ML20154C399

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Amends 113 & 96 to Licenses DPR-53 & DPR-69,respectively, Deleting Requirements for post-accident Sampling Sys & post-accident Main Vent Iodine & Particulate Monitors
ML20154C399
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/19/1986
From: Thadani A
Office of Nuclear Reactor Regulation
To:
Baltimore Gas & Electric Co (BGE)
Shared Package
ML20154C404 List:
References
DPR-53-A-113, DPR-69-A-096 NUDOCS 8603050132
Download: ML20154C399 (33)
v • d • e


Text

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UNITED STATES if h

NUCLEAR REGULATORY COMMISSION

,j WASHINGTON, D. C. 20655

\\.....J BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.113 License No. DPR-53 1.

The Nuclear Regulatory heission (the Commission) reas found that:

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated September 9, 1985, as supplemented on October 29, 1985, complies wih the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

sen 98e! 8s880A7 P

2-2.

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

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.113 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

)

hok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance:

Februa ry 19, 1986

ATTACHMENT TO LICENSE AMENDMENT NO. 113 FACILTIY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

The corresponding overleaf pages are provided to maintain document completeness.

Remove Pages I"'

'N VII VII XII XII XVI XVI 3/4 3-26 3/4 3-26 3/4 3-28 3/4 3-28 3/4 3-77 (reprinted) 3/4 7-78 B 3/4 7-7 8 3/4 7-7 6-21 6-21 6-22 6-22 6-23 1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......

3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM.......................

3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM.................................

3/4 7-15 3/4.7.5 SALT WATER SYSTEM....................................

3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............

3/4 7-17 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM.........

3/4 7-21 3/4.7.8 SNUBBERS.............................................

3/4 7-25 3/4.7.9 SEALED SOURCE _ CONTAMINATION..........................

3/4 Z-63 3/4.7.10 WATERTIGHT D00RS.....................................

3/4 7-65 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................

3/4 7-66 Spray and/or Sprinkler Systems.......................

3/4 7-69 Halon System.........................................

3/4 7-72 Fire Hose Stations...................................

3/4 7-73 Yard Fire Hydrants and Hydrant Hose Houses...........

3/4 7-75 3/4.7.12 PENETRATION FIRE BARRIERS............................

3/4 7-77 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating............................................

3/4 8-1 Shutdown.............................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating........................

3/4 8-6 A.C. Distribution - Shutdown.........................

3/4 8-7 D.C. Distribution - Operating........................

3/4 8-8 D.C. Di stribution - Shutdown.........................

3/4 8-11 i

CALVERT CLIFFS - UNIT 1 VII Amendment No. 26, fl. 54. 99,113 l

~ - -.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

SECTION, PAGE 3/4.9 REFUELING OPERATIONS

,,g,,,

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

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 9-5 i

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

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.........

3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION................

3/4 9-8 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................

3/4 9-10 3/4.9.11 SPENT FUEL POOL WATER LEVEL.........................

3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM......................

3/4 9-12 3/4.9.13 SPENT FUEL CASK HANDLING CRANE......................

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

3/4 9-17 l

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...........................

i 3/4.10.3 NO FLOW TESTS........................................

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 VIII Amendment No. 26, 55, 8 8

e o

INDEX BASES SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS................. 8 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 COMBUSTIBLE GAS CONTR0L..............................

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

l l

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CALVERT CLIFFS - UNIT 1 XI

= _ _ _ _ - - _

INDEX BASES SECTION

_PAGE j

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 j

3/4.7.4 SERVICE WATER SYSTEM................................. B 3/4 7-4 l

3/4.7.5 SALT WATER SYSTEM.................................... B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............ B 3/4 7-4 i

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 3/4.7.9 SEALE0 SOURCE C0NTAMIf;ATION.......................... B 3/4 7-6 3/4.7.10 WATERTIGHT D00RS..................................... 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 SY9TEMS................................ B 3/4 8-1 I

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION...................................... B 3/4 9-1 i

3/4.9.3 DE C AY T I ME........................................... B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS............................. B 3/4 9-1

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CALVERT CLIFFS - UNIT 1 XII Amendment No. 26./99,113 i

l l

1

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY............................................". 6-1

..J M e

6.2 ORGANIZATION 0ffsite...................................................

6-1 Fa c i l i ty S t a f f..............................................

6-1 6.3 FACILITY STAFF QUAL I FICATIONS............................. 6-6 6.4 TRAINING..................................................

6-6 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

Fu n c t i o n................................................

6-6 Co m po s i t i o n.............................................

6-6 A l t e r n a t e s..............................................

6-6 Meeting Frequency.......................................

6-7 Quorum..................................................

6-7 Responsibi11 ties........................................

6-7 A u t h o r i t y...............................................

6-8 R e c o r d s.................................................

6-8 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

Fu n c t i o n................................................

6-8 Co m po s i t i o n.............................................

6-9 Al t e r n a t e s..............................................

6-9 Co n s u l t a n t s.............................................

6-9 Meeting Frequency.......................................

6-9 Qu o r um..................................................

6-9 R e v i e w..................................................

6-1 0 A u d i t s..................................................

6-1 1 A u t h o r i ty...............................................

6-12 l

Records.................................................

6-12

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CALVERT CLIFFS - UNIT 1 XV Amendment No. pp, 105

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N....................................

6-12 6.7 SAFETY LIMIT VIOLATION.....................................

6-13 6.8 PRO C E DU R E S.................................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS..........................................

6-14 6.9.2 SPECIAL REP 0RTS..........................................

6-18 6.10 RECORD RETENTION...........................................

6-19 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-20 6.12 HIGH RADIATION AREA........................................

6-20 6.13 SYSTEM INTEGRITY...........................................

6-21 6.14 I OD I N E MON ITOR I NG..........................................

6-21 6.15 POSTACCIDENT SAMPLING......................................

6-21 l

6.16 PROCESS CONTROL PR0 GRAM....................................

6-22 l

6.17 0FFSITE DOSE CALCULATION MANUAL............................

6-22 l

6.18 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOL ID WASTE TRE ATMENT SY5TEMS.............................. 6-23 l

l CALVERT CLIFFS - UNIT 1 XVI Amendment No. 29.53.94.195.198. 113 t

i INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION

)

i LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within l

the specified limits.

]

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the set-point to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

3 b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

The provisions of Specifications 3.0.3 and 3.0.4 are not c.

applicable.

1 i

SURVEILLANCE REQUIREMENTS j

4.3.3.1 Each radiation monitoring instrumentation channel shall be i

demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL 1

CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

l l

t j

l CALVERT CLIFFS - UNIT 1 3/4 3-25 i

I I

TABLE 3.3-6

_ RADIATION MONITORING INSTRUMENTATION n

N M

MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION n

C 4

1. AREA MONITORS v.
a. Containment E
1. Purge & Exhaust Z

Isolation 3

6 1 220 mr/hr 10-j - 10 mr/hr 16 4

b. Containment Area High Range 2

1,2,3,84 5 10 R/hr 1 - 10 R/hr 30 0

2. PROCESS MONITORS g
a. Containment
1. Gaseous Activity w4 a) RCS Leakage Detection 1

1,2,3,&4 Not Applicable 1 - 10 ep, 34 6

11. Particulate Activity a) RCS Leakage Detection 1

1,2,3,&4 Not Applicable 1 - 10 ep, j4 6

b. Noble Gas Effluent s

g Monitors 3

1. Main Vent Wide Range 1

1,2,3,&4 10~7 to 10 uCi/cc 30 0

.E 3i

  • Alam setpoint to be specified in a controlled document (e.g., setpoint control manual)

S N

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply withtheACTIONrequirementsofSpecification3g.,6.1.

ACTION 16 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 30 - With the number of channels OPERA 8tE less than required by the Minimum Channels OPERA 8tE requirement, initiate the preplanned alternate wwthod of monitoring the appro-priate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

I

1) either restore the inoperable channel (s) to OPERABLE status within 7 days of the event, or
2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days follow-ing the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for i

restoring the system to OPERABLE status, i

i i

)

l 4

4

)

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CALVERT CLIFFS - UNIT 1 3/4 3-27 Amendment No. 99

TABLE 4.3-3 g

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS G

m E

CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE p

INSTRUMENT CHECK CALIBRATION TEST REQUIRED 3

1.

AREA MONITORS i

a.

Containment 5

1.

Purge & Exhaust

]

Isolation S

R M

6 i

b.

Containment Area High i

Range S

R M

1, 2, 3, & 4 g

2.

PROCESS MONITORS y

a.

Containment o$

1.

Gaseous Activity a) RCS Leakage Detection S

R M

1, 2, 3, & 4

11. Particulate Activity y

a) RCS Leakage 4,

Detection S

R M

1, 2, 3, & 4 b.

Noble Gas Effluent Monitors

.E 1.

Main Vent Wide Range S

R M

1, 2, 3, & 4 t

3 L

U

  • The CHANNEL CHECK shall be accomplished by comparing samples independently drawn from the main vent.

PLANT SYSTEMS 3/4.7.12 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.12 All fire barrier penetrations (i.e., cable penetration barriers, fire-doors and fire dampers), in fire zone boundaries, protecting safe shutdown areas shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more of the above required fire barrier penetrations inoperable within one hour either establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the inoperable fire barrier and establisn an hourly fire watch patrol; or verify the operability of automatic sprinkler systems (including the water flow alarm and supervisory system) on both sides of the inoperable fire barrier. Restore the inoperable fire barrier penetration (s) to operable status within 7 days or prepare and submit a Special Report to the Comission pursuant to Specifica-tion 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperable penetration and plans and schedule for restoring the fire barrier penetration (s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be OPERABLE:

a.

At least once per 18 months by a visual inspection.

b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspec-tion of the affected fire barrier penetration (s).

CALVERT CLIFFS - UNIT 1 3/4 7-77 Amendment No. 67,94,113

t PLANT SYSTEMS BASES 3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is, required to be maintained in the vicinity of_

the affected barrier until the barrier is restored to functional status.

CALVERT CLIFFS - UNIT 1 B 3/4 7-7 AmendmentNo.26,ppf,113

ADMINISTRATIVE CONTROLS b.

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

above, and in addition locked barricades shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained by the Supervisor-Radiation Control Operations and the Operations Shift Supervisor on duty under their,.asparate adminis-trative control.

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

1.

Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.

Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

6.14 IODINE MONITORING The licensee shall implement a program

  • which will ensure the capability to l

accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

6.15 POSTACCIDENT SAMPLING The licensee shall establish, implement and maintain a program

  • which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

  • It is acceptable if the licensee maintains details of the program in plant operation manuals (e.g., chemistry procedures, training instructions, maintenance procedures, ERPIPs).

CALVERT CLIFFS - UNIT 1 6-21 pt# f 19/24/p9,JLp pJ,pg, Am. No. Jpp, Jpp, JJg e ll3

~ _..

ADMINISTRATIVE CONTROLS 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to implementation.

6.16.2 Licensee initiated changes to the PCP:

g 1.

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

This submittal shall contain:

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

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

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

2.

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

6.17 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1 The ODCM shall be approved by the Conunission prior to implementation.

l 6.17.2 Licensee initiated changes to the ODCM:

g 1.

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

This submittal shall contain:

Sufficient infonnation to support the rationale for the change.

a.

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

b.

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

and found acceptable by the POSRC.

l 2.

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

I CALVERT CLIFFS - UNIT 1 6-22 Amendment No. 195.178.119.

ADMINISTRATIVE CONTROLS 6.18 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.18.1 Licensee initiated major changes to the radioactive waste systems l

(liquid, gaseous and solid) shall be reported to the Commission in the Semi-annual Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:

a.

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

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

1 CALVERT CLIFFS - UNIT 1 6-23 Amendment No. 113

p'# "%

UNITED STATES

't NUCLEAR REGULATORY COMMISSION j

g wasHmGTON, D. C. 20005 e

%,...../

BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. OPR-69 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated September 9,1985, as supplemented on October 29, 1985, complies wth the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; 8.

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

There is reasonable assurance (i) that the activities authorized by a

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; 1

0.

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

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

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.

J i

2.

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

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/ PWR Project Directorate #8 o

. Thadani, Director Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: February 19,1;86

ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

The corresponding overleaf pages are provided to maintain document completeness.

Remove Pages Insert Pages VII VII XII XII XVI XVI 3/4 3-26 3/4 3-26 I

3/4 3-28 3/4 3-28 3/4 7-69 (no changes) i 3/4 7-70 l

B 3/4 7-7 8 3/4 7-7 6-21 6-21 6-22 6-22 6-23 l

k

INDEX

\\

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION......

3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM.......................

3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM.................................

3/4 7-15 3/4.7.5 SALT WATER SYSTEM....................................

3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............

3/4 7-17 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM.........

3/4 7-21 3/4.7.8 SNUBBERS.............................................

3/4 7-25 3/4.7.9 SEALED SOURCE CONTAMINATION..........................

3/4 7-55 3/4.7.10 WATERTIGHT 000RS.....................................

3/4 7-37 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fi re Suppression Water System........................

3/4 7-58 Spray and/or Sprinkler Systems.......................

3/4 7-61 Halon System.........................................

3/4 7-64 f

Fire Hose Stations...................................

3/4 7-65 Yard Fire Hydrants and Hydrant Hose Houses...........

3/4 7-67 3/4.7.12 PENETRATION FIRE BARRIERS............................

3/4 7-69 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0 p e ra t i n g............................................

3 / 4 8 - 1 Shutdown.............................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating........................ 3/4 8-6 A.C. Distribution - Shutdown.........................

3/4 8-7 D.C. Distribution - Operating........................

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

3/4 8-11 3/4.9 REFUELING OPERATIONS 1

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

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

3/4 9-2 3/4.9.3 D E C AY T I ME........................................... 3/ 4 9-3 i

CALVERT CLIFFS - UNIT 2 VII Amendment No. 6. JJ, AJ, #6, M' 96

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

_PAGE 3/4.9.4

. CONTAINMENT PENET RATIONS.............................. 3/4 9-4 3/4.9.5 COMMUNICATIONS........................................ 3/4 9-5 3/4.9.6 REFUELING MACHINE OPERABILITY......................... 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING....... 3/4 9-7 3/4.9.8 SHUTDOWN COOL ING AND COOLANT CIRCULATIDN.............. 3/4 9 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.............. 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL.......................... 3/4 9-1 3/4.9.11 SPENT FUEL POOL WATER LEVEL........................... 3/4 9-11 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM.................... 3/4 9-12 3/4.9.13 SPENT FUEL CASK HANDLING CRANE........................ 3/4 9 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES..................... 3/4 9-17 l 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SH UT DOWN MARG I N....................................... 3 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT. CEA INSERTION AND POWER DISTRIBUTION LIMITS....................... 3/4 10-2 4

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 i

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INDEX

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s BASES i

SECTION PAGE 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 J

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 COMBUSTIBLE GAS CONTR0L..............................

B 3/4 6-4 l

3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM.......

B 3/4 6-4 i

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INDEX BASES i

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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 7-4 i

3/4.7.4 SERVICE WATER SYSTEM................................. B 3/4 7-4 3/4.7.5 SALT WATER SYSTEM.................................... B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............

B 3/4 7-4 J

3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM......... B 3/4 7-4 3/4.7.8 SNU B B E RS............................................. B 3/4 3/4.7.9 SEALED SOURCE CONTAMINATION.......................... B 3/

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3/4.7.10 WATERTIGHT D00RS..................................... B I

3/4.7.11 FIRE SUPPRESSION SYSTEMS............................. B 3/4 7-6 i

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

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3/4.8 ELECTRICAL POWER SYSTEMS................................ B 3/4 8-1 j

3/4.9 REFUELING OPERATIONS j

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 l

3/4.9.4 CONTAINMENT PENETRATIONS............................. B 1

i CALVERT CLIFFS - UNIT 2 XII Amendment No. g. JJ. 31, 96 i

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INDEX l

ADMINISTRATIVE CONTROLS I

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SECTION PAGE i

6.1 R E S PO N S I B I L I T Y............................................

6-1 i

6.2 ORGANIZATION j

Offs 1te...................................................6-1 Fa c i.1 1 ty S t a f f............................................

6 - 1 6.3 FACILITY STAFF QUALIFICATIONS.............................

6-6 4

6.4 TRAINING..................................................

6-6 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) i Function................................................

6-6 C o m po s i t i o n.............................................

6 - 6 Alternates..............................................

6-6 t

Meeting Frequency.......................................

6-7 4

Quorum..................................................

6-7 Responsibilities........................~................

6-7 Authority...............................................

6-8 1

Records.................................................

6-8 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

Function................................................

6-8 f

Composition..............................................

6-9 l

Alternates..............................................

6-9 i

Consultants.............................................

6-9 7

Meeting frequency.......................................

6 9 i

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Quorum..................................................

6-9 4

Review..................................................6-10 Audits..................................................6-11 A u t h o r i t y...............................................

6-12 l

l Records.................................................

6-12 i

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6.6 REPORTABLE EVENT ACT!0N....................................

6-12 6.7 SAFETY LIMIT VIOLATION.....................................

6-13 i

6.8 PROCEDURES.................................................

6-13 l

6.9 REPORTING REQUIREMENTS 4

6.9.1 ROUTINE REP 0RTS...........................................

6-14 6.9.2 SPECIAL REP 0RTS...........................................

6-18 6.10 RECORD RETENTION...........................................

6-19 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-20 i

6.12 HIGH RADIATION AREA........................................

6-20 i

6.13 SYSTEM INTEGRITY...........................................

6-21 i

J 6.14 IODINE MONITORING..........................................

6-21 i

6.15 POSTACCIDENT SAMPLING......................................

6-21 l

6.16 PROCESS CONTROL PR0 GRAM....................................

6-22 l

6.17 0FFSITE DOSE CALCULATION MANUAL............................

6 22 6.18 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND 1

SOLID WASTE TREATMENT SYSTEM5..............................

6-23 i

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i INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 4

RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in i

Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within i

the specified limits.

i APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the set-point to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the 1

channel inoperable, f

l b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

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c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I a.

I SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the perfonnance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

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TABLE 3.3-6 h

RADIATION MONITORING INSTRUMENTATION

  • m5 MINIMJM n

CHANNELS APPLICABLE ALARM / TRIP EASUREMENT C

INSTRUENT OPERABLE MODES

_SETPOINT RANGE ACTION Y

u' l.

AREA MONITORS i

.E a.

Containment

i. Purge & Exhaust m

Isolation 3

6 1 220 mr/hr 10 10 mr/hr 16 4

b.

Containment Area High Range 2

1, 2, 3 & 4 1 10 R/hr 1 - 10 R/hr 30 8

w1 2.

PROCESS IGNITORS u

A, a.

Containment c.

1.

Gaseous Activity a) RCS Leakage Detection 1

1, 2. 3 & 4 Not Applicable 10 - 10 cp, j4 j

6 l

11. Particulate Activity a) RCS Leakage

[

i Detection 1

1. 2, 3 & 4 Not Applicable 10 - 10 cpm 14 1

6 b.

Noble Gas Effluent 3

Monitors 1.

Main Vent Wide Range 1

1, 2, 3 & 4 10' to 10 uCi/cc 30 i

e Z

  • Alarm setpoint to be specified in a controlled document (e.g., setpoint control manual) g a.

4 TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 16 - With the number of channels OPERABLE less than required by the Minimum Channels OPERA 8LE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the i

appropirate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1) eitherrestoretheinoperablechannel(s)toOPERABLE status within 7 days of the event, or
2) prepare and sumbit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

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TABLE 4.3-3 i

SG RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1

g

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P CHANNEL M00ES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUENT CHECK CALIBRATION TEST REQUIRED l

0 t

1.

AREA MONITORS c

t fi a.

Containment

~*

m 1.

Purge & Exhaust l

Isolation S

R M

6 b.

Containment Area High I

1 i

Range S

R M

1, 2, 3 & 4 y

2.

PROCESS IGNITORS i

i Y

a.

Containment m

1.

Gaseous Activity 3

)'

a) RCS Leakage i

Detection S

R M

1, 2, 3 & 4 i

a 1

11. Particulate Activity l

g a) RCS Leakage l

s Detection S

R M

1, 2, 3 & 4 k

s b.

Noble Gas Effluent i

Monitors I

.E 1.

Main Vent Wide Range S

R M

1, 2, 3 & 4 l

i

=.

1'

  • The CHANNEL CHECK shall be accompli'hed by comparing samples independently drawn from the main vent.

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PLANT SYSTEMS l

3/4.7.12 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.12 All fire barrier penetrations (i.e., cable penetration barriers, fire-doors and fire dampers), in fire zone boundaries, protecting safe shutdown areas shall be OPERA 8LE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more of the above required fire barrier penetrations inoperable within one hour either establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the inoperable fire barrier and establish an hourly fire watch patrol; j

or verify the operability of automatic sprinkler systems (including the water flow alarm and supervisory system) on both sides of the inoperable fire barrier.

Restore the inoperable fire barrier penetration (s) to operable status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specifica-tion 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperable penetration and plans and schedule for restoring the fire barrier penetration (s) to operable status.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be OPERABLE:

I a.

At least once per 18 months by a visual inspection, b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspec-tion of the affected fire barrier penetration (s).

I CALVERT CLIFFS - UNIT 2 3/4 7-69 knendment No.11. AA. 75. 96 l

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PLANT SYSTEMS i

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BASES l

3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program

{

and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of, the affected barrier until the barrier is restored to functional status.

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