Text

Amends 64 & 46 to Licenses DPR-53 & DPR-69,respectively, Updating Limiting Conditions for Snubbers,Deleting Restriction on Reserve Battery Capacity Test & Assigning Reserve Battery to Capacity Test Load Group
	ML20039G912
Person / Time
Site:	Calvert Cliffs
Issue date:	12/28/1981
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20039G913	List: ML20039G912; ML20039G916; ML20039G918;
References
	NUDOCS 8201190290
	Download: ML20039G912 (29)
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',q NUCLEAR REGULATORY COMMISSION s.3 M "m2j WASHINGTON, D. C. 20555 o, y -

%, +.... /g BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 64 License No. DPR-53 7

1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 30, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, a's amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity 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 duthorized by this anendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations; D.

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

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

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8201190290 811228 PDR ADOCK 05000317 p

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license l

amendment, and paragraph 2.C.(2) of Facility Operating License l

No. DPR-53 is hereby amended to read as follows:

i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby 4

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incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION f

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7af,A

/ Robert A. Clark, Chief Operating Reactors Branch #3 4

1 Division of Licensing

Attachment:

3 Changes to the Technical Specifications

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Date of Issuance: December 28,.1981 i

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o-ATTACHMEf1T TO LICEllSE AMEN 0 MENT NO. 64 FACILITY OPERATING LICENSE N0. OPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix Technical Specifications with the enclosed pages as indicated.

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

The corresponding overleaf pages are also provided to' maintain document complete-ness.

Remove Insert VII VII 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 3/4 7-26a 3/4 7-26b 3/4 8-10 3/4 8-10 B 3/4 7-5 B.3/4 7-5 B 3/4 7-6 B 3/4 7-6 6-20 6-20 S

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l INDEX

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS l

l SECTION PAGE.

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3/4.9 REFUEL-ING OPERATIONS l

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

3/4 9-1 j

3/4.9.2 INSTRUMENTATION......................................

3/49-2 L

3/4.9.3 DECAY TIME...........................................

3/4 9-3 j

3/4.9 4 CONTAINMENT PENETRATIONS.............................

3/4 9-4 7

j 3/4.9.5 COMMUNICATIONS.......................................

3/49-5

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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 1

j 3/4.9.8 SHUTDOWN COOLING.AND COOLANT CIRCULATION ~~..~.......... 3/49-8

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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 i

i 3/4.9.11 SP ENT FU EL POOL WATER - L EVEL..........................

3/4 9-11 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM...................

3/4 9-12

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3/4.9.13 SPENT FUEL CASK HANDLING CRANE.......................

3/4 9-16 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

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3/4.10.4 CENTER CEA MISALIGNMENT..............................

3/4 10-4 3/4.10. 5 - COOLANT C IRCULATION..................................

3/4 10-5 I

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l' CALVERT CLIFFS - UNIT 1 VIII Amendment No. ff. 55 Y

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1 INDEX ns LIMITING CONDITIONS FOR OPERATICN AND SURVEILLANCE REOUIREMENTS 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 S ERVI C E WATER S YSTEM......................................

3/4 7-15 3/4.7.5 S ALT WATER S YS T EM............'.............................

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 S N U B D ERS..................................................

3 / 4 7 - 2 5 l

3/4.7.9 S EALED SOURC E CONTAMINATION...............................

3/4 7-63 3/4.7.10 WATERTIGHT 000RS..........................................

3/4 7-65 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fi re Suppres s ion Water Sys tem.............................

3/4 7-66 S pray and/or S pri nkl er Sys tems............................

3/4 7-69 Ha l o n Sy s t em..............................................

3 / 4 7 - 7 2 Fi r e H o s e S ta t i o n s........................................

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

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

3/4 7-77 3/4.8 ELECTRICRL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0 p e ra t i n g.................................................

3 / 4 8 -1 Shutdown..................................................3/48-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Di s tri buti on - Opera ti ng.............................

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

3/4 8-7 0.C. Di s tri bu ti on - Opera ti ng.............................

3/4 8-8 D. C. Di s tri bu tio n - S hu tdown..............................

3/4 8-11

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CALVERT CLIFFS - UNIT 1 VII Amendment No. 26, //, g 4

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3/4.7.8 SNUBBERS i

l LIftITING CONDITION FOR OPERATION 3.7.8.1 All snubbers listed in Table 3.7-4 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4 (MODES 5 and 6 for snubbers located ori

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systems required OPERABLE in those MODES.)

ACTION: With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber (s) to OPERABLE status, and perform an engineering evaluation

per Specification 4.7.8.b. and c. on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REOUIREMENTS 4.7.8.1 Each snubber shall.be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Insoections Visual inspections shall be performed in accordance with the fcilowing schedule:

No. Inoperable Snubbers Subsequent Visual **

oer Insoection Period Inscection Periode 0

18 months + 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days

[25%

5,6,7 62 days 1 25%

8 or more 31 days 1 25%

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation. Additional analyses, as needed, shall be completed in a reasonable period of time.

The inspection interval shall not be lengthened more than two steps at a time.

The provisions of Specification 4.0.2 are not applicable.

CALVERT CLIFFS - UNIT 1 3/4 7-25 Amendment No. 6 4 a.

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PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)

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b.

Visual Insoection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of detachment from foundations or supporting structures.

Snubbers which appear inoperable as a result of j

visual inspections may be determined OPERABLE for the purpose of estab-lishing the next visual inspection interval, providing that (1) the cause of the rejection.is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8 d, as applicable.

When the fluid port of a hydraulic snubber

is found i

to be uncovered, the snubber shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

For the snubber (s) found inoperable, an engineering evaluation shall be

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performed on the component (s) which are supported by the snubber (s).

The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspec-tion of the supported component (s).

The purpose of this eng'ineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service, c.

Functional Tests i

i At least once per 18 months during shutdown, a representative sample i

of 10% of the snubbers in use in the plant shall be functionally tested either in place or in a bench test.**

For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.d, an additional 5". of the snubbers shall be functionally tested until no more failures are found or until all snubbers have been functionally tested.

l This requirement is also applicable to snubbers served by a common hydraulic reservoir.

- The Steam Generator snubbers 1-63-13 through 1-63-28 need not be functionally tested until the refueling outage following June 30, 1985.

CALVERT CLIFFS - UNIT l-3/4 7-26 Amendment No. 35,9.i

PLANT SYSTEMS i

SURVEILLANCE RECUIREMENTS (Continued)

Snubbers identified in Table 3.7-4 as "Especially Difficult to Remove" or in "High Exposure Zones" shall also be included.in the representative sam pl e.

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test period.

Failure of these snubbers shall not entail functional testing of additional snubbers.

If any~ snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all generically susceptible snubbers of the same design subject to the same defect shall be functionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).

The scope of this engineering evaluation shall be. consistent with the licensee's engineering judgment and may be limited to a visual inspec-tion of the supported component (s).

The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

d.

Hydraulic Snubbers Functional Test Acceotance Criteria The hydraulic snubber functional test shall verify that:

1.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required to not displace under continuous load, the ~ ability of the snubber to withstand load without displacement shall be verified.

Permanent or other exemptions from functional testing for individual snubbers in 'these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber.lif,e destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

CALVERT CLIFFS - UNIT 1 3/4 7-26a Amendment No. 64

PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) e.

Snubber Service Life Monitoring

A record of the. service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.m.

At least once per-18 months, the installation and maintenance records for each snubber listed in Table 3.7-4 shall be-reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.**

If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-j evaluated or the snubber shall be replaced or reconditioned'so as to l

extend its service life beyond the date of the next scheduled service l-1.ife review. This reevaluation, replacement, or reconditioning shall i

be indicated in the records.

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f.. Snubbers Served by a Common Hydraulic Reservoir l

Snubbers served by a common hydraulic reservoir are indicated by La.

t bracket in Table 3.7-4.

All reservoirs serving more than one snubber shall be inspected to ensure adequate. hydraulic level:

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Within 7 days after reactor startup following 'a major outage or following any maintenance in the immediate vicinity of these j

snubbers, reservoirs, or associated hydraulic piping; and 4

2.

Every 31 days.+ 25%.

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The Snubber Service Life Program shall be fully implemented by January 1,1983.,

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- The provisions of Specification 4.0.2 are applicable.

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CALVERT CLIFFS - UNIT I 3/4 7-26b Anendment No.o 4 i

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' PLANT SYSTEMS BASES environment.

The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity o'f the reactor coolant system and all other safety related systems is maintained during and following'a seismic or other event initiating dynamic loads. Snubbers ex-cluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the' system on which they are installed, would have no adverse effect on any safety-related systsa.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval v' aries inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections perforced before that interval has elapsed may be used as a new reference point to detersine the next inspection.

However, the results of such early inspections perfor=ed before the original required time interval has elapsed (nominal time less 25'O may not be used to lengthen the required inspection interval.

Any inspecticn whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.

Generically susceptible snubbers are those which are (1) of a specific make or model, (2) of the same design, and (3) similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

These characteristics of the snubber installation shall be evaluated to determine if further functional testing of shnilar snubber installations is warranted.

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber made of failure, in order to deter-mine if any safety-related component or system has been adversely affected by the inoperability of the snubber.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degrada-tion on the supported component or system.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.

Observed ' failures of these sample snubbers shall require functional testing of additional units.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installa-tion and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.... ).

The requirement to monitor the snubber service life is included to ensure that the CALVERT CLIFFS - UNIT 1

.B 3/4 7-5 Amendment No. 6 4

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PLANT SYSTEMS BASES snubbers periodically undergo a performance evaluation in view of-their age and operating conditions.

The service life program is designed.to uniquely reflect the 'c'onditions at Calvert Cliffs. The criteria for evaluating service life shall be determined, and documented, by the licensee.

Records will provide statistical bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

I 3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

i 3/4.7.10 WATERTIGHT 000RS This specification is provided to ensure the protection of safety related equip-ment from the effects of water or steam escaping from ruptured pipes. or components in adjoining rooms.

3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire I

suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.

The fire suppression system consists of the water system, spray and/or sprinklers, Halon and fire hose stations.

The collective capability. of the fire suppres-sion systems is adequate to min'imize potential damage to safety related equip-j ment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression systems are inoperable, alternate cackup fire fighting equipment is reouired to be made available in i

the affected areas until the inoperable equipment is restored to service.

Where a continuous fire watch is required in lieu of fire protection equipment and habitability due to heat or radiation is a concern, the fire watch should be stationed in a habitable area as close as possible to the inoperable equip-ment.

l In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the' continued protection of the nuclear plant.

I CALVERT CLIFFS - UNIT 1 8 3/4 7-6 Amendment No. 26, $7, 61 l

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ELECTRICAL POWER SYSTEMS LI!1ITING CONDITION FOR OPERATION (Continued)

,e.

With one 125-volt D.C. battery inoperable during surveillance testing of the battery per Specification 4.8.2.3.2.e., operation may continue provided the associated bus is being powered by the Reserve Battery and an OPERABLE ~ charger.

f.' With single cells having a voltage decrease of more than 0.10 volts from the previous performance discharge test (4.8.2.3.2.e.) value, but still 3,2.10 volts per surveillance requirement 4.8.2.3.2.b.l.,

either restore / replace cells or replace the affected battery with the Reserve Battery within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOI STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.8.2.3.1 Each D.C. bus train shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignsent and indicated power availability:

4.8. 2.3. 2 Each 125-volt battery bank and charger and the Reserve Battery shall be demonstrated OPERAELE; a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.

2.

The pilot cell specific gravity, corrected to 77*F and full electrolyte level is 2,1.200.

3.

The pilot cell voltage is 3,2.10 volts.

4, The overall battery voltage is 3,125 volts.

b.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is > 2.10 volts under float charge and has not decreased more than 0.10 volts from the value observed during the latest performance discharge test (4.8.2.3.2.e).

2.

The specific gravity, corrected to 77*F and fGil electrolyte level, of each connected cell is > 1.200 and has not decreased more than 0.02 from the value observed during the previous test.

3.

The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

CALVERT CLIFFS - UNIT 1 3/4 8-9 Amendment' No. AD, 58

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ELECTRfCAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

At least once per 18 months by verifying that:

c.

1.

The cells, cell plates and battery racks shew no visual indica-tion of physical damage or deterioration.

2.

The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material.

d.

At least once per 18 months by verifying that the battery capacity, with the charger disconnected, is adequate to 6ither:

1.

Supply and maintain in OPERABLE status all of the actual emergency loads for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the battery is subjected to a battery service test, or 2.

Supply a dummy load of the following profile for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months while maintaining the battery tenniral voltage 3,100 vol ts :

a) Batteries 1121 and Reserve:

l First minute 3,827 amperes Next 1 minute > 461 amperes Next 117 minutes 3,251 amperes Next 1 minute 3,325 amperes b)

Batteries 12 and 22:

First minute 3,193 amperes Next 119 minutes 3,160 amperes At the completion of this battery test, the battery charger

shall be demonstrated capable of recharging the battery at a rate of < 400 amperes while supplying normal D. C. loads.

The battery shall be charged to at least 95%. capacity in < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

At least once per 60 months by verifying that the battery capacity l

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is at least 80% of the manufacturer's rating when subjected to a performance discharge test.

This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test.

Not applicable to the charger associated with the Reserve Battery.

l CALVERT CLIFFS - UNIT 1 3/4 8-10 Amendment No.,40, JA, 6 4

o ADMINISTRATIVE CONTROLS q

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

a.

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

b.

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

c.

All REPORTABLE OCCURRENCES submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations

. required by these Technical Specifications.

e.

Records of reactor tests and experiments.

f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments.

h.

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

i.

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

6.10.2 The following records shall be retained for the duration of the i

Facility Operating License:

a.

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

b.

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

Records of facility. radiation and contamination surveys.

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CALVERT CLIFFS - UNIT 1 6 Amendment No. 29 l

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i ADMINISTRATIVE CONTROLS d.

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

e.

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

f.

Records of transient or operational cycles for those facility i

components identified in Table 5.7.1.

g.

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

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

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

J.

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

k.

Records of meetings of the POSRC and the OSSRC.

1.

Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

m.

Records of the service lives of all snubbers listed on Table 3.7-4 including the date at which the service life cc=nences and associated installation and maintenance records.

6.11 RADIATI0t PROTECTIO'1 PROGRA*1 Procedures for personnel radiation protection shall be prepared cor::istent with the requirements of 10 CFR Part 20 and shall be approved, maintaindd and adhered to f'r all operations involving personnel radiation exposure.

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

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a.

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

CALVERT CLIFFS - UNIT 1 6-20 hendment No. 6 4

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8 UNITED STATES.

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NUCLEA'R REGULATORY COMMISSION

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9 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE' Amendment No. 46 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 30, 1981, 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 conforinity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

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

The issuance of this amendment will not be inimical to the 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.

l 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. OPR-69 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, 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 COMMISSIOk h

h.

/

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/ Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Iscuance: December 23, 1981 sum m

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 46 4

FACILITY OPERATING LICENSE NO. OPR-60 DOCKET NO. 50-317 Replace the follcwing pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The i

corresponding overleaf pages are also provided to maintain document complete-ness.

Remove, Insert VII VII 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 e.

3/4 7-26a 3/4 7-26b 3/4 8-10 3/4 8-10 8 3/4 7-5 8 3/4 7-5 B 3/4 7-6 B 3/4 7-6 1-6-20 6-20 s

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a INDEX LIMITING. CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS 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 S ERV I CE WATER SYST EM....................................... 3/4 7-15 3/4.7.5 S ALT WATER S YST EM.........................................

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

- a

[

3/4.7.8 SNU3BERS..................................................

3/4 7-25

'3/4.7.9 S EALED SOURCE CONTAMINATION...............................

3/4 7-5 5 3/4.7.10 WATERTIGHT 000RS..........................................

3/4 7-57

'3/4.7.11 FIRE SUPPRESSION SYSTEMS Fi re Suppres sion Wa ter Sys tem.............................

3/4 7-58 Spray and/or Spri nkl er Sys tems............................

3/4 7-61 l

Halon Sysem..............................................

3/4 7-64 Fi r e Ho s e S ta ti o ns........................................

3/4 7-6 5 Yard Fire Hydrants and Hydrant Hose Houses................

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

3/4 7-69 s

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

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

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

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Di s tri bu ti o n - Opera ti ng.............................

3/4 8-6 A.C. Di s tri bu ti o n - Shu tdown.................. '............

3/ 4 8-7 D.C. Di s tri bu tion - Opera ti ng............................

3/4 8-8 v

D.C. Distribution -

Shutdown..............................

3/4 8-11 3/4.9 REFUELING OPERATIONS

3/4.9.1 BO RON CON C ENTRAT I ON.......................................

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

3/4 9-2 3/4.9.3 DECAY TIME................................................

3/4 9-3 CALVERT CLIFFS - UNIT 2 VII Amendment No. 6, JT, Aa,4 g

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INDEX i!

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS i

i 3

SECTION PAGE 3/4.9.4 CONTAINMENT PENETRATIONS........../..................

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 POOL BUILDING......

3/4 9-7 3/4.9.8 SHUTD0'.4N COOLING AND COOLANT CIRCULATION............

3/49 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.............

3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR V ESS EL.........................

3/4 9-10 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 9-16 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN......................................

3/4 10-1 3/4.10.2 tt0DERATOR. TEMPERATURE COEFFICIENT, CEA INSERTION

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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 i

CALVERT CLIFFS-UNIT 2 VIII.

AmendmentNo.5,)),28 eM

PLANT SYSTEMS 3/4.7.8 SNUBBERS LIftITING CONDITION FOR OPERATION 3.7.8.1 All snubbers listed in Table 3.7-4 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.)

ACTION: With one or more. snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber (s) to OPERABLE status, and perform an engineering evaluation

per Specification 4.7.B.b. and c. nn the supported component or declare the supported system inoperable and I

follow the appropriate ACTION statement for that system.

SURVEILLANCE RE0VIREMENTS 4.7.8.1

$ach snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Insoections Visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual **

per Inspection Period Insoection Periode 0

18 months + 25%

1 -

12 months T 25%

2 6 months T 25%

3, 4 124 days T 25%

5,6,7 62 days T 25%

8 or more 31 days i25%

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.

A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation. Additional analyses, as needed, shall be' completed in a reasonable period of time.

The inspection interval shall not be lengthened more than two steps at a tine.

The provisions of Specification 4.0.2 are not applicable.

CALVERT CLIFFS - UNIT 2 3/4 7-25 Amendment No. 70, 4 6

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PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) b.

Visual Inscection Acceotance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of detachment from foundations or supporting structures.

Snubbers which appear inoperable as a result of visual inspections may be determined'0PERABLE for the purpose of estab-lishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.d.

as appl.icabl e.

When the fluid port of a hydraulic snubber *' is found to be uncovered, the snubber shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).

The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspec-tion of the supported component (s). The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported componer.t remains capable of meeting the designed service.

c.

Functional Tests At least once per 18 months during shutdown, a. representative sample of 10% of the snubbers in use in the plant shall be functionally tested either in place or in a bench test.**

For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.d, an additional 5% of the snubbers shall be functionally tested until no more failures are found or until all snubbers have been functionally tested.

This requirement is also applicable to snubbers served by a common hydraulic reservoir.

- The Steam Generator snubbers 2-63-11 through 2-63-26 need not be functionally tested until the refueling outage following June 30, 1985.

CALVERT CLIFFS - UNIT 2 3/4 7-26 Amendment No.M 33,16

i PLANT SYSTEMS SURVEILLANCE RECUIREMENTS (Continued)

Snubbers identified in Table 3.7-4 as "Especially Difficult to Remove" or in "High Exposure Zones" shall also be included in the representative sampl e.*

In addition to the' regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test period.

Failure of these snubbers shall not entail functional testing of additional snubbers.

If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all generically susceptible snubbers of the same design subject to the same defect shall be functionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria, For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).

The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspec-tion of the supported component (s).

The purpose of this engineering evaluation shall be 'to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

d.

Hydraulic Snubbers Functional Test Accaotance Criteria The hydraulic snubber. functional test shall verify that:

1.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in ooth tension and compression.

2.

' Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be ver.ified.

Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exenption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

CALVERT CLIFFS - UNIT 2 3/4 7-26a Amendment No.Es,4 g

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

Snubber Service Life Monitoring

A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.m.

At least once per 18 months, the installation and maintenance records for each snubber listed in Table 3.7-4 shall be. reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.**

If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement, or reconditioning shall b'e indicated in the records.

f., Snubbers Served by a Common Hydraulic Reservoir 1

Snubbers served by a common hydraulic reservoir are' indicated by a bracket in Table 3.7-4.

All reservoirs serving more than one snubber shall be inspected to ensure adequate hydraulic level:

1.

Within 7 days after reactor startup following 'a major outage or following any maintenance in the immediate vicinity of these snubbers, reservoirs, or associated hydraulic piping; and 2.

Every 31 days,+ 25%.

The Snubber Service Life Program shall be fully implemented by January 1,1983.

- The provisions of Specification 4.0.2 are applicable.

CALVERT CLIFFS - UNIT 2 3/4 7-26b Amendment No. E,4 6 1

l ELECTRICAL POWER SYSTEMS i

LI!11 TING CONDITION FOR OPERATION (Continued) e.

With one 125-volt D.C. battery inoperable during surveillance testing of the battery per Specification 4.8.2.3.2.e., operation may continue provided the associated bus is being powered by the Reserve Battery and an OPERABLE-charger.

f.

With single cells having a voltage decrease of more than 0.10 volts from the previous performance discharge test (4.8.2.3.2.e.) value, but still 3,2.10 volts per surveillance requirement 4.8.2.3.2.b.l.,

either restore / replace cells or replace the affected battery with the Reserve Battery within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.8.2.3.l' Each D.C. bus train shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.3,2 Each 125-volt battery bank and charger and the Reserve Battery shall be demonstrated OPERABLE; a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.

2.

The pilot cell specific gravity, corrected' to 77'F and full electrolyte level is 2,1.200.

3.

The pilot cell voltage is 3,2.10 volts.

4.

The overall battery voltage is 3,125 volts.

b.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is > 2.l0 volts under float

~

charge and has not decreased more than 0.10 volts from the value observed during the latest performance discharge test (4.8.2.3.2.e).,

2.

The specific gravity, corrected to 77*F and full electrolyte level, of each connected cell is > 1.200 and has not decreased more than 0.02 from the value observed during the previous test.

3.

The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

CALVERT CLIFFS - UNIT 2 3/4 8-9 Amendment No.

22, 40

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) c.

At least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show.no visual indica-tion of physical damage or deterioration.

2.

The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material.

d.

At least once per 18 months by verifying that the battery capacity, with the charger disconnected, is adequate to either:

1.

Supply and maintain in OPERABLE status all of the actual emergency loads for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the battery is subjected to a battery service test, or 2.

Supply a dummy load of the following profile for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months while maintaining the battery terminal voltage

> 100 volts:

a)

Batteries 11, 21 and Reserve:

l First minute > 827 amperes Next 1 minute > 461 amperes Next 117 minutis > 251 amperes Next 1 minute > 325 amperes b)

Batteries 12 and 22:

First minute > 193 amperes Next 119 minutes > 160 amperes At the completion of this battery test, the battery charger

shall be demonstrated capable of recharging the battery at a rate of 4

1 00 amperes while supplying normal D. C. loads. The battery shall be charged to at least 95% capacity in < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

e.

At least once per 60 months by verifying that the battery capacity l

is at least 80% of the. manufacturer's rating when subjected to a performance discharge test.

This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test.

t

Not applicable to the charger associated with th'e Reserve Battery.

CALVERT CLIFFS - UNIT 2 3/4 8-10 Amendment No.22, /0,1 g E ---- _

!e i

PLANT SYSTEMS BASES

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environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

3/4.T.8 SNUB 8ERS All snubbers are required ~0pERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systeas is maintained during and following a seismic or other event initiating dynamic loads.

Snubbers ex-cluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the. system cm which they are installed, would have no adverse effect on any safety-related system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspectica interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to detanmine the next inspection. However, the results of such early inspections perfc:rmed before the

~

original required time interval has elapsed (nominal time less Zm3) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be genericaMy susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically' susceptible snubbers are those which are (1) of a specific make or model, (2) of the same design, and (3) similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

These characteristics of the snubber installation shall be evaluated to determine if further functional testing of s-imilar snubber installations is warranted.

When a snubber is found inoperable, an engineering evaluation is ;:erformed, in addition to the determination of the snubber mode of failure, in srder to deter-mine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degrada-tion on the supported component or system.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plar.t shutdowns at 18 month intervals.

Observed. failures of these sample snubbers sball require functional testing of additional units.

The service life of a snubber is evaluated via manufacturer input and information.

through consideration of the snubber service conditions and associated installa-tion and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.... ).

The requirement to monitor the snubber service life is included to ensure that the

,CALVERT CLIFFS - UNIT 2 B 3/4 7-5 Amendment No. 4 6 J

PLANT SYSTEMS BASES snubbers periodically undergo a performance evaluation in view of their age and operating conditions. The service life program is designed to uniquely reflect the conditions at Calvert Cliffs. The criteria for evaluating service life shall be determined, and documented, by the licensee.

Records will provide statistical bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not' intended to

. affect plant operation.

3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

3/4.7.10 WATERTIGHT DOORS Thi,s specification is provided to ensure the protection of safety related equip-ment from the effects of water or steam escaping from ruptured pipes or components in adjoining rooms.

3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.

The fire suppression system consists of the water system, spray and/or sprinklers, Halon and fire hose stations.

The collective capability of the fire suppres-sion systems is adequate to minimize potential damage to safety related equip-ment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

Where a continuous fire watch is required in lieu of fire protection equipment and habitability due to htat or radiation is a concern, the fire watch should be stationed in a habitable area as close as possible to the inoperable equip-ment.

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Commission provides for prompt evaluation.of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

CALVERT CLIFFS - UNIT 2 B 3/4 7-6 Amendment No. JJ, A3,4 6

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l ADMINISTRATIVE CONTROLS I

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

Records and logs of facility operaf. ion covering time interval a.

at each power level.

b.

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

i c.

All REPORTABLE OCCURRENCES submitted to the Commission.

i d.

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

i Records of reactor tests and experiments.

e.

i

. f.

Records of changes made to Op:erating Procedures.

g.

Records of radioactive shipments.

h.

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

i.

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

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

Records and drawing changes reflecting facility design modifi-a.

cations made to systems and equipment described in the Final Safety Analysis Report.

b.

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

i Records of facility radiation and contamination surveys.

c.

i i

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

(

ADf4IllISTRATIVE CONTROLS d.

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

e.

Records of gaseous and liquid radioactive material released 'to

{

the environs.

f.

Records of transient or operational cycles for those facility compone1ts identified in Table 5.7.1.

g.

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

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities identified in the NRC

. approved QA tianual as lifetime records.

j.

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

k.

. Records of meetings of the POSRC and the OSSRC.

1.

Records of Environmental Qualification which are covered under the provisiens of paragraph 6.13.

m.

Records of the service lives of all snubbers listed on Table 3.7-4 including the date at which the service life cgmences and associated installation and maintenance records.

6.11 RADIATIOri PROTECTION PP,0GRA*t Procedures for personnel radiation protection shall be p epared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

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

a.

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

CALVERT CLIFFS - UNIT 2 6-20 Amendment No. 4 6

ML20039G912

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