Text

Proposed Tech Specs Changing Limiting Conditions for Operation,Including Deletion of Ref to Containment Purge Isolation Valve Mode 5 Applicability in Operability Table 3.3-3 for ESFAS Instrumentation
	ML20209E621
Person / Time
Site:	Calvert Cliffs
Issue date:	06/28/1985
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20209E618	List: ML20209E613; ML20209E621;
References
	NUDOCS 8507120037
	Download: ML20209E621 (42)
	v • d • e

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s . .

s INDEX ADMINISTRATIVE CONTROLS .

PAGE SECTION_

6-12 6.6 REPORTABLE EVENT ACTI0N_....................................

6-13 6.7 SAFETY LIMIT VIOLATION _.....................................

6.8 P ROC E DU RE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6.9 REPORTING REQUIREMENTS 6.9.1 ROUT I N E REP 0 RT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6 - 18 6.9.2 S P EC I AL REP 0 RT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,

' 6- 19 6.10 R ECO RD RET ENT ION _. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6.11 RADI ATION PROTECTION PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . .

6-20 6.12 HIGH PAD I AT I ON AREA _. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 . . . . . . - .

4.1* CN"! E:::::"TAL 0"AliFICAT IO" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6- 21 m Sv 5T EM I NTEGR iTv . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6-22 ha 100iNE M0NiTORiNG.........................................

XVI Amendment flo. 29. Jul. $

CALVERTCLI5FS-UNIT 1 k

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REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS.

LIMhTINGCONDITIONFOROPERATION 3.1.3.3 At least two of the following three CEA position indicator channels shall be OPERABLE for each shutdown and regulating CEA:

a. CEA voltage divider reed switch position indicator channel, capable of determining the absolute CEA position within + 1.75 inches;

b. CEA " Full Out" or " Full In" reed switch position indicator channel, only if the CEA is fully withdrawn or fully inserted, as verified by actuation of the applicable position indicator; and

c. CEA pulse counting position indicator channel.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one CEA per group having its voltage divider reed switch position indicator channel or its_ pulse counting position indicator channel inoperable and the CEA(s) with the inoperable position indicator channel partially inserted, either:

. 1. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a) Restore the inoperable position indicator channel to OPERABLE status, or b) 8e in at least HOT STANDBY, or c) Reduce THERMAL POWER to < 70% of the maximum allowable THERMAL POWER level for The existing Reactor Coolant Pump combination; if negative reactivity . insertion is required to reduce THERMAL POWER, boration shall be used. Operation at or below this reduced THERMAL POWER level may continue provided that within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1) The CEA group (s) with4* the inoperable position indicator l is fully withdrawn while maintaining the withdrawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn position, the " Full Out" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully withdrawn. Subsequent to fully withdrawing this CEA group (s), the THERMAL POWER level may be returned to a level consistent with all other applicable soecifications and operation may continue per Specification 3.1.3.3 above; or

2) The CEA group (s) with the inoperable position indi-cator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level required oy Spectfica-tion 3.1.3.6 and when this CEA group reaches its 'ully

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TABLE 3.3-3 (Continued) -

h ENGINEERED SAFETY FEATURE-ACTUATION SYSTEM INSTIMENTATION

= -

4

.n '_ MINIRM C TOTAL N0. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHAINIELS ~

TO TRIP OPERABLE MODES ACTION .

]

6.

CONTAllt1ENT PURGE -

E VALVES ISOLATION ~

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a. Manual (Purge Valve Control hitches) 2/ Penetration 1/ Penetration 2/Penetrat' ion 6 4 8 l

//

b. Contairunent Radiation -

High Area Monitor 4 2 3 6 8

7. LOSS OF POWER u ,

1 a. 4.16 kv Emergency Bus -

w Undervoltage (Loss of g Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

b. 4.16 kv Emergency Bus Undervoltage (Degraded -

Voltage) 4/ Bus 2/ Bus 3/ Bus l . 2, 3 7*

5 h ## Containment purge valve isolation is also initiated by SIAS (functional units 1.a. 1.b. and 1.c).

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t 8 REACTIVITY C0!-lTP.0L SYSTFJ_:S REG'JLATII:G CEA II:SERTIO:: LI:.:ITS LIMITIliG CO::0! TION FOR OPERATION 3.I.3.6 The regulating CEA grcups shall be limited to the withdra'e:a1 sequence and to the insertion limits sbcwn on Figure 3.1-2 (rcgulating g* g_t CEAs are considered to be fully withdrcwn in accordance with Figure

. when wiuider.;n to at least 129.0 inches) with CEA insertien t.et'.:ecn I ipt.ie Long Ter . Steady State Insertion Limits and the Trar.sient Insertion Limits restricted to:

a. 1 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months por 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval,

b. 1 5 Effective Full Power Days per 30 Effective Full Power 0;y interval, and

. c. 1 14 Effective Full Po.:er Days per calendar year.

APPLICABILITY: MODES 1* and 2*#.

ACTIO!!:

a. With the ' regulating CEA groups inserted beyond tFe Transient Insertion Limits, except for surveillence testing pursuant to Specification 4.1.3.1.2, itithin two incurs either:

1. Restore the regulating CEA groups to within the limits, or

2. Reduce THEi'J'AL PC'.lER tn less than or equal to that frccticn of RATED Ti!&'R AL PO'.!ER v.hich is allowed by th'e CEA group position using th:. 250/: Fipe 3.P2.} I

b. With the regulating CEA croups insertt.d between the Long Te c.

Steacy State Insertion Limi:s and the Transient Insertien l

Limits for intervals > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 2a hour interval, excep:

during operations pursuant to the provisicns of I.C710!; its.:s

c. and e. of Specification 3.1.3.1, craration may procceo provided either:

1. The Short Term Steady State Insertion Limits of Figure 3.1-2 are not exceeded, or 1

2. Any subsequent increase in THER.'U,L P0'.!ER is restricted to 1 5% of RATED T!!ERt'.AL PC':ER per hour.

i Se:e Special Test Excepticns 3.10.2 and 3.10.4 i b:ithK,g.,.E,1.0.

C.^.L'.'i.'.T CL I ri S -U"I T 1 3/4 1-25 Amend,taed Mo.

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TABLE 3.3-3 -(Continued)

ACTION 8 - With less than the Minimum Channels OPERABLE, operation may continue provide the containment purge valves are 1 maintained closed.

ACTION 11 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition

. and the Minimum Channels OPERABLE requirement is demonstrated within I hour; one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 'for surveillance testing per Specification 4.3.2.1.

i CALVERT CLIFFS - UNIT 1 3/4 3-16 gg 4g

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REACTOR COOLANT SYSTEMS g

,_ SURVEILLANCE REQUIREMENTS (Continued) s I ? b. If the inservice inspection of a steam generator conducted .in l accordance with Table 4.4-2 requires a third sample ipspection i whose results fall _in Category C-3, the inspection frequency shall be reduced to at least once per 20 months. The reduction in inspection frequency shall apply until a subsequent inspection

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demonstrates that a third sample inspection is not required.

c. Additional, unscheduled inservice inspections shall be perfonned on each steam generator in accordance with the first sample r _ _ - . -- n inspection specified in Table 4.4-2 during the shutdown _ subsequent-__ _

to any of the following conditions: ,

1. Primary-to-secondarytubeKleaks(notincludingleaks I originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2,

2. A seismic occurrence greater than the Operating Basis

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Earthquake, , _. __

3. A loss-of-coolant accident requiring actuation; ~

of the-engineered safeguards, or

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4. A main steam line er feedwater line break. ==----__

4.4.5.4 Acceptance Criteria

a. As used in this Specification:

1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing _ indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced cracking, wast _ge,a wear or general corrosion occurring on either inside or outside of a tube.

3. Degraded Tube means a tube'co.ntaining imperfections >20".

of the nominal wall thickness caused by degradation.-

4. % Degradation b ns the percentage of the tube wall thickness affefced or removed by degradation.

. CALVERT CLIFFS - UNIT 1 3/4 4-8 AmeM me.d MO,

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TABLE 3.6-1 (Continued) h CONTAINilENT ISOLATION VALVES M

N PENETRATION ISOLATION ISOLATION VALVE ISOLATION n NO. CHANNEL IDENTIFICATION NO. FUNCTION TIME (SECONDS)

C 4

61 NA SFP-176 Refueling Pool Outlet NA :

NA - '

SFP-174 '

NA ?

NA SFP-172 NA '

E NA SFP-189 NA C ,-~

U (.

62 SIAS A Pil-6579-M0V Containment lleating Outlet <13 >

C 64 NA Pil-376 Containment lleating Inlet NA C 6

g (1) Hanual or remote manual valve which is closed during piant operation.

I ~(2) 11ay be opened below 300 F to establish shutdown cooling flow.

A (3) Containment purge and containment vent isolation valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 and TS 3/4 6.1.8, respectively.

May be open on an intermittent basis under adminiktrative control.

- Containment purge isolation valves isolation times will only apply fer " anes 5 and 5 der %g y ,6fcb time there valves may be epened. Isolation time for contal nt purge and containment g vent isolation valves is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1 and TS 3/4 6.1.8, g respectively, during which time these valves must remain closed.

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i PLANT SYSTEMS HALON SYSTEMS.

LIMITING CONDITION FOR OPERATION 3.7.11.3. The fallowing Halon systems shall be OPERABLE with the storage tanks having at least 95% of full charge weight (or level) and 90% of full charge pressure.

a. Cable spreading rooms total flood system, and associated vertical cable chase IC, Unit 1.

b. 4 G volt switchgear rooms 27 & 45' elevation Unit 1. l -

APPLICABILITY: Whenever equipment protected by the Halon system is required to be OPERABLE.

ACTION:

a. With both the primary and backup Halon systems protecting the areas inoperable, within one hour establish an hourly fire watch with backup fire suppression equipment for those areas protected by the inoperable Halon system. Restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 wfthin the next 30 days outlining the action taken, the cause of the inoperabil-ity and the plans and schedule for restoring the system to CPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.3 Each of the above required Halon systems shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual,

! power operated or automatic) in the flow path is in its correct

, position.

b. At least once per 6 months by verifying Halon storage tank weight (level) and pressure.

c. At least once per 12 months by performing a visual inspection of l the nozzle (s) and visible flow paths for obstructions,

d. At least once per 18 months by verifying the system, including ~

! associated ventilation dampers and fire door release mechanisms, l

actuates manually arid automatically, up~on receipt of a simulated l

actuation signal, and

e. Following completion of major maintenance or modifications on the system (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by perfonnance of a flow test l

through headers and nozzles to assure no blockage.

CALVERT CLIFFS - UNIT 1 3/4 7-72 Amendment No.

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ELECTRICAL P0'WER SiSTEMS i

SURVEILLAt:CE REGUIREMENTS (Continued) '

c. At least once per la months by verifying that:

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

2.

i The cell-to-cell and terminal connections are clean, tight, and

.I coa ted with anti-corrosion ma terial .

d.

At least once per 18 months by verifying that the battery capacity,

, with the charger disconnected, is adequate to either:

i II 1. Supply and maintain in OPERABLE status all of the actual l 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

> 104 volts:

- lor a) Batteries 11, 21 and Reserve:

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} First minute > 827 amperes l! tiext 1 minute > 461 amperes flext 117 minutes > 251 amperes ,.~

l tiext I minute > 325 amperes

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1,.: - c., c) th% 12. q 2.14 First minute > M amperes p,m , m, A 2 2. 6 L A P

' ilext 119 minutes > W amperes , ,a ,gg4 I

' 89S

t the completion of this battery test, the bat ery charger *

' snall be demonstrated capatie of recnarging tre battery at a rate of < 400 amperes while supplying normal 0. C. loads. The

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battery shall be charged to at least 9C% ca acity in < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . _

e-At least once per 50 montns by verifying that the battery capacity I, is at least 80% of the manufacturer's rating when subjected to a {

Ii performance discnarge test. This performance discharge test shall-I be performed subsequent to the satisfactcry completion of the ~

required battery service test.

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'Not applicable to trre charger associated with the Reserve Battery.

CALVERT CLIFFS - UtlIT 1 3/4 S-10 bendmenc No. 30, JA, gg '

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I REFUELING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum o'f four bolts, g ,

b. A minimum of one door in each airlock is closed, and k

c. Each penetration providing dir'ect access from the containment atmosphere to the outside atmosphere shall be either:

1. Closed by an isolation valve. blind flange, or manual valve, or

2. Be capable of being closed by an OPERABLE automatic ,

containment purge valve. !

APPLICA3ILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment. :

ACTION: !

With the requirements o'f the above specification not satisfied, immedi-ately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.9.4 Each of the above required containment penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge valve within-72 hours prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment by:

a. Verifying the penetrations are in their closed / isolated condition, or

b. Testing the containment purge valves per the applicable portions of Specification 4.6.4.1.2.

$ h en v.ox.y EM PL M M M u q CLes M Mut is M AufmSd MUMMNT M CALVERT CLIFFS - UNIT 1 3/4 9-4 *#^'*"***

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REFUELING OPERATIONS SPENT FUEL P00L WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11 As a minimum, 21h feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.

ACTION:

With the requirement of the specification not satisfied, suspend all +

movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The provisions of Specification 3.0.3 are not applicable.

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SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the;fwe4rs pent fuel pool. l CALVERT CLIFFS - UNIT 1 3/4 9-11 [gg3end33eni- 6)o,

'SPECIAL TEST EXCEPTIONS i N COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.10.5 The reactor coolant circulation requirements of Soecification 3.4.1 may

'be suspended and all reactor coolant pumps and shutdown cooling ; umps may be de-energized during the time intervals required 1) for local leak este . testing of containment penetration number 41 pursuant to the requirements of Specifi:a-tion d.5.1.2 d and 2) to permit maintenance on varves located in the ::mmon inctdo. n cooling suctien line 'or on the shutdown cooling flow control valve l Ma #(CV-305) provided:

~

a. No operations are permitted which could cau.se dilution of the reactor coolar.t system boron concentration, and specifically, the charging pumps shall. be de-energized and the cnarging flow paths shall be closec,

b. The xenon. reactivity is < 0.1" ak/k and is approachi-.g stability, and

' c. The, SHUTDOWN MARGIN requirement of Specification 3.1.1.2 is verified at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when no shutdown cooling or reactor coolant pumps are in operation.

MODES 4 and 5.

APPLICABILITY: ,

ACTION:

With the requirements of the above specification not satisfied, suspend all l

operations involving local leak rate testing of containment ;enetration number 41, maintenance on valves located in the common shutdcwn cooling i suction line, and maintenance on valve CV-306.

l SURVEILLANCE RE0'UIREMENTS L gr I

4.10.5.1 The charging pumps shall be verified d; ;n:c;i;;d and the charging l flow paths shall be verified closed at least once per hour.

ren 4.1'O . 5 . 2 The reactivity shall be determined to be < 0.1" ak/k and l approaching stability within i hour prior to suspending reactor coolant ci rcula tion. , _

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3/i 10-5 .4:endmen: No.

CALVERT CLIFFS - UNIT 1 l r

REACTIVITY' CONTROL SYSTEMS BASES The baron capability required below 200*F is based upon providing a 3% ak/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140*F. This condition requires either 737 gallons of 7.25% boric acid solution from the boric acid tanks or 9,844 gallons of 2300 ppm borated water from the refueling water tank.

The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the' original criteria are met.

The ACTION statements applicable to a stuck or untrippable CEA and to a large misalignment (> 15 inches) of two or more CEAs, require a prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUT-DOWN MARGIN.

For small misalignments (< 15 inches) of the CEAs, there is 1) a l small degradation in the peakin'g factors relative to those assumed in l generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a l

small effect on the time dependent long term power distributions rela-tive to those used in generating LCOs and LSSS setpoints for DNBR and linear heat' rate, 3) a small effect on the available SHUTDOWN MARGIN, i and 4) a small effect on the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated with the small misalignment of a CEA permits a one hour time interval during which

! attempts may be made to restore the CEA to within its alignment require-ments prior to initiating a reduction in THERMAL POWER. The one hour time limit is Oxf'icicnt to (1) identify causes of a misaligned CEA, (2) take appropriathorrective action to realign the CEAs and (3) minimize

, the effects of Aenon redistribution.

l Gdficht]

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

1

r

. , . l REFUELING OPERATIONS -

1 BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The_ minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM The. limitations on the spent fuel pool ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

3/4.9.13 SPENT FUEL CASK HANGLING CRANE The restriction on movement of the spent fuel shipping cask within

! one cask length of any fuel assembly ensures that in the event this load is dropped (1) the. stored spent fuel assemblies will not be damaged, and (2) any possible distortion of fuel in the storage racks will not result a critical array. -

l 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES The OPERABILITY and closure restrictions on the containment vent isolation valves are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressuriza-i tion potential while in the REFUELING MODE.

CALVERT CLIFFS - UNIT 1 B 3/4 9-3 Amendment No.

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

The intent of the orig;ni;l procedure is not altered. l a.

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

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

-+ .

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the followi,nq reports shall be submitted.

to the Director _of the Regional Office of Inspection and Enforcement

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unless otherwise noted. -

.~ _

STARTUP REPORT ,-

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

(3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may

' have significantly altered the nuclear, thermal, or hydraulic perfor-

' mance of the plant.

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

- of the operating conditions or characteristics obtained during the test l-program and a comparison of these values with design oredictions and l

specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific l details required in license conditions based on other commitments shall be included in this report, r

l 6-14 Amendment No.

CALVERT CLIFFS - UNIT 1 s

L _ . . ~ .

a ,

ADMINISTRATIVE CONTROLS

b. A high radiation area in whien tne 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 maintair.ed by the Supervisor-Radiation Control and the Operations Shift Supervisor on duty under their separate administrative control .

6 h ENVIRONMENTAL QUALIFICATION 6.13.1 Sy later than o'une 30, 1982 all safety-related elect al eculp-ment in the fac i ty shall be qualified in accordance with) provisions of: Division of Op ting Reactors " Guidelines for Ev d ting Environmental Qualification of Class lectrical Equipment in rating Reactors" (DOR Guidelines); or NUREG-0588 . erim Staff Posi*' n 'on Environmental Qualification of Safety-Related ctrical ~ uipment", December 1979.

Copies of these documents are attac Order for Modification of Licenses DPR-53 and DPR-69 dated ober ,1980.

6.13.2 By no later than ember 1, 1980, camp and auditable records must be available an intained at a central locat1 which describe the environmental qu

ication method used for all safety-r ted electrical l equipment in ficient detail to document the degree of comalQnce with the 00R elines or NUREG-0583. Thereaf ter, sucn records shouh aeg upda and maintained current as equipment is reolaced, further tess otherwise further qualified.

4r44- SYSTEM INTEGRITY .

The licensee shall implement a program to reduce leakage from systems outside containment that would or could centain highly radioactive fluids during a

, serious transient or accident to as low as practical levels. This program shall include the following:

3

1. Provisions establishing preventive maintenance anc sericcic visual inspection requirements, and

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

4 .

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ll CALVERT CLIFFS - UNIT 1 5-21 Jfdet 10/24/204//ml/334 Amendment No.,76 L'

ADMINISTRATIVE CONTROLS O

4-M- IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately detennine 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 ecui;; men:.

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1 CALVERT CLIFFS - UNIT I 6-22 AmendmentNo.M

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

The O.ief L..-i.;.u u:;l L.gia;;r, Electric Engineering Department, has l th,e direct responsibility to assure compliance with the specifications presented in Sections 3.0 and 4.0.

Director, EnvimomenTa\ $rc3 i

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Calvert Cliffs Unit 1 5.1-1 Amendment No.

Calvert Cliffs Unit 2 Amendment No.

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5'. 3 R;vihv and Audit

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l The Off-Site Safsty and Ravisv Committes as described in Appendix A Tachnical Spaci-I N .

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ficaticus, paragraph b.5, shall be responsible for:

4 .

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1. , Reviewing the results of the Environmental Monitoring Requirements and the Environmental Surveillence and Special Studies as required by the specifi-i cations.

2. Reviewing and approving proposed changes to the Environmental Technical Specifications.

3." Reviewing results of the audits perfor=ed by the Q,uality Assurance Department.

16 . Review of occurrences whica exceed a limiting condition for operation.

The Plant Operations and Safety Review Committee'as described in Appendix A, Specification o.5, shall be responsible for:

'1. Review of the results of any any proposed changes to the specifications ir. Section 2.0 and preparation of a summary report of this review for presen-

~

tation to the Off-Site Safety and Review Committee.

% 2. . Review of proposed changes .or modifications to plant equipment or systems affecting specifications in Section 2.0.

3 Review of operating procedures and changes thereto, for the systems and com-ponents involved in fulfilling specifications in Section 2.0.

(Proyams Vaith The Environmental igi;.nri ; 0;er Electric Engineering Department shall be l responsible for: .

1. Review of the results of any any proposed changes to the specifications in Sections 3.0 and 4.0, and preparation of a su==ary report of this reviev for presentation to tne Off-Site Safety and Review Co=nittee.

2. Review of operating procedures, and changes thereto, for the systems and ccm-ponents involved in fulfilling specifications in Sections 3.0 and k.0.

The Quality Assurance Department snall be responsible for audit of the operating procedures for the systems and components involved in fulfilling the Environmental d Tecnnical Specifications. Significant findings of the audit shall be presented to and reviewed by the Off-Site Safety and Review Consittee.

Amuk.& Mo.

s.3-1

, 5.3- Operating;Prdca.dures

'Q2 syste=s which,are directly involved with the fulfii' e::t of the environmental

[

-inica.l. specifications shall be operated in accordance with approved operating .

procedures.

551 on-Site invironmental Monitori5g Program All vritten openting procedures, and changes thereto, vhich pertain to specifica-tiens in Section 2.0 shall be reviewed by a member of the plant staff a=d approved

> by the ?lant Superintendent ' prior to implementation, except as provided in the following paragraph:

Ts=porary changes to operating procedures which do not change the intent of the original procedure may be made provided such changes are app _mved by two licensed ssnior rete .or operators , one of whom shall be the Shift Supervisor. Such changes shall be docunented and subsequently reviewed by the Plant Operations and Safety Raviev Con:=ittee and approved by the Plant Supe'rintendene.

.2 Off-Site Environmental Monitoring Progrs=s All vritten operating procedures and changes thereto, which pertain to spe * *ica-QPrc cars ua;v tiens in Sections 3 0 and h.0, shall be reviewed by the Envir_ommental _,_ ... .

birecR&ucomutat Yregra m s Cr:g, Electric Engineering Departnent and approved ,te .

igin;;r prior to implementation, except as provided belev:

Tz=porary changes to operating procedures which do not change the intent of the original procedure may be made provided such changes are approved by the project leader as specified in the opera _ ting procedure. Such chan;!;es shall be subsequently raviewed by the Environmental _,_;;;ri=g Cr;q and approved by the ?ict iv. :;_

__..,w Diredor, %Nenwn%\ Pcyrams. ,

Calvert Cliffs Unit 1 5.5-1 Amendment No.

Calvert Cliffs Unit 2 Amendment No.

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PRESIDENT .

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ELECTRIC tilERCDraiECTION ENGINf EHING a Sul W AND OPERATIONS 00t4S fitucilOtt C

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PL ANT SUPERit4TENDEt4T f CHEMICAL EtlGl:4EERING . . .. .. .. .. staff staff

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CALVElli Cliffs j ,

AND TEST . .

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flGullE S.2 - l l MANAGEMENT 04CANIZ ATION CllAlli flEL ATING 10 '

ENVillOt4 MENTAL M AT TERS CALVEflT Clif f S HuCLE Aft POWER PLANT UAL(IMOllE GAS G ELECTulC COMPANY

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.6 CONTAINMENT SYSTEMS _

3/4.6.1 PRIMARY CONTAINMENT Containment Integrity............................... 3/4 6-1 Containment Leakage................................. 3/4 6-2 Containment Air Locks............................... 3/4 6-4 Interna 1' Pressure................................... 3/4 6-6 Air Temperature......................................'3/4 6-7

~

Contai nment S tructural Integri ty. . . . . . . . . . . . . . . . . . . . 3/4 6-8 Containment Purge System............................ 3/4 6-9a Containmen t Vent Sys tem. . . . . . . . . . . . . . . . . . '. . . . . . . . . . . 3/4 6-9b

't 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS '

- Contai nment Spray Sys tem. . . . . . . . . ..s.

. . . . . . . . . . . . . . . 3/4-6-10

~

Containment Cooling System.......................... 3/4 6-12 3/4.6.3 IODINE REMOVAL SYSTEM...............................

3/4 6-13 -

}

3/4.6.4 CONTAINMENT ISOLATION VALVES........................

3/4 6-17 1

3/4.6.5 COMBUSTIBLE GAS CONTROL l t .

Hydrogen Analyzers.................................. 3/4 6-26 I

El ectric Hydrogen Recombiners - W. . . . . . . . . . . . . . . . . . .

3/4 6-27 l

QxHAusT) 3/4 6-28 l 3/4.6.6 PENETRATION ROOM E7"^.USFAIR FILTRATION SYSTEM. .. . . .

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYC'LE Sa fe ty Va 1 ves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 1 Auxili ary Feedwater Sy s tem. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-5 i

~-

~

Condensate Storage Tank . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-6 '

Ac t i v i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 7- 7

.t Main Steam Line Isol ation Valves . . . . . . . . . . . . . . . . . . . . 3/4 7-9 .

S econda ry Wa te r Chemi s try . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 7- 10 CALVERT CLIFFS - UNIT 2 VI a mendment No. /4

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N................................. 6-12 6.7' SAFETY LIMIT VIOLATION.................................. 6-13 6.8 PROCEDURES............................................... 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.......................l............... 6-19 6.11 RADIATION PROTECTION PR0 GRAM........................... 6-20 6.12 HIGH RADIATION AREA.................................... 6-20

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- SvSTEM INTEGRITv....................................... 6-2i

+cM IODINE MONITORING...................................... 6-22 CALVERT CLIFFS - UNIT 2 XVI Amendment No. M, 36, //

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4 REACTIVITY CONTROL SYSTEMS

. POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 At least two of the following three CEA position indicator channels shall be OPERABLE for each shutdown and regulating CEA:

a. CEA voltage divider reed switch position indicator channel, capable of determining the absolute CEA position within + 1.75 inches;

b. CEA " Full Out" or " Full In" reed switch position indicator channel, only if the CEA is fully withdrawn or fully inserted, as verified by actuation of the applicable position indicator; and

c. CEA pulse counting position indicator channel.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one CEA per group having its voltage divider reed switch position . indicator channel or its pulse counting position indicator channel inoperable and the CEA(s) with the inoperable position indicator c:iannel partially inserted, either:

1. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a) Restore the inoperable position indicator channel to

, OPERABLE status, or i

b) Be in at least HOT STANDBY, or c) Reduce THERMAL POWER to < 70% of the maximum allowable THERMAL POWER level for The existing Reactor Coolant Pump combination; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used. Operation I at or below this reduced THERMAL POWER level may continue provided that within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1) The CEA group (s) with4e the inoperable position indicator l is fully withdrawn while maintaining the withdrawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn position, the " Full

Out" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully withdrawn. Subsequent to fully withdrawing this CEA group (s), the THERMAL POWER level may be returned to a

level consistent with all other applicable specifications

and operation may continue per Specification 3.1.3.3 above, ,

i or The CEA gro u (s) with the inoperable position indi-

~

2)

cator is fuli,' inserted, and subsequently maintained

! . fully inserteo while maintaining the withdrawal i

sequence and THCRMAL POWER level required by Specifica-tion 3.1.3.6 and when this CEA group reaches its fully CALVERT CLnffS uAhr 2. Q j.,ql Qgmed )lc.

REACTIVITY C0!; TROL SYSTEMS REG'JLATI?iG CEA I!!SERTI0ft LIMES.

.LIMITIt!G C0!:3ITIO:: FCR OPERATIO 3.1.3.6 The regulating CEA groups shall be limited to the withdrauci sequence and to the insertion lir.its shoiin on Figure 3.1-2 (regulating CEAs are considered to be fully withdra'.tn in accordance witn Figure 3.1-2 when withdrawn to 'at least 129.0 inches) with CEA insertion bet. 3en the Long Tera Steady State Insertion Limits and the Transient Insertion i

Limits restricted to:

a. 1 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hcur interval,

b. 1 5 Effective Full Power Days per 30 Effective Full Power Day interval, and

c. 1 14 Effective Full Po.;;r Days per calendar year.

APPLIC/.BILITY: MODES 1* and 2*!.

ACTION: .

a. With the regulating CEA groups inserted beyond the Transicr.t

- Insertion' Limits, except for surveillance testing pursuar.t to.

Specification 4.1.3.1.2, within two hours either:

1. Restore the regulating CEA groups to within the limits, or

2. Reduce TilEPliAL 'PC'.:ER to less than or .cqual to that frcction of RATED THEF;'AL FC'.!ER which is allo.ted by the CEA group position using th: de : ff piyre. 3,1-2]

l

b. With the regulating CEA groups inserted between the Long Tern Steady State Insertion Limits and the Transient Insertion Limits for intervals > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, except during operations pursuant to the previsions of ACTIO:; itens

c. and e. of Specification 3.1.3.1, operation may procced provided either:

1. The Short Tera Stecdy St:te Insertion Limits of Figure 3.1-2 are not excceded, or

2. Any subsequent increase in TIER".AL PC'.!ER is restricted to 1 5% of RATED T !U.:GL PO'.lER per hour.

w See Special Test Exceptions 3.10.2 and 3.10.4.

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CALVE;T CLIFFS-U::!T 2 3/4 1-25 hce.ndnent ::o.

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TABLE 3.3-3 (Continued)-

. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM '

9 TOTAL NO. CilANNELS CliANNELS APPLICABLE '

h FUNCTIONAL. UNIT OF CilANNil S TO TRIP OPERABLE MODES ACTION n 6. CONTAINNENT PURGE n -

[n VALVES ISOLATION ## ,

5 a. Manual (Purge Valve g i

Control Switches) 2/ Penetration 1/Penetra tion 2/ Penetration jl/6 8 E

q b. Containment Radiation -

m liigh .

Area Monitor 4 2 3 6 8

{ 7. LOSS OF POWER .

f, a. 4.16 kv Onergency Bus u Undervoltage (Loss of Voltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

b. 4.16 kv Emergency Bus

-Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

b' g ## Containment purge valve isolation is also initiated by SIAS (functional units 1.a.1.b and 1.c).

g =

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TABLE 3.3-3 (Continued)

ACTION 8 -

With less than the' Minimum Channels OPERABLE, operation may continue provide the containment purge valves are l maintained closed. -

ACTION 11 - With the number of OPERABLE Channels one less than the Total. Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

1 5

4 CALVERT CLIFFS - UNIT 2 3/4 3-16 Amendment No. 2I

TABLE 3.3-10 -

j] POST-ACCIDENT MONITORING INSTRUMENTATION h

n h".,"/, *"D Locd or ar $h$ N$S OPERABLE l r . . . , , . . _ . . . .

4; v ,

ul 1. Containment Pressure 2 c: 2. Wide Range Logarithmic Neutron Flux Monitor 2 5

3. Reactor Coolant Outlet Temperature 2

{l ,

4. Pressurizer Pressure 2

5. Pressurizer Level 2

6. Steam Generator Pressure 2/ steam' generator

7. Steam Generator Level (Wide Range) 2/ steam generator R

8. Auxiliary Feedwater Flow Rate 2/ steam generator Y

is 9. RCS Subcooled Margin Monitor 1

10. PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve -

?T 11. PORV Solenoid Power Indication 1/ valve R- 12. Feedwater Flow 2 r

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t REACTOR COOLANT SYSTEMS ! ! .

SURVEILLANCE REQUIREMENTS (Continued)

b. If the inservice inspection of a steam generator conducted in l accordance with Table 4.4-2 requires a third sample inspection l whose results fall in Category C-3, the inspection frequency ;

shall be reduced to at least once per 20 months. The reduction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.

c. Additional, unscheduled inservice inspections shall be performed

' on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the, shutdown subsequent to any of the following conditions:

1. Primary-to-se'condary tube)( leaks (not including leaks l originating from tube-to-tube sheet welds) in excess of

the limits of Specification 3.4.6.2,

2. A seismic occurrence greater than the Operating Basis Earthquake,

3. A loss-of-coolant accident requiring actuation of the engineered safeguards, or 4 A main steam line or feedwater line break.

4.4.5.4 Acceptance Criteria

a. As used in this Specification:

1. Imperfection means an exception to the dimensions, finish or contour of a tube from that regired by fabrication drawings or specifications. Eddy-c arrent testing indications below 20". of the nominal tube wall thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

3. Degraded Tube means a tube cont'aining imperfections >20".

of the nominal wall thickness caused by degradation.

4 " Degradation means the percentage of the tube wall tnickness affected or removed by degradation.

4 CALVERT CLIFFS-UtlIT 2 3/4 4-8 @und%t Mo,

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TABLE 3.6-1 (Continued) -

9 CONTAINitENT ISOLATION VALVES E

EF PENETRATION ISOLATION ISOLATION VALVE ISOLATION NO. CilANNEL IDENTIFICATION NO. FUNCTION TIME _(SECONDS)

M 61 NA SFP-184 Refueling Pool Outlet '

NA 7 U! NA SFP-182 - '

' NA c

. NA SFP-180 '

NA c c NA SFP-186 '

NA c s

-7 62 SIAS A PH-6579-MOV Containment lleating outlet <13

_ n -

64 NA PH-387 Containment lleating Inlet NA (1) Manual or remote manual valve which is closed during' plant operation. '

I (2) May be opened below 300*F to establish shutdown cooling flow.

a (3) Containment-purge and containment vent isolation valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 and TS 3/4 6.1.8, respectively.

May be open on an intermittent basis under adminiktrative control.

- Containment purge isolation valves isolation times will' only applygfar WES S =ad 6 d" iag uhich

i -

k -, o on o , ..m o so one==d Isolation time for containment pulrge and containment vent isola-

[ tion valves is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 and TS 3/4 6.1.8, respectively, during g which time these ' valves must remain closed.

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l 'l 8 3/4.7 PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE . ._. _ .

SAFETY VALVES T-- ?-1_: -~. Z T Z Z LIMITING CONDITION FOR OPERATION

3. 7 .1.1 All main steam line code safety valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the' Power Level-High trip set-

~

point is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ,

-- b. .With one reactor coolant loop and associated steam generator in operation and with one or more main steam line code safety valves associated with the operating steam generator inoperable, operation in MODES 1, 2 and 3 may proceed provided:

1. That at least 2 main steam lire code safety valves on the non-operating steam generator are OPERABLE, and

2. That within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint.is reduced per Table 3.7-2; otherwise, be in at least 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 .

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. 7 .1.1 No additional Surveillance Requirements other than those required code safety l by Specification 4.0.5 are applicable for the main steam valves of Table 4.7-1. g, CALVERT CLIFFS-UNIT 2 3/4 7-1 y p g,

PLANT SYSTEMS .

AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

Qubs~pite4

c. Whenever a sybsystr (consisting of one pump, piping, valves and I controls in the direct flow path) required for operability is in-operable for the perfonnance of periodic testing (e.g. manual discharge valve closed for pump Total Dynamic Head test) a dedicated operator will be stationed at the local station with direct communica-tion to the Control Room. Upon completion of any testing, the sub-system required for operability will be returned to its proper status and verified in its proper status by an independent operator check.

d. The requirements of- Specification 3.0.4 are not applicable whenever one motor and one steam-driven pump (or two steam-driven pumps) are aligned for automatic flow initiation.

~ . . . ,

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater flowpath shall be demonstrated OPERABLE:

j a. At least once per 31 days by:

1. Verifying that each steam driven umpr develops a Total Dynamic Head of > 2800 ft. on recirculation flow. (If verification must be demonTtrated during startup, surveillance testing shall be perfonned upon achieving an RCS temperature

> 3000F and prior to entering MODE 1).

2 ., Verifying that the motor driven pump develops a Total Dynamic Head of > 3100 ft. on recirculation flow.

3. Cycling each testable, remote operated valve that is not in its operating position through at least one complete cycle.

4. Verifying that each valve (manual, power operated or autcmatic in the direct flow path is in its correct position.

b. Before entering MODE 3 after a COLD SHUTOOWN of at least 14 days by completing a flow test that verifies the flow path frcm the conden-sate storage tank to the steam generators. ,

c. .At least once per 18 months by:

1. Verifying that each autcmatic valve in the flow path actuates to its correct position-(varification of flow-modulating characteristics not required) and each auxiliary feedwater pump automatically starts upon receipt of each AFAS test signal, and

2. Verifying that the auxiliary feedwater system is capable of providing a minimum of 2C0 gpm nominal flow to each flow leg.

CALVEKT CVTFS. - uAM 2 3l+ 7-Ecr Auen L ent bio.

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PLANT SYSTEMS HALON SY' STEMS ,

LIMITING CONDITION FOR OPERATION 3.7.11.3 The following Halon systems shall be OPERABLE with the storage tanks having at least 95% of full charge weight (or level) and 90% of full charge' pressure.

a. Cable spreading rooms total flood system, and associated vertical Q4t@ cable chase IC, Unit 2. I

b. 460- volt switchgear rooms 27 & 45' elevation Unit 2. l APPLICABILITY: Whenever equipment protected by the Halon system is required to ba30PERABLE.

ACTIb5:

a. With both the primary and backup Halon systems protecting the areas inoperable, within one hour establish an hourly fire watch with backup fire suppression equipment for those areas protected by the inoperable Halon system. Restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the l Commission pursuant to Specification 6.9.2 wit'hin the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

l b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS 4.7.11.3 Each of the above required Halon systems shall be demonstrated OPERABLE:

.a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position. -

b. i At least once per 6 months by verifying Halon storage tank weight

.(level)andpressure. '

c. At least once per 12 months by per471g a visual inspection of the nozzle (s) and visible flov pc 4 6 obstructions.

d. At least once per 18 months by erity t.x,) the system, including associated ventilation dampers and fire door release mechanisms, actuates manually and automatically, upon receipt of a simulated actuation signal, and

e. Following completion of major maintenance or modifications on the system (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by performance of a flow test through headers and nozzles to assure no blockage.

CALVERT CLIFFS - UNIT 2 3/4 7-64 Amendment No.

o

e ELECTRICAL POWER SYSTEMS SUR'IEILLANCE 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 .vi th anti-corrosion ma terial .

{

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 CPERABLE status all of the actual emergency leads 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 i

l 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months while maintaining the battery terminal voltage

> 4M-vol ts :

105-1 i

a) Batteries 11, 21 and Reserve:

{

t First minute > 827 amperes

~

Next 1 minute > 461 amperes Next 117 minutes > 251 amperes Next 1 minute > 325 amperes b)

W"'^^ ,2 i 6: c.

Oka % 11 284 First minute > M amperes F.* ~ A 2 2.S' A P

.)-- n 6 Ap Next 119 mnuter > EiG amperes

~ E95 7 At the ccmpletion of this battery test, the battery charger *

' shall be demonstrated capable of recnarging the Dattery at a rate of 1 400 amperes while supplying normal D. C. loads. The battery shall be charged to at least 95% capacity in 124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months .

e.

At least once per 60 months by verifying that the battery capacity j 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 comp 1.etion of the required battery service test.

Not applicable to the charger associated with the Reserve Battery.

CALVERT CLIFFS - UNIT 2 3/4 8-10 Amendment No.22, 4 , gg ,

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'^', REFUELING OPERATIONS g

CONTAINMENT PENETRATIONS 5

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z 3.9.4 The containment penetrations shall be in the following status: [.j

a. The equipment door closed and held in place by a minimum of four bolts, h

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g i 5 A minimum of one door in each airlock is closed, and I Ei

c. Each penetration providing direct access from the containment 5

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, atmosphere to the outside atmosphere shall be either: !

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1. Closed by an isolation valve, blind flange, or manual valve, or g

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Be capable of being closed by an OPERABLE automatic containment purge valve. @

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f; APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel ;,;g h L ' within the containment. ~

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~n With the requirements of the above specification not satisfied, immedi- _EE ately suspend all operations involving CORE ALTERATIONS or movement of E0 irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable. ! =E E,

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SURVEILLANCE REQUIREMENTS f.]

E E4 4.9.4 Each of the above required containment penetrations shall be determined to be either in its closed / isolated condition or capable of =

being closed by an OPERABLE automatic containment purge valve within 72 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months prior to the start of and at least once per 7 days during CORE E ALTERATIONS or movement of irradiated fuel in the containment by: 5 E

a. Verifying the penet: <. Sos are in their closed / isolated E condition, or E 5

b. Testing the containment purge valves per the applicable _ . . . [?

portions of Specification 4.6.4.1.2. g52

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CALVERT CLIFFS - UNIT 2. 3/4 9-4 E l

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RE; SPENT FUEL P0OL WATER LEVEL ==

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LIMITING CONDITION FOR OPERATION Es;

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3.9.11 As a minimum, 21h feet of water shall be maintained over the top !!$

of irradiated fuel assemblies seated in the storage racks. 5~i

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APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel Mjj(.;

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ACTION: E 55 With the requirement of the specification not satisfied, suspend all E=

movement of fuel assemblies and crane operations with loads in the fuel [15 storage areas and restore the water level to within its limit within 4 EE hours. The provisions of Specification 3.0.3.are not applicable. @

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SURVEILLANCE REQUIREMENTS Fr:

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l 4.9.11 The water level. in the spent fuel pool shall be determined to be at EE

! least its miniinum required depth at least once per 7 days when irradiated .:::::

fuel assemblies are in the .5we4- spent -fuel pool. l M

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CALVERT; CLIFFS - UNIT 2 3/4 9-11 Q%d Me, Eil t;-

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SPECIAL TEST EXCEPTIONS C00LANTDIRCULATION ,

LIMITING CONDITION FOR OPERATION TZ WUPThe. reactor coolant circulation requirements' of Specification 3.4.1 may be suspended and all reactor coolant pumps and shutdown cooling pumps may be de-energized during the time intervals required .1) for local leak rate testing of containment penetration number 41 pursuant to the requirements of Specifica-tion 4.6.1.2.d and 2) to permit maintenance on valves located in the common A '

Thetde cooling suction line or on the shutdown cooling flow control valve l~

(CV-306) provided: .

a. No operations are permitted which could cause dilutio.n of ,-

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the reactor coolant system boron concentra. tion, and specifically, the charging pumps shall be de-energized and the charging flow paths shal'1 be closed, ,

. b. The xenon reactivity is 10.1% ak/k and is approaching stab'ility, and

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c. The SHUTOOWN MARGIN requirement. of Specification 3.1 l .2 is verified at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when no shutdown cooling or reactor coolant pumps are in operation. -

APPLICABILITY: MODES 4 and 5.

,r ACTIO'N :

-- With-theJequirements of the above specification not satisfied, suspend all operations involving local leak rate testing of containment penetration number 41, maintenance on valves located in the common shutdown cooling suction line, and maintenance on valve CV-306.

SURVEILLANCE REQUIREMENTS

T f

h 4.10.5.1 The charging pumps shall be verified d; :n:rgi::d and the charging l flow paths shall be verified closed at least once per hour. -

M 4.10.5.2 The sdbe reactivity shall be determined to be < 0.1% ak/k and l approaching stability within i hour prior to suspending Teactor coolant circulation. . .

1 CALVERT CLIFFS - UNIT 2 3/4 10-5 Amendment No.

REFUELING OPERATIONS BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to renove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM The limitations on the spent fuel pool ventilation system ensure that all radioactive maMial released from an irradiated fuel assembly .

will be filtered thrbugh the HEPA filters and charcoal adsorber prior to

discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine ranoval capacity are consistent with the assumptions of the accident analyses.

3/4.9.13 SPENT FUEL CASK HANDLING CRANE The restriction on movement of the spent fuel shipping cask within one cask length of any fuel assembly ensures that in the event this load is dropped (1) the stored spent fuel assemblies will not be damaged, '

and (2) any possible distortion of fuel in the storage racks will not

- _ . resul t acri(icalarray. l

+1 s.. -

31 j 3/4.9.1 CONTAINMENT VENT ISOLATION VALVES The OPERABILITY and closure restrictions on the containment vent isolation valves are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressuriza-tion potential while in the REFUELING MODE.

l l

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

l

'*a _

, ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and abalysis of the plant for transients and accidents. -

6.4 TRAINING' ,

ggy 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervis~or - Training and Technical Services for the Nuclear Power Department and the General Fcan for l the Production Maintenance Department and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55, as applicable.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.

6.5 REVIEW AND AUDIT 6.5.1 ; PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) h FUNCTION 6.5.1.1 The POSRC shall function to advise the Plant Superintendent on all matters related to nuclear safety. -

COMPOSITION 6.5.1.2 The POSRC shall be composed of the:

Chairman: Plant Superintendent Member: General Supervisor - Operations Member: General Supervisor - Electrical and ContFols Member: General Supervisor - Chemistry -

tiember: Principal Engineer - Plant Engineering Nuclear i Member: General Supervisor - Maintenance and Modifications ~ ;

l Member: Principal Engineer - Incore Fuel Management ~

Member: General Supervisor - Radiation Safety ~

l Member: General Supervisor - Training and Technical Services ALTERNATES l 6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates j shall participate as voting members in POSRC activities at any one time.

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CALVERT CLIFFS - UNIT 2 6-6 Amendment No.

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

vided:

. a. The intent of the origim:1 procedure is not altered. l

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

c. The change is documente.d, reviewed by the POSRC and aooroved by the Plant Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREMENTS .

ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code o'f Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement -

unless otherwise noted. .

STARTUP REPORT _ ..

6. 9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu- .,

factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and s peci fications . Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

l CALVERT CLIFFS - UNIT 2 6-14 AmendmentNo.['

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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 and the Operations Shift Supervisor on duty under their separate administrative control.

h ENVIRONMENTAL QUALIFICATION 6.13.1 By later than June 30, 1982 all safety-related electr ca equip-ment in the fa ity shall be qualified in accordance with t rovisions of:

Oivision of Operat Reactors " Guidelines for Evaluatin fronmental Electrical Equipment in Op ing Reactors" (00R Qualification of Class on Environmental Guidelines); or NUREG-0588 terim Staff Positi Qualification of Safety-Relate lectrical pment", December 1979.

Copies of these documents are atta rder for Modification of Licenses OPR-53 and OPR-69 dated October 24, 6.13.2 By no later than De . er 1,1980, com te andwhich auditable records describe the must be available and ained at a central loca

environmental quali ation method used for all , safety- lated electrical equipment in s cient detail to document the degree of c liance with ines or NUREG-0588. Thereafter, such records sh be the 00R Gui update d maintained current as equipment is replaced, further te

d, or envise f"urther qualified.

6-M 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 nbt to exceed refueling cycle intervals. l l

4 CALVERT CLIFFS - UNIT 2 6-21 Orddf/J9/2f/804 Amendment 33 D

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ADMINISTRATIVE CONTROLS IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas us. der accident conditions. This program shall include the fellowing:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

CALVERT CLIFFS-UNIT 2 6-22 Amendment No. )#

._ . ._. . .

ML20209E621

Text

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