIT 1 1-4 Amendment No. 217

1.0 DEFINITIONS that should be included in the Annual Radiological Environmental Operating j

Report and Radioactive Effluent Release Report, required by Specifications i

6.6.2 and 6.6.3, respectively.

OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of perfonning its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE 1.21 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

l PURGE - PURGING 1.24 PURGE or PURGING is the controlled process of discharging air or gas l

from a confinement to maintain temperature, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

CALVERT CLIFFS - UNIT 1 1-5 Amendment No. 217

1.0 DEFINITIONS RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate l

to the reactor coolant of 2700 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l

when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT a

1.27 A REPORTABLE EVENT shall be any of those conditions specified in l

Section 50.73 to 10 CFR Part 50.

SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by l

which the reactor is subtritical or would be subcritical from its present condition assuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.

I I

SITE B0UNDARY 1.29 The SITE B0UNDARY shall be that line beyond which the land is neither l

owned, nor leased, nor otherwise controlled by the licensee.

l SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel l

response when the channel sensor is exposed to a source of increased radioactivity.

l STAGGERED TEST BASIS 1.31 A STAGGERED TEST BASIS shall consist of:

l a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and 3

b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

CALVERT CLIFFS - UNIT 1 1-6 Amendment No. 217

_. - = -

1.0 DEFINITIONS i

THERMAL P0WER 1.32 THERMAL POWER shall be the total reactor core heat transfer rate to l

the reactor coolant.

)

TOTAL INTEGRATED RADIAL PEAKING FACTOR - F.

1.33 The TOTAL INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak l

pin power to the average pin power in an unrodded core.

1 TOTAL PLANAR RADIAL PEAKING FACTOR - FI, i

1.34 The TOTAL PLANAR RADIAL PEAKING FACTOR is the maximum ratio of the l

i peak to average power density of the individual fuel rods in any of the unrodded horizontal planes.

UNIDENTIFIED LEAKAGE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED l

LEAKAGE or CONTROLLED LEAKAGE.

l UNRESTRICTED AREA 1.36 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY l

access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE B0UNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

j VENTILATION EXHAUST TREATMENT SYSTEM i

1.37 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and l

installed to reduce gaseous radiciodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing t

j iodines or particulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluent.

Engineered Safety Feature (ESF) Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

i i

CALVERT CLIFFS - UNIT 1 1-7 Amendment No. 217

I 1.0 DEFINITIONS

\\

VENTING 1.38 VENTING is the controlled process of discharging air or gas from a l

confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is 1

not provided or required during VENTING. Vent, used in system names, does l

not imply a VENTING process.

i l

j CALVERT CLIFFS - UNIT 1 1-8 Amendment No. 217

o 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION

[ Technical Specifications 3/4.3.3.9 and 3/4.3.3.10 have been deleted.]

CALVERT CLIFFS - UNIT 1 3/4 3-43 Amendment No. 217

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASEOUS EFFLUENTS l

Explosive Gas Mixture (Hydrogen rich systems not desi withstand a hydrogen explosion)gned to LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of oxygen in the Waste Gas Holdup System shall l

be limited to less than or equal to 4% by volume.

]

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in a waste gas decay tank greater than 4% by volume immediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen j

to less than or equal to 4% by volume without delay.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

4 l

SURVEILLANCE REQUIREMENTS 4.11.1.1 The concentration of oxygen in the Waste Gas Holdup System shall be determined to be within the above limit by collecting and analyzing a sample from the Waste Gas Decay Tank once per week on the in-service tank and following tank isolation. Waste Gas Surge Tank samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other times.

CALVERT CLIFFS - UNIT 1 3/4 11-1 Amendment No. 217

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASEOUS EFFLUENTS l

Gas Storace Tanks LIMITING CONDITION FOR OPERATION 3.11.1.2 The quantity of radioactivity contained in each gas storage tank l

shall be limited to less than or equal to 58,500 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank r,xceeding the above limit, innediately suspend all additions of radioactive material to that tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 The quantity of radicactive material contained in the in-service I

gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Coolant System specific activity of Xe-133 is greater than 150 pCi/ml.

CALVERT CLIFFS - UNIT 1 3/4 11-2 Amendment No. 217

. = _ _ _ _ _ _ _.

a 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

[ Technical Specification Section 3/4.12 has been deleted.]

l i

)

1 I

CALVERT CLIFFS - UNIT 1 3/4 12-1 Amendment No. 217 1

4

,m.-

o 3/4.3 INSTRUMENTATION BASES In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during an extended COLD SHUTDOWN.

This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved.

If only one channel is inoperable, it should be restored to OPERABLE status in accordance with the schedule outlined in a Special Report.

If both channels are inoperable, the system shall be restored to OPERABLE status in the next refueling outage.

3/4.3.3.7 Fire Detection Instrumentation OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

I i

i l

i i

s a

1 4

t CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 217

3/4.11 RADI0 ACTIVE EFFLUENTS BASES i

i 3/4.11.1 GASE0US EFFLUENTS l

3/4.11.1.1 Explosive Gas Mixture l

This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System is maintained below the flammability limit of oxygen. Maintaining the concentration of oxygen below its flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 60.

3/4.11.1.2 Gas Storace Tanks l

The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the quantity that provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 10 CFR Part 100 limits.

Restricting the quantity of radioactivity contained in each gas storage J,

tank provides assurance that in the event of an uncontrolled release of the 4

tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed accident guidelines.

i 4

i i

j CALVERT CLIFFS - UNIT 1 B 3/4 11-1 Amendment No. 217

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING c

BASES

[ Technical Specifications Section 3/4.12, and the associated Bases, have been deleted.]

l

)

l CALVERT CLIFFS - UNIT 1 B 3/4 12-1 Amendment No. 217 J

e 6.0 ADMINISTRATIVE CONTROLS c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR, a

d.

Proposed changes to the Technical Specifications incorporated in the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question shall be reviewed and approved by the NRC prior to implementation. Changes to the i

Bases implemented without prior NRC approval shall be j

the NRC on a frequency consistent with 10 CFR 50.71(e)provided to 6.5.5 Radioactive Effluent Controls Prooram i

This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from l

radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

l a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and setpoint determination, in accordance with the l

methodology in the ODCM; b.

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to l

10 CFR Part 20, Appendix B, Table II, Column 2; c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents, in accordance with 10 CFR 20.1302, and with the methodology and parameters in the ODCM; 3

d.

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS to be limited:

1.

During any calendar quarter: Less than or equal to 3 mrems to the total body, and to less than or equal to 10 mrems to any organ; and 4

i 2.

During any calendar year:

Less than or equal to 6 mrems to the total body, and to less than or equal to 20 mrems to any j

organ; I

e.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, in accordance with the methodology and s

parameters in the ODCM, at least every 31 days; CALVERT CLIFFS - UNIT 1 6-6 Amendment No. 217 1

1 6.0 ADMINISTRATIVE CONTROLS f.

Limitations on the functional capability and use of the Liquid i

Radwaste Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body, or 1.20 mrem to any organ in a 92-day period; g.

Limitations on the functional capability and use of the Gaseous a

Radwaste Treatment System and the Ventilation Exhaust Treatment System to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the calculated doses to UNRESTRICTED AREAS exceeds 1.20 mrad for gama radiation, and 2.40 mrad for beta radiation in a 92-day period; l

h.

Limitations on the functional capability and use of the Ventilation Exhaust Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the calculated doses due to gaseous releases to UNRESTRICTED AREAS exceeds 1.8 mrem to any organ in a 92-day period; i.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE B0UNDARY, to be limited:

l 1.

For noble gases:

Less than or equal to 500 mrems/yr to the total body, and less than or equal to 3000 mrems/yr to the skin; and 2.

For Iodine-131 and for all radionuclides in particulate form with half lives greater than 8 days:

Less than or equal to 1500 mrems/yr to any organ; j.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:

1 1.

During any calendar quarter:

Less than or equal to 10 mrads for gama radiation, and less than or equal to 20 mrads for beta radiation; and 2.

During any calendar year:

Less than or equal to 20 mrads for gama radiation, and less than or equal to 40 mrads for beta radiation; i

1 CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 217

6.0 ADMINISTRATIVE CONTROLS k.

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to areas beyond the SITE B0UNDARY, to be limited:

i 1.

During any calendar quarter:

Less than or equal to 15 mrems i

to any organ; 2.

During any calendar year:

Less than or equal to 30 mrems to e

any organ; and 3.

Less than 0.1% of the limits of 6.5.5.k(1) and (2) as a result of burning contaminated oil; and I

1.

Limitations on the annual dose or dose commitment to any MEMBER

)

0F THE PUBLIC due to releases of radioactivity, and to radiation from uranium fuel cycle sources to be limited to less than or j

equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

6.5.6 Containment Leakage Rate Testing Program l

A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, i

" Performance-Based Containment Leak-Test Program," dated September 1995, as modified by approved exceptions.

1 The peak calculated containment internal pressure for the design basis loss-of-coolant accident, P, is 49.4 psig. The containment design pressure is 50 psig.

The maximum allowable containment leakage rate, L., shall be 0.20 percent of containment air weight per day at P,.

Containment leakage rate acceptance criterion is 51.0 L.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria is 5 0.75 L, for Type A tests.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

CALVERT CLIFFS - UNIT 1 6-8 Amendment No. 217

a O

6.0 ADMINISTRATIVE CONTROLS 6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.

6.6.1 Occupational Radiation Exposure Report

• A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignment to various duty functions may be estimates based on pocket dosimeter, electronic personal dosimeter or thermoluminescent dosimeter. Small exposures totallir.g < 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. The report shall be submitted prior to March 31 of each year.

6.6.2 Annual Radioloaical Environmental Operatino Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include suninaries, l

interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the ODCM, and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C.

The Annual Radiological Environmental Operating Report shall include the l

results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the 00CM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1 November 1979. The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program, and the exposure period associated with each result.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

A single submittal may be made for Calvert Cliffs. The submittal should combine those sections that are common to both units.

Occupational dose from the Independent Spent Fuel Storage Installation will be reported separately.

CALVERT CLIFFS - UNIT 1 6-9 Amendment No. 217

l 6.0 ADMINISTRATIVE CONTROLS 6.6.3 Radioactive Effluent Release Report

• The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a (i.e.,,* time between submittal of the reports must be no longer than 12 months)

The report l

shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units.

The material provided i

shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous and solid) shall be reported to the Comission in the Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:

1 l

a.

A description of the equipment, components and processes involved; and b.

Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the onsite review function.

The report shall also include changes to the ODCM, in accordance with Specification 6.5.1.c.

6.6.4 Monthly Operatino Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis, no later than the 15th of each month following the calendar month covered by the report.

A single submittal may be made for Calvert Cliffs, since the Radwaste Systems are comon to both units.

In lieu of submission with the Radioactive Effluent Release Report, Sr" and Sr" analyses results may be submitted in a supplementary report within 120 days after submittal of the Radioactive Effluent Release Report.

CALVERT CLIFFS - UNIT 1 6-10 Amendment No. 217

6.0 ADMINISTRATIVE CONTROLS 6.6.5 Core Operatino Limits Report (COLR) a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a triad cycle, and shall be documented in the COLR for the followi.. '

2.2.1 3.1.1.1 3.1.1.2 3.1.1.4 3.1.3.1 3.1.3.6 3.2.1 t

3.2.2.1 3.2.3 3.2.5 l

3.9.1 b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC; specifically, those described in the following documents:

l (1) CENPD-199-P, Latest Approved Revision, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LC0 Setpoint Methodology for Analog Protection Systems,"

January 1986 (2) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II," December 1979 (3) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2," January 1980 (4) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (5) CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 (6)

Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr.

(BG&E),datedJune 24,1982, Unit 1 Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER)

CALVERT CLIFFS - UNIT 1 6-11 Amendment No. 217 l

d 6.0 ADMINISTRATIVE CONTROLS (7) CEN-348(B)-P, " Extended Statistical Combination of Uncertainties," January 1987 j

(8) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD-161-P-A, " TORC Code, A Computer Code for Detemining the Thermal Margin of a Reactor Core," April 1986 (10) CENPD-162-P-A, Latest Approved Revision, " Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1 Unifom Axial Power Distribution" (11) CENPD-207-P-A, Latest Approved Revision, " Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-Uniform Axial Power Distribution" (12) CENPD-206-P-A, Latest Approved Revision, " TORC Code, Verification and Simplified Modeling Methods" (13) CENPD-225-P-A, Latest Approved Revision, " Fuel and Poison Rod Bowing" (14) CENPD-266-P-A, Latest Approved Revision, "The ROCS and DIT Computer Code for Nuclear Design" (15)CENPD-275-P-A,LatestApprovedRevision,"C-EMethodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers" (16) CENPD-382-P-A, Latest Approved Revision, "C-E Methodology for Core Designs Containing Erbium Burnable Absorbers" (17) CENPD-139-P-A, Latest Approved Revision, "C-E Fuel Evaluation Model Topical Report" (18) CEN-161-(B)-P-A, Latest Approved Revision, " Improvements to Fuel Evaluation Model" (19) CEN-161-(B)-P, Supplement 1-P, " Improvements to Fuel Evaluation Model," April 1989 (20) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (21) CEN-372-P-A, Latest Approved Revision, " Fuel Rod Maximum Allowable Gas Pressure" CALVERT CLIFFS - UNIT 1 6-12 Amendment No. 217 l

l' 6.0 ADMINISTRATIVE CONTROLS 1

(22) Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC), dated December 15, 1981, LD-81-095, Enclosure 1-P, i

"C-E ECCS Evaluation Model Flow Blockage Analysis" (23) CENPD-132, Supplement 3-P-A, Latest Approved Revision, j

" Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS" (24) CENPD-133 Supplement 5. "CEFLASH-4A, a FORTRAN 77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 j

(25) CENPD-134, Supplement 2, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 1985 (26) Letter from Mr. D. M. Crutchfi. eld (NRC) to Mr. A. E. Scherer i

(CE),datedJuly 31, 1986, " Safety Evaluation of Combustion i

Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports" t

(27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical i

Geometry Fuel Rod Heat Transfer Program," April 1977 t

(28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE),

l dated September 6,1978, " Evaluation of Topical Report j

CENPD-135, Supplement 5" k

(29) CENPD-137, Supplement'l-P, " Calculative ~ Methods for the C-E i

Small Break LOCA Evaluation Model," January 1977 (30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, A Computer Program-i for the Reactor Blowdown Analysis of the Small Break Loss of j

Coolant Accident," January 1977 l

(31) Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE),

j dated September 27,1977, " Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P"

}

(32) CENPD-138, Supplement 2-P, " PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 4

(33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated April 10,1978, " Evaluation of Topical Report CENPD-138, 1

Supplement 2-P" l

(34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert i

Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, 1

Amendment to Operating License DPR-53, Eighth Cycle License Application"

[

CALVERT CLIFFS - UNIT 1 6-13 Amendment No. 217 l

I

.- _~

6.0 ADMINISTRATIVE CONTROLS (35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr.

(BG&E), dated May 20, 1985, " Safety Evaluation Report Approving Unit 1 Cycle 8 License Ap lication" (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, " Amendment to Operating License No. 50-317, Fifth Cycle License Application" (37) Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr.

(BG&E), dated December 12,1980, " Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38) Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1,1986, "Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2, Docket Nos. 50-317 & 50-318, Request for Amendment" (39) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7,1987, Docket Nos. 50-317 and 50-318 Approval of Amendments 127 (Unit 1) and 109 (Unit 2)

(40) CENPD-188-A, Latest Approved Revision, "HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients" (41) The Full Core Power Distribution Monitoring System i

referenced in Specifications 3.1.3.1, 3.2.2.1, 3.2.3, and the BASES is described in the following documents:

(a)

CENPD-153-P, Latest Approved Revision, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by i

the Self-Powered, Fixed Incore Detector System" (b)

CEN-199(B)-P,"BASSS,UseoftheIncoreDetectorSystem i

to Monitor the DNB-LC0 on Calvert Cliffs Unit I and Unit 2," November 1979 (c)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit Nc. 2; Docket 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" (d)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42) Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, " Approval to Use Convolution Technique in Main Steam Line Break Analysis -

Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898)

CALVERT CLIFFS - UNIT 1 6-14 Amendment No. 217 l

6.0 ADMINISTRATIVE CONTROLS c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

6.6.6 Pressurizer PORV and Safety Valve Report A report shall be submitted prior to March 1 of each year documenting all failures and challenges to the pressurizer PORVs or safety valves.

CALVERT CLIFFS - UNIT 1 6-15 Amendment No. 217 l

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 194 FACILITY OPERATING LICENSE NO. OPR-69 DOCKET NOS 50-318 Revise Appendix A as follows:

Remove Paaes Insert Paaes I

I IV IV V through VII V through VII VIII and IX VIII X through XII IX through XI XIII and XIV XII XV XIII XVI XIV 1-4 through 1-8 1-4 through 1-8 3/4 3-41 through 3/4 3-50 3/4 3-41 3/4 11-1 through 3/4 11-19 3/4 11-1 and 3/4 11-2 3/4 12-1 thre.Th 3/4 12-15 3/4 12-1 B 3/4 3-3 8 3/4 3-3 B 3/4 11-1 through B 3/4 11-5 B 3/4 11-1 B 3/4 12-1 and B 3/4 12-2 B 3/4 12-1 6-6 through 6 1 6-6 through 6-10 6-10 through 6-14 6-11 through 6-15

N i

j 3

TABLE OF CONTENTS j

DEFINITIONS SECTION PAGE 3

1.0 DEFINITIONS Defi ned Te rms...................

1-1 Action 1-1 Axial Shape Index.................

1-1 j

Azimuthal Power Tilt - T,.............

1-1 Channel Calibration................

1-1 Channel Check...................

1-2 l

Channel Functional Test..............

1-2 Containment Integrity...............

1-2 Controlled Leakage 1-3 j

Core Alteration..................

1-3 l

Core Operating Limits Report (COLR)........

1-3 Dose Equivalent I-131...............

1-3 E-Average Disintegration Energy..........

1-3 Engineered Safety Feature Response Time......

1-3 frequency Notation 1-4 Gaseous Radwaste Treatment System.........

1-4 Identified Leakage 1-4 Member (s) of the Public..............

1-4 Offsite Dose Calculation Manual (0DCM) 1-4 Operable - Operability 1-5 Operational Mode 1-5 j

Physics Tests...................

1-5 Pressure Boundary Leakage.............

1-5 i

Purge-Purging...................

1-5 Rated Thermal Power................

1-6 Reactor Trip System Response Time.........

1-6 Reportable Event 1-6 l

Shutdown Margin..................

1-6 Site Boundary...................

1-6 l

Source Check 1-6 Staggered Test Basis 1-6 The rmal Power...................

1-7 Total Integrated Radial Peaking Factor - F;....

1-7 Total Planar Radial Peaking Factor - 6[,......

1-7 Unidentified Leakage 1-7 i

Unrestricted Area.................

1-7 Ventilation Exhaust Treatment System 1-7 Venting......................

1-8 i

i a

CALVERT CLIFFS - UNIT 2 I

Amendment No. 194

s TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..................

3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 Meteorological Instrumentation 3/4 3-27 Remote Shutdown Instrumentation..........

3/4 3-30 Post-Accident Instrumentation...........

3/4 3-33 Fire Detection Instrumentation 3/4 3-37 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP and POWER OPERATION............

3/4 4-1 HOT STANDBY....................

3/4 4-2 Shutdown 3/4 4-4 3/4.4.2 SAFETY VALVES...................

3/4 4-6 3/4.4.3 RELIEF VALVES...................

3/4 4-7 3/4.4.4 PRESSURIZER....................

3/4 4-9 3/4.4.5 STEAM GENERATORS 3/4 4-10 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............

3/4 4-17 Reactor Coolant System Leakage 3/4 4-19 3/4.4.7 CHEMISTRY.....................

3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY.................

3/4 4-24 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-28 Pressurizer....................

3/4 4-32 Overpressure Protection Systems..........

3/4 4-33 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components.......

3/4 4-37 CALVERT CLIFFS - UNIT 2 IV Amendment No. 194

J.

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.11 CORE BARREL MOVEMEM 3/4 4-39 3/4.4.12 LETDOWN LINE EXCJSS FLOW 3/4 4-41 3/4.4.13 REACTOR COOLANT SYSTEM VENTS 3/4 4-42 l

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - MODES 1, 2 AND 3 (> 1750 PSIA) 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - MODES 3 (< 1750 PSIA) AND 4...

3/4 5-7 l

3/4 5.4 REFUELING WATER TANK 3/4 5-8 3/4.6 CONTAINMENT SYSTEMS 1

3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY...............

3/4 6-1 Containment Leakage................

3/4 6-2 i

Containment Air Locks...............

3/4 6-5 Internal Pressure.................

3/4 6-7 i

Air Temperature..................

3/4 6-8 Containment Structural Integrity 3/4 6-9 Containment Purge System 3/4 6-11 1

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System 3/4 6-12 Containment Cooling System 3/4 6-14 2

3/4.6.3 IODINE REMOVAL SYSTEM...............

3/4 6-16 3/4.6.4 CONTAINMENT ISOLATION VALVES 3/4 6-19 i

3/4.6.5 COMBUSTIBLE GAS CONTROL l

Hydrogen Analyzers 3/4 6-21 Electric Hydrogen Recombiners - W.........

3/4 6-22 3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM 3/4 6-23 i

CALVERT CLIFFS - UNIT 2 V

Amendment No. 194 l

c TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SORVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves...................

3/4 7-1 Auxiliary Feedwater System 3/4 7-5 Condensate Storage Tank..............

3/4 7-8 Activity 3/4 7-9 Main Steam Line Isolation Valves 3/4 7-11 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..

3/4 7-12 3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4 7-13 3/4.7.4 SERVICE WATER SYSTEM 3/4 7-14 3/4.7.5 SALTWATER SYSTEM 3/4 7-15 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.....

3/4 7-16 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM 3/4 7-20 3/4.7.8 SNUBBERS 3/4 7-23 3/4.7.9 SEALED SOURCE CONTAMINATION............

3/4 7-30 3/4.7.10 WATERTIGHT DOORS 3/4 7-32 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System...........

3/4 7-33 l

Spray and/or Sprinkler Systems 3/4 7-37 Halon System 3/4 7-40 Fire Hose Stations 3/4 7-42 Yard Fire Hydrants and Hydrant Hose Houses 3/4 7-45 3/4.7.12 PENETRATION FIRE BARRIERS.............

3/4 7-47 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 3

Operating.....................

3/4 8-1 Shutdown 3/4 8-6 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating...........

3/4 8-9 A.C. Distribution - Shutdown 3/4 8-11 D.C. Distribution - Operating...........

3/4 8-13 l

D.C. Distribution - Shutdown 3/4 8-17 1

CALVERT CLIFFS - UNIT 2 VI Amendment No. 194 l

l TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTni. TION................

3/4 9-1 3/4.9.2 INSTRUMENTATION..................

3/4 9-2 3/4.9.3 DECAY TIME 3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS 3/4 9-4 3/4.9.5 COMMUNICATIONS 3/4 9-6 3/4.9.6 REFUELING MACHINE OPERABILITY...........

3/4 9-7 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..

3/4 9-9 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION 3/4 9-10 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM 3/4 9-12 1

3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-13 3/4.9.11 SPENT FUEL P0OL WATER LEVEL............

3/4 9-14 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM 3/4 9-15 3/4.9.13 SPENT FUEL CASK HANDLING CRANE 3/4 9-19 i

3/4.9.14 CONTAINMENT VENT ISOLATION VALVES.........

3/4 9-20 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..................

3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS...........

3/4 10-2 3/4.10.3 NO FLOW TESTS...................

3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT..............

3/4 10-4 3/4.10.5 COOLANT CIRCULATION................

3/4 10-5 l

l CALVERT CLIFFS - UNIT 2 VII Amendment No. 194 l

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I

SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASEOUS EFFLUENTS Explosive Gas Mixture...............

3/4 11-1 Gas Storage Tanks.................

3/4 11-2 3/4.12

[ DELETED].....................

3/4 12-1 l

7 CALVERT CLIFFS - UNIT 2 VIII Amendment No. 194

TABLE OF CONTENTS BASES SECTION PAGE 3/4.0 APPLICABILITY...................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL B 3/4 1-1 3/4.1.2 BORATION SYSTEMS B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE B 3/4 2-1 3/4.2.2, 3/4.2.3, and 3/4.2.4 TOTAL PLANAR AND I

INTEGRATED RADIAL PEAKING FACTORS - FI, AND P, AND AZIMUTHAL POWER TILT - T, B 3/4 2-1 3/4.2.5 DNB PARAMETERS B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY i

FEATURES (ESF) INSTRUMENTATION B 3/4 3-1 1

3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-1 3/4.4 REACTOR COOLANT SYSTEM

)

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.......

B 3/4 4-1 3/4.4.2 SAFETY VALVES...................

B 3/4 4-1 3/4.4.3 RELIEF VALVES...................

B 3/4 4-2 j

3/4.4.4 PRESSURIZER....................

B 3/4 4-3 3/4.4.5 STEAM GENERATORS B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-5 CALVERT CLIFFS - UNIT 2 IX Amendment No. 194 l

i TABLE OF CONTENTS BASES SECTION PAGE 3/4.4.7 CHEMISTRY.....................

B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY.................

B 3/4 4-6 3.4.4.9 PRESSURE / TEMPERATURE LIMITS............

B 3/4 4-7 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-11 3/4.4.11 CORE BARREL MOVEMENT B 3/4 4-11 3/4.4.12 LETDOWN LINE EXCESS FLOW B 3/4 4-12 3/4.4.13 REACTOR COOLANT SYSTEM VENTS B 3/4 4-12 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS B 3/4 5-1 3/4.5.4 REFUELINGWATERTANK(RWT)

B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT................

B 3/4 6-1 J

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS B 3/4 6-3 3/4.6.3 IODINE REMOVAL SYSTEM...............

B 3/4 6-3 3/4.6.4 CONTAINMENT ISOLATION VALVES B 3/4 6-3 1

3/4.6.5 COMBUSTIBLE GAS CONTROL..............

B 3/4 6-4 3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM B 3/4 6-4 i

i CALVERT CLIFFS - UNIT 2 X

Amendment No. 194 l

d

TABLE OF CONTENTS BASES SFCTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..

B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-4 i

3/4.7.5 SALTWATER SYSTEM B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.....

B 3/4 7-4 l

3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM B 3/4 7-4 3/4.7.8 SNUBBERS B 3/4 7-5 j

3/4.7.9 SEALED SOURCE CONTAMINATION............

B 3/4 7-6 j

3/4.7.10 WATERTIGHT DOORS B 3/4 7-6 3/4.7.11 FIRE SUPPRESSION SYSTEMS B 3/4 7-7 i

3/4.7.12 PENETRATION FIRE BARRIERS.............

B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS l

3/4.9.1 BORON CONCENTRATION............

B 3/4 9-1 3/4.9.2 INSTRUMENTATION..................

B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS B 3/4 9-1 4

3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 REFUELING MACHINE OPERABILITY...........

B 3/4 9-2 CALVERT CLIFFS - UNIT 2 XI Amendment No. 194 l

O TABLE OF CONTENTS BASES SECTION PAGE 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL..........

B 3/4 9-3 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE B 3/4 9-3 1

3/4.9.14 CONTAINMENT VENT ISOLATION VALVES.........

B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS................

B 3/4 10-1 3/4.10.3 NO FLOW TESTS...................

B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT..............

B 3/4 10-1 3/4.10.5 COOLANT CIRCULATION................

B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASE0US EFFLUENTS.................

B 3/4 11-1 l

3/4.12

[ DELETED].....................

B 3/4 12-1 CALVERT CLIFFS - UNIT 2 XII Amendment No. 194

=

~_.

s TABLE OF CONTENTS DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION...................

5-1 1

5.2 REACTOR CORE 5.2.1 Fuel Assembl i es..................

5-1 3

5.2.2 Control Element Assemblies 5-1 5.3 FUEL STORAGE 5.3.1 Cri ti cal i ty....................

5-1 5.3.2 Drainage 5-2 l

5.3.3 Capacity 5-2 4

i i

i i

4 i

o CALVERT CLIFFS - UNIT 2 XIII Amendment No. 194 l

b TABLE OF CONTENTS ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6.2.1 Onsite & Offsite Organizations 6-1 l

6.2.2 Unit Staff 6-1 6.3 FACILITY STAFF QUALIFICATIONS...........

6-3 1

6.4 PROCEDURES 6-3 6.5 PROGRAMS AND MANUALS 6.5.1 Offsite Dose Calculation Manual (0DCM) 6-4 6.5.2 Post-Accident Sampling 6-5 6.5.3 Primary Coolant Sources Outside Containment....

6-5 6.5.4 Technical Specification Bases Control Program...

6-5 6.5.5 Radioactive Effluent Controls Program.......

6-6 6.5.6 Containment Leakage Rate Testing Program 6-8 l

6.6 REPORTING REQUIREMENTS 6.6.1 Occupational Radiation Exposure Report 6-9 l

6.6.2 Annual Radiological Environmental Operating Report 6-9 l

6.6.3 Radioactive Effluent Release Report........

6-10 l

6.6.4 Monthly Operating Report 6-10 l

6.6.5 Core Operating Limits Report (COLR)........

6-11 l

6.6.6 Pressurizer PORV and Safety Valve Report 6-15 l

CALVERT CLIFFS - UNIT 2 XIV Amendment No. 194

1.0 DEFINITIONS l

FRECUENCY NOTATION 1.15 The FREQUENCY NOTATIOk specified for the performance of Surveillance Requirements sha!1 correspond to the intervals defined in Table 1.2.

GASE0US RADWASTE TREATMENT SYSTEM 1.16 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting Primary Coolant System offgases from the Primary System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.17 IDENTIFIED LEAKAGE shall be-a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to the Secondary System.

MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l

occupationally associated with the plant. This category does not includa employees of the utility, its contractors or vendors. Also excluded fron this category are persons who enter the site to service equipment or to l

make deliveries.

OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.19 The 0FFSITE DOSE CALCULATION MANt/AL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM i shall also cor.tain the radioactive effluent controls, radiological l

environmental monitoring activities, and descriptions of the information l

CALVERT CLIFFS - UNIT 2 1-4 Amendment No. 194

1.0 DEFINIT 19NS l

1 that should be included in the Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report, required by Specifications 1

6.6.2 and 6.6.3, respectively.

OPERABLE - OPERABILITY k

1.20 A system, subsystem, train, component or device shall be OPERABLE or 3

have OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subsystem.

3 train, component or device to perform its function (s) are also capable of i

performing their related support function (s).

t OPERATIONAL MODE 1.21 An OPERATIONAL MODE shall correspond to any one inclusive combination 4

of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

i i

PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

l t

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE B0UNDARY LEAKAGE shall be leakage (except steam generator 1

tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

1 4

l a

J 4

4 PURGE - PURGING 1.24 PURGE or PURGING is the controlled process of disenarging air or gas l

from a confinement to maintain temperature, humidity, concentration or i

other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

)

CALVERT CLIFFS - UNIT 2 1-5 Amendment No. 194 i

1 i

1.0 DEFINITIONS RATED THERMAL POWER 2

1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate l

to the reactor coolant of 2700 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1

1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l

when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in l

Section 50.73 to 10 CFR Part 50.

SHUTDOWN MARGIN i

1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by l

which the reactor is subcritical or would be subcritical from its present condition assuming all full length control element assemblies (shutdown and 4

regulating) are fully inserted except for the single assembly of highest l

reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is l

i neither owned, nor leased, nor otherwise controlled by the licensee.

4 l

SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel l

response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.31 A STAGGERED TEST BASIS shall consist of:

l a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

CALVERT CLIFFS - UNIT 2 1-6 Amendment No. 194

1.0 DEFINITIONS THERMAL POWER 1.32 THERMAL POWER shall be the total reactor core heat transfer rate to l

the reactor coolant.

TOTAL INTEGRATED RADIAL PEAKING FACTOR - FJ 1.33 The TOTAL INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak l

pin power to the average pin power in an unrodded core.

TOTAL PLANAR RADIAL PEAKING FACTOR - FI, 1.34 The TOTAL PLANAR RADIAL PEAKING FACTOR is the maximum ratio of the l

peak to average power density of the individual fuel rods in any of the unrodded horizontal planes.

UNIDENTIFIED LEAKAGE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED l

4 LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.36 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY l

access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.37 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and l

installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

I CALVERT CLIFFS - UNIT 2 1-7 Amendment No. 194 i

l 8

^

1.0 DEFINITIONS J

VENTING i

1.38 VENTING is the controlled process of discharging air or gas from a l

confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is 3

not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

1

)

l I

4 I

l i

l i

'l l

i i

5 i

i I

l i

l j

CALVERT CLIFFS - UNIT 2 1-8 Amendment No. 194

-l

= _... _ _.. -... _ -.

r 3/4.3 INSTRUMENTATION i

3/4.3.3 MONITORING INSTRUMENTATION

[ Technical Specifications 3/4.3.3.9 and 3/4.3.3.10 have been deleted.]

3 a

)

1 I

4 1

i i

l 1

l 1

i s

i I

e i

i

?

j 1

l 1

1 CALVERT CLIFFS - UNIT 2 3/4 3-41 Amendment No. 194 i

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASE0US EFFLUENTS l

1 1

Explosive Gas Mixture (Hydrogen rich systems not designed to withstand a hydrogen explosion)

LIMITING C'JNDITION FOR OPERATION 3.11.1.1 The concentration of oxygen in the Waste Gas Holdup System shall l

be limited to less than or equal to 4% by volume.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in a waste gas decay tank greater than 4% by volume immediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume without delay, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1 The concentration of oxygen in the Waste Gas Holdup System shall be determir.ed to be within the above limit by collecting and analyzing a sample from the Waste Gas Decay Tank once per week on the in-service tank and following tank isolation. Waste Gas Surge Tank samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other times.

CALVERT CLIFFS - UNIT 2 3/4 11-1 Amendment No. 194

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 GASE0US EFFLUENTS l

Gas Storace Tanks LIMITING CONDITION FOR OPERATION 3.11.1.2 The quantity of radioactivity contained in each gas storage tank j

shall be limited to less than or equal to 58,500 curies noble gases (consideredasXe-133).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to that tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 The quantity of radioactive material contained in the in-1ervice l

gas storage tank shall be determined to be within the above li: nit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Coolant System specific activity of Xe-133 is greater than 150 pCi/ml.

i l

CALVERT CLIFFS - UNIT 2 3/4 11-2 Amendment No. 194

.. ~. -.. ~. -... - -...

s i

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

[ Technical Specification Section 3/4.12 has been deleted.]

l t

b i

l l

4 CALVERT' CLIFFS - UNIT 2 3/4 12-1 Amendment No. 194

e 3/4.3 INSTRUMENTATION BASES In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during an extended COLD SHUTDOWN.

This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved.

If only one channel is inoperable, it should be restored to OPERABLE status in accordance with the schedule outlined in a Special Report.

If both channels are inoperable, the system shall be restored to OPERABLE status in the next refueling outage.

3/4.3.3.7 Fire Detection Instrumentation OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable 1

instrumentation is restored to OPERABILITY.

I CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. 194

5 3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 GASEOUS EFFLUENTS l

3/4.11.1.1 Explosive Gas Mixture l

This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System is maintained below the flammability limit of oxygen. Maintaining the concentration of oxygen below its flammability limit provides assurance 1

that the releases of radioactive materials will be controlled in conformance with the requirements of 10 CFR Part 50, Appendix A, Genera; Design Criterion 60.

3/4.11.1.2 Gas Storace Tanks l

The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the

)

quantity that provides assurance that in the event of an uncontrolled i

release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 10 CFR Part 100 limits.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed accident guidelines.

l

/

I CALVERT CLIFFS - UNIT 2 B 3/4 11-1 Amendment No. 194 J

o i

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

]

BASES i

[ Technical Specifications Section 3/4.12, and the associated Bases, have been deleted.]

I

-l 1

i I

• )

CALVERT CLIFFS - UNIT 2 B 3/4 12-1 Amendment No. 194

6.0 ADMINISTRATIVE CONTr.0LS c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d.

Proposed changes to the Technical Specifications incorporated in the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

6.5.5 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from l

radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and setpoint determination, in accordance with the methodology in the ODCM; b.

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to l

10 CFR Part 20, Appendix B, Table II, Column 2; c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents, in accordance with 10 CFR 20.1302, and with the methodology and parameters in the ODCM; d.

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS to be limited:

1.

During any calendar quarter:

Less than or equal to 3 mrems to the total body, and to less than or equal to 10 mrems to any organ; and 2.

During any calendar year:

Less than or equal to 6 mrems to the total body, and to less than or equal to 20 mrems to any organ; e.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, in accordance with the methodology and parameters in the ODCM, at least every 31 days; CALVERT CLIFFS - UNIT 2 6-6 Amendment No. 194

o 6.0 ADMINISTRATIVE CONTROLS f.

Limitations on the functional capability and use of the Liquid Radwaste Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the i

projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body, or 1.20 mrem to any organ in a 92-day period; g.

Limitations on the functional capability and use of the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the calculated doses to UNRESTRICTED AREAS exceeds 1.20 mrad for gamma radiation, and 2.40 mrad for beta radiation in a 92-day period; h.

Limitations on the functional capability and use of the Ventilation Exhaust Treatment System to ensure that appropriate portions of this system are used to reduce releases of i

radioactivitv when the calculated doses due to gaseous releases to UNRESTTs1CTED AREAS exceeds 1.8 mrem to any organ in a 92-day i

period; i.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:

1 1.

For noble gases:

Less than or equal to 500 mrems/yr to the total body, and less than or equal to 3000 mrems/yr to the skin; and 2.

For Iodine-131 and for all radionuclides in particulate form with half lives greater than 8 days:

Less than or equal to 1500 mrems/yr to any organ; j.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:

1.

During any calendar quarter:

Less than or equal to 10 mrads for gamma radiation, and less than or equal to 20 mrads for beta radiation; and 2.

b ring any calendar year:

Less than or equal to 20 mrads for gamma radiation, and less than or equal to 40 mrads for beta radiation; CALVERT CLIFFS - UNIT 2 6-7 Amendment Ho. 194

~

o f

1 6.0 ADMINISTRATIVE CONTROLS k.

Limitations on the annual and quarterly doses to a MEMBER OF THE PUELIC from Iodine-131, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to areas beyond the SITE BOUNDARY, to be limited:

1.

During any calendar quarter:

Less than or equal to 15 mrems to any organ; 2.

During any calendar year:

Less than or equal to 30 mrems to any organ; and 3.

Less than 0.1% of the limits of 6.5.5.k(1) and (2) as a result of burning contaminated oil; and 1.

Limitations on the annual dose or dose comitment to any MEMBER OF THE PUBLIC due to releases of radioactivity, and to radiation from uranium fuel cycle sources to be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

6.5.6 Containment Leakace Rate Testing Program A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The perk calculated containment internal pressure for the design basis loss-of-coolant accident, P., is 49.4 psig.

The containment design pressure is 50 psig.

The maximum allowable containment leakage rate, L, shall be 0.20 percent of containment air weight per day at P,.

]

Containment leakage rate acceptance criterion is 51.0 L. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria is 5 0.75 L, for Type A tests.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

CALVERT CLIFFS - UNIT 2 6-8 Amendment No. 194

6.0 ADMINISTRATIVE CONTROLS 6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accoraance with 10 CFR 50.4.

6.6.1 OccuDational Radiation Exposure Report

• A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignment to various duty functions may be estimates based on pocket dosimeter, electronic personal dosimeter or thermoluminescent dosimeter. Small exposures totalling < 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions.

The report shall be l

submitted prior to March 31 of each year.

6.6.2 Annual Radiolooical Environmental Operatino Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, l

interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in the ODCM, and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C.

The Annual Radiological Environmental Operating Report shall include the l

results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program, and the exposure period associated with each result.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

A single submittal may be made for Calvert Cliffs. The submittal should combine those sections that are comon to both units.

Occupational dose from the Independent Spent Fuel Storage Installation will be reported separately.

CALVERT CLIFFS - UNIT 2 6-9 Amendment No. 194

t 6.0 ADMINISTRATIVE CONTROLS 6.6.3 Radioactive Effluent Release Report

• The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a (i.e.,,, time between submittal of the reports must be no longer than 12 months)

The report I

shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:

a.

A description of the equipment, components and processes involved; and b.

Documentation of the fact that the change, including the safety analysis, was reviewed and found acceptable by the onsite review function.

The report shall also include changes to the ODCM, in accordance with Specification 6.5.1.c 6.6.4 Monthly Operatino Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis, no later than the 15th of each month following the calendar month covered by the report.

1 I

A single submittal may be made for Calvert Cliffs, since the Radwaste Systems are common to both units.

In lieu of submission with the Radioactive Effluent Release Report Sr" and Sr" analyses results may be submitted in a supplementary report within 120 days after submittal of the Radioactive Effluent Release Report.

CALVERT CLIFFS - UNIT 2 6-10 Amendment No. 194

i

(

6.0 ADMINISTRATIVE CONTROLS 6.6.5 Core Operatina Limits Report (COLR) a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

2.2.1 3.1.1.1 3.1.1.2 3.1.1.4 i

3.1.3.1 3.1.3.6 3.2.1 3.2.2.1 3.2.3 3.2.5 3.9.1 l

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC; specifically, those described in the following documents:

(1) CENPD-199-P, Latest Approved Revision, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LC0 Setpoint Methodology for Analog Protection Systems,"

January 1986 (2) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II," December 1979 (3) CEN-124(B)-P, " Statistical Combination of Uncertainties Methodolog; Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2," January 1980 (4)

CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (5)

CEN-191(B)-P,"CETOP-DCodeStructureandModelingMethods for Calvert Cliffs Units 1 and 2," December 1981 (6)

Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr.

(BG&E), dated June 24,1982, Unit 1 Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER)

(7) CEN-348(B)-P, " Extended Statistical Combination of Uncertainties," January 1987 CALVERT CLIFFS - UNIT 2 6-11 Amendment No. 194 l

5 6.0 ADMINISTRATIVE CONTROLS (8)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9) CENPD-161-P-A, " TORC Code, A Computer Code for Determining the Thennal Margin of a Reactor Core," April 1986 (10) CENPD-162-P-A, Latest Approved Revision, " Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1. Uniform Axial Power Distribution" (11) CENPD-207-P-A, Latest Approved Revision, " Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part'2, Non-Uniform Axial Power Distribution" (12) CENPD-206-P-A, Latest Approved Revision, " TORC Code, Verification and Simplified Modeling Methods" (13) CENPD-225-P-A, Latest Approved Revision, " Fuel and Poison Rod Bowing" (14) CENPD-266-P-A, Latest Approved Revision, "The ROCS and DIT Computer Code for Nuclear Design" (15) CENPD-275-P-A, Latest Approved Revision, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers" (16) CENPD-382-P-A, Latest Approved Revision, "C-E Methodology for Core Designs Containing Erbium Burnable Absorbers" (17) CENPD-139-P-A, Latest Approved Revision, "C-E Fuel Evaluation Model Topical Report" (18) CEN-161-(B)-P-A, Latest Approved Revision, " Improvements to Fuel Evaluation Model" (19) CEN-161-(B)-P, Supplement 1-P, " Improvements to Fuel Evaluation Model," April 1989 (20) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (21) CEN-372-P-A, Latest Approved Revision, " Fuel Rod Maximum Allowable Gas Pressure" (22) Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC), dated December 15,1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" CALVERT CLIFFS - UNIT 2 6-12 Amendment No. 194 l

4 i

6.0 ADMINISTRATIVE CONTROLS (23) CENPD-132, Supplement 3-P-A, Latest Approved Revision, i

' Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS" (24) CENPD-133, Supplement 5, "CEFLASH-4A, a FORTRAN 77 Digital j

Computer Program for Reactor Blowdown Analysis," June 1985

)

j (25) CENPD-134, Supplement 2, "COMPERC-II, a Program for i

Emergency Refill-Reflood of the Core," June 1985 3

I (26) Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE),datedJuly 31, 1986, " Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports" j

(27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical j

Geometry Fuel Rod Heat Transfer Program," April 1977 (28) Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE),

1 dated September 6, 1978, " Evaluation of Topical Report CENPD-135, Supplement 5" l

i (29) CENPD-137, Supplement 1-P, " Calculative Methods for.the C-E j

Small Break LOCA Evaluation Model," January 1977 (30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, A Computer Program i

for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (31) Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE),

dated September 27, 1977, " Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" s

(32) CENPD-138, Supplement 2-P, " PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant t-

)-

Heatup," January 1977 (33) Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer, dated 4i April 10,1978, " Evaluation of Topical Report CENPD-138, j

Supplement 2-P" (34) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC) dated February 22, 1985, "Calvert i

Cliffs Nuclear Power Plant Unit 1; Docket No. 50-317, j

Amendment to Operating License DPR-53, Eighth Cycle License Application" (35) Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr.

(BG&E), dated May 20, 1985, " Safety Evaluation Report j

Approving Unit 1 Cycle 8 License Application" i

s CALVERT CLIFFS - UNIT 2 6-13 Amendment No. 194 l

1 a

6.0 ADMINISTRATIVE CONTROLS (36) Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22, 1980, " Amendment to Operating License No. 50-317, Fifth Cycle License Application" (37) Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr.

(BG&E), dated December 12, 1980, " Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" I

(38) Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1,1986, "Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 & 50-318, Request 4

for Amendment" l

(39) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan i;

(BG&E),datedJuly7,1987,DocketNos.50-317and50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)

(40) CENPD-188-A, Latest Approved Revision, "HERMITE: A Multi-Dimensional Space-Time Kinetics Code for PWR Transients" (41) The Full Core Power Distribution Monitoring System 4

referenced in Specifications 3.1.3.1, 3.2.2.1, 3.2.3, and i

the BASES is described in the following documents:

(a) CENPD-153-P, Latest Approved Revision, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System" (b) CEN-199(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LC0 on Calvert Cliffs Unit I and j

Unit 2," November 1979 (c)

Letter from Mr. G. C. Creel (BG&E) to NRC Document i

Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket 50-318 Request for Amendment, Unit 2 Ninth Cycle License Application" (d)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42) Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, " Approval to Use Convolution Technique in Main Steam Line Break Analysis -

Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2 (TACNos.M90897andM90898)

CALVERT CLIFFS - UNIT 2 6-14 Amendment No. 194 l

6.0 ADMINISTRATIVE CONTROLS The core operating (e.mits shall be determined such that all li c.

i applicable limits g., fuel themal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall j

be provided upon issuance for each reload cycle to the NRC.

1 i

6.6.6 Pressurizer PORV and Safety Valve Report a

A report shall be submitted prior to March 1 of each year documenting all failures and challenges to the pressurizer PORVs or safety valves.

i i

CALVERT CLIFFS - UNIT 2 6-15 Amendment No. 194 l