Text

Amends 128 & 110 to Licenses DPR-53 & DPR-69,respectively, Changing Surveillance Interval for Listed Tech Specs Surveillance Requirements Generally Performed During Refueling to 24 Months
	ML20236M049
Person / Time
Site:	Calvert Cliffs ; (DPR-53-A-128, DPR-69-A-110)
Issue date:	11/03/1987
From:	Capra R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20236M053	List: ML20236M049; ML20236M064;
References
	NUDOCS 8711120021
	Download: ML20236M049 (61)
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UNITED STATES i 31

. NUCLEAR REGULATORY COMMISSION

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, ASHINGTON, D. C. 20555.

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BALTIMORE GAS'AND1 ELECTRIC COMPANY.'

DOCKET NO.,50-317

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CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 l

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~ AMENDMENT TO FACILITY OPERATING ~ LICENSE-

1

. Amendment No.1128i License No. DPR-53

~

1.

The Nuclear Regulatory Commission:(the Commission)_.hasLfound that:-

1 A.

The applications for amendment by Baltimore Gas and Electric Company..

]

(the licensee). dated July 31, October 17 and No' ember 24, 1986,'as v

supplemented on January.12.- February 23, March 24, April 3,'and -

1 June 29, 1987, comply with the standards. and re i

Atomic Energy-Act of 1954, as amended (the Act)quirements'of the' and the Commission's 1

rules and regulations set forth in'10 CFR Chapter I;

]

B.

The facility will. operate in conformity with the: application, the provisions of the Act, and the rules and. regulations of the 1

~ Commission;:

J 1

C.

There is reasonable _ assurance?(1) that the activities. authorized

i by this amendment can be conducted without endangering the healthJ j

and safety of the public,'and (ii)1thattsuch activities Will.be conducted in~ compliance with~the Commission's regulations; D.

The issuance of this amendment Will not betinimical.to the common defense and security 'or to the health and-safety of Lthe public;-

and E.

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

have been satisfied.

2.

Accordingly, the license is amended by changes t'o the Technical.'

Specifications as_ indicated in the attachment to this license amendment, and paragraph 2.C.(2) 'of Facility Operating License i

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

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8711120021 871103 PDR ADOCK 05000317 1

P PDRi 1

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( -(2) Technical Specifications The' Technical' Specifications contained in Appendices.

f A and B.. as. revised through Amendment No.128, 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 to be implemented within 30 days.

]

FOR THE NUCLEAR REGULATORY COMMISSION

%L :t O.. Cy 0

Robert A. Capra, Acting Director Project Directorate.I-1 Division of Reactor Projects I/II'

Attachment:

y Changes to the Technical Specifications Date of Issuance: November 3, 1987 I

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. UNITED s7ATES -

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NUCLEAR REGULATORY COMMISSION -

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' WASHINGTON, D. C. 2055!. -

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BALTIMORE GAS AND'SLECTRIC COMPANY' 1 DOCKET'NO.- 50-318 1~

CALVERT' CLIFFS NUCLEAR POWER PLANT, UNIT:1-j

1 l-AMENDMENT TO FACILITY OPERATING LICENSE

-Amendment No'.110 l.

l License No. DPR-69

\\

1.

The Nuclear Regulatory Comission (the' Comission) has, found that:

A.

The applications for amendment by Baltimore Gas and Electric. Company (the licensee) dated July 31,-October 17 and' November 24, 1986, as q

supplemented January 12, February 23, March 24, April;3,'and JuneL29,3 1987, comply with the standards.and requirements of the Atomic Energy.

Act of.1954,'as' amended (the Act) and the Commission's rules and:

1 regulations set forth in 10 CFR Chapter I;'

B.

The facility will operate in conformity.with the application, 4

the provisions of-the'Act, and the rules and regulations of the Comission; p

C.

Thereisreasonableassurance.(1)that'the' activities'euthorized-by this amendment can' be conducted without endangering the health i

and safety of the public, and (ii) that such activities 1will be.

1 conducted in compliance 'with the Comission's regulations; D.

The issuance of this amendment will not be inimical to'the common l

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

l.

and i

E.

The issuance,0f this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all~ applicable requirements -

have been satisfied.

j' 2.

Accordingly, the license'is amended by changes to the Technical

s

. Specifications as indicated in the attachment' to this license -

1 amendment, and paragraph 2.C.(2) of' Facility Operating License No. DPR-69 is hereby amended to read as-follows:

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(.2) Technical Specifications The Technical Specifications centained,in-Appendicesi A and B, as revised through Amendment'No.1104 are hereby incorporated in the license. The licensee shall1 operate the facility in accordance with the Technical.

i Specifications..

3.

This license amendment' is effective.as of the' date of its issuance to be I

implemented within 30 days.

FOR~THE NUCLEAR REGULATORY COMMISSION esa a. Ce Robert A. Capra,. Acting Director i

l

. Project Directorate I Division of Reactor Projects,-1/II I

i Attachment

Changes to the Technical Specifications l-Date of~ Issuance: November 3, 1987 I

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, UNITED STATES '

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NUCLEAR REGULATORY COMMISSION.

..j WASHINGTON, D. C.' 20$55

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 128 FACILITY.0PERATING LICENSE NO. DPR AMENDMENT NO. 110 -FACILITY OPERATING LICENSE N0.' DPR-69 DOCKET-NOS. 50-317 AND 50-318 Revise Appendix A as'follows:

Remove Pages Insert'Pages 3/4 1-9 3/4 l'-9' 3/4 1-10*

.3/4 1-10*-

3/4 1-11

-3/4 1-11 3/4 1-12*-

-3/4 1-12*'

3/4 4-32* (1) 3/4'4-32*'(1) 3/44-33(1) 3/4 4-33 (1) i 3/44-33*(2).

3/44-33*(2)

-l 3/4 4-34 (2) 3/4 4-34 (2)-

3/4.5-1*

3/4 5-2 3/4 5-2 3/4 5 3/4 5-5 3/4 5-5a*

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3/4 6-11 3/4 6-11 3/4 6-12*

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Overleaf pages provided to maintain document completeness remove / insert for DPR-53 only remove / insert for DPR-69 only j

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l REACTIVITY CONTROL SYSTEMS l

FLOW PATHS - 0PER ATING LIMITING CONDITION FOR OPER ATION 3.1.2.2 At least two of the followirig three boron injection flow paths and one associated heat tracing circuit shall be OPERABLE:

j i

Two flow paths from the boric acid storage tanks required to be l

a.

OPERABLE pursuant to Specifications 3.1.2.8 and 3.1.2.9 via 4

either a boric acid pump or a gravity. feed connection, and a charging pump To the Reactor Coolant System, and

]

b.

The flow path from the refueling ' water tank via a charging pump to the Reactor Coolant System.

j APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION-1 With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor

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Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY i

and borated to a SHUTDOWN MARGIN equivalent to at least 3% A k/k at 2000F within

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the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two flow paths to OPERABLE status within the i

next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENE i

4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

At least once per 7 days by verifying that the temperature of the a.

heat traced portion of the fic.v path from the concentrated boric acid tanks is above the temperature limit line shown on Figure 3.1 - 1.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct posi-tion.

At least once per refueling interval by verifying on a SIAS test c.

signal that:

(1) each automatic valve in the flow path actuates to its correct position, and (2) each boric acid pump starts.

CALVERT CLIFFS - UNIT 1 3/41-9 Amendment No. f,

,120

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REACTIVITY CONTR0L SYSTEMS CHARGING PUMP'- SHUTDOWN-LIMITING CONDITION-FOR OPERATION 3.1.2.3.At least one charging pump or one high pressure safety injection,

~

pump in the. boron injection flow. path' required OPERABLE pursuantLto o Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

APPLICABILITY: MODES 5 and 6.

l ACTION:

With no. charging pump or.high pressure safety < injection. pump OPERABLE, suspend all operations invelving CORE ALTERATIONS or. positive reactivity -

l changes until at least one of the required pumps is restored to OPERABLE status.

.i SURVEILLANCE REQUIREMENTS l

4.1.2.3 No additional Surveillance Requirements'other:than th'ose required by Specification 4.0.5.

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i CALVERT CLIFFS - UNIT 1 3/4'1-10 1

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REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPER ATION ~

3.1.2.4 At least two charging pumps shall:be OPERABLE.* -

. APPLICABILITY:

MODES 1, 2, 3 and 4.

1 ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to 'a SHUTDOWN MARGIN equivalent to at least 3% A k/k at 2000F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to' OPERABLE status within the 'next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .-

.1 SURVEILLANCE REOUTREME1TTS l

4.1.2.4 At least two charging pumps-shall be demonstrated OPERABLE:

At least once per refueling interval by. verifying that each charg-a.

ing pump starts automatically upon receipt of a Safety injection Actuation Test Signal.

f j

.I b.

No additional. Surveillance Requirements other than those required

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by Specification 4.0.5.

Above 80% RATED THERMAL POWER the two OPERABLE charging pumps shall have independent power supplies.

i CALVERT CLIFFS - UNIT 1 3/4 1-11 Amendment lNo. //, ///, //[.128

REACTIVITY CONTROL' SYSTEMS BORIC ACID PUMPS'- SHUTOOWN LIMITING CONDITION FOR OPERATION 1

3.1.2 5 At' least one boric acid pump shall be OPERABLE and capable of-being powered from an OPERABLE emergency bus if only the flow path l

through the boric acid pump in Specification 3.1.2.4'above is OPERABLE.

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APPLICABILITY: MODES 5 and 6.

ACTION:

With no boric acid pump OPERABLE as required to complete the flow-path of Specification 3.1.2.la, suspend all operations involving CORE ALTERA-TIONS or positive reactivity changes until at least one boric acid, pump is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS i

l 4.1.2.5 Ne additional Surveillance Requirements other than those required by Specification 4.0.5.

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CALVERT CLIFFS - UNIT 1 3/4 1-12 i

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REACTOP COOLANT SYSTEM D.: ACTOR COOLANT SYSTEM VENT 3 i

LIMITING CONDITION FOR OPERATION 3.4.13 One reactor coolant syst.em vent path consisting of two solenoid _ valves-linseriesshall_beOPERABLEandclosedateachofthefollowinglocations-u a.

Reactor vessel head b.

Pressurizer vapor space APPLICABILITY: MODES 1 and 2-ACTION:

a.

With the reactor vessel head vent path inoperable, maintain the i

inoperable vent path closed with power removed from the actuator of the solenoid valves in the inoperable vent path, and:

J 1.

If the pressurizer vapor space vent path -is also inoperable, restore both inoperable vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY-within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or j

?.

If the pressurizer vapor space vent path is'0PERABLE, restore the inoperable reactor vessel head vent path to OPERABLE status J

within 30 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With only the pressurizer vapor space vent' path inopercble, maintain the inoperable vent path closed with power, removed from the valve

)

actuator of the solenoid valves in the inoperable vent path, and:

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1.

Verify at least one PORV and its associated flow path is -

i OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the inoperable

'j pressurizer vapor space vent path to OPERABLE status prior to entering MODE 2 following the next HOT SHUTDOWN of sufficient i

duration, or

=

2.

Restore the inoperable pressurizer vapor space vent path to l

OPERABLE status within 30 days, or be in at least HOT STANDBY -

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within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The provisions of Specification 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.4.13.1 Each reactor coolant system vent path shall be demonstrated OPERABLE-by testing each valve in the vent path per Specification 4.0.5.

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CALVERT CLIFFS - UNIT 1 3/4 4-32 Amendment No.

119 q

'I RE ACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS SURVEILLANCE REQUIREMENTS (Continued) 4.4.13.2. Each reactor coolant system vent path shall be demonstrated OPERABLE at

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l least once per refueling interval by:

i a.'

Verifying all manual isolation valves in each vent path are locked -

in the open position.

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b.

Verifying flow through the reactor coolant system vent paths with the vent valves open.

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CALVERT CLIFFS - UNIT 1 3/4 4-33 Amendment No. ///,128 e

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3/4.5 ' EMERGENCY CORE'C00 LING' SYSTEMS (ECCS) q SAFETY INJECTION TANKS.

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LIMITING CONDITION FOR OPERATION -

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3.5.1-Each reactor coolant system safety. injection. tank shall;be 1

OPERABLE with:

-1 11 a.

The. isolation valve open,

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,q b.

A contained borated water volume of between 1113 and 1179 cubic feet:of borated. water (equivalent. to' tank. levels of.

1 between187and199. inches,respectively),

q A boron concentration'of between 2300 and 2700 ppm. and.

l c.

d.

A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*-

ACTION:

With one safety injection tank inoperable, except'as'a. result '

a.

of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one safety injection tank inoperable due. to the isolation valve ~being closed, either imediately open the isolation.

valve or be in HOT STANDBY within one hour and' be in' HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ..

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SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

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a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

Verifying the contained borated water volume and nitrogen 1

cover-pressure in the tanks, and.

4 2.

Verifying that each safety. injection tank isolation valve -

is open.

adith pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 1.

Amendment No'. (S. 55 CALVERT CLIFFS - UNIT 2 3/4 5-1

. Amendment 4. 31, 38-r

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t EMERGENCY CORE COOJJNG SYSTEMS j.

SURVEILLANCE REQUIREMENTS (Continued)-

b.

At least once per 31 days by verifying the. boron concentration of the safety injection tank solution.

r-c.

At least once per 31 days when the-RCS pressure is above 2000 psis,'by-verifying that power to the isolation valve operator. is removed by main-taining the feeder breaker open under administrative corttrol.

1 d.

Within'4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to increasing the RCS pressure above 1750 psia' by verifying, via local indication 'at the. valve, that the tank isolation valve is open.

c.

At least once per refueling interval by. verifying that each safety injection l

tank isolation valve opens automatically under each of the' following condi--

i tions:

1.

When the RCS pressure exceeds 300 psia, and -

2.

Upon receipt of a safety injection test signal.

T.

Within.one' hour prior to each increase in solution volume of g 1% of normal tank volume by verifying the boron concentration at the operating high pressure safety injection pump discharge is batween 2300 and 2700 ppm.

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1 CALVERT CLIFFS - UNIT 1 3/4 5-2 Amendment No. M f/,128 4

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUTREMENTS (Continued)

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e.

At least once per refueling interval by:

1.

. Verifying automatic isolation and interlock action of the shutdown cooling system from the Reactor Coolant System when the Reactor Coolant System pressure is above_300 psia.

]

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2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by j

debris and that the sump components-(trash racks,

'l screens, etc.) show no' evidence of structural distress or Corrosion.

.I 3.

Verifying that a minimum total of 100 cubic feet of solid -

-l granular trisodium phosphate dodecahydrate.(TSP) is con-

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tained within the TSP storage baskets.

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Verifying that when a representat!ve sample of 4.010.1 j

grams of TSP from a TSP storage basket is submerged,-

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without agitation, in 3.5 10.1 li:ers of 77 1100 F borated l

water from the RWT, the pH of the mixed solution is raised I

to 2. 6 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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f.

At least once per refueling interval, during shutdown, by:

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1.

Verifying that each automatic valve in the flow path actu-ates to its correct position on a Safety injection Actuation test signal.

2.

Verifying that each of the following pumps start automati-

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cally upon receipt of a Safety injection Actuation Test j

Signal:

a.

High-Pressure Safety Injection pump, b.

Low-Pressure Safety Injection pump, 1

CALVERT CLIFFS - UNIT 1 3/4 5-5 Amendment No. /[ [f,((, N8

EMERGENCY CORE COOLING SYSTEMS.

SURVE1LLANCE REQUIREMENTS (Continued) l 9

By performing'a flow balance test during shutdown following i

j completion 'of HPSI system modifications that alter system flow characteristics and verifying the following flow rates for a single HPSI pump system *:

1.

Tne sum of the three lowest flow legs shall be greater than 470** gpm, h.

By verifying that the HPSI pumps' develop a total head of i

2900 ft. on recirculation flow to the refueling water tank when tested ~ pursuant to Specification 4.0,5, sj i

j

A HPSI pump system is a HPSI pump and one of two safety injection headers.

- These limits contain allowances for instrument error, drift or fluctuation.

l CALVERT CLIFFS - UNIT 1 3/4 5-Sa Amendment No. H,7),Jpf, 117-i i

l CONTAINMENT SYSTEMS j

SURVEILL ANCE REQUIREMENTS (Continued) i b.

If any periodic Type A test fails to meet either.75 Ls f259l500 SCCM) or.75 Lt (46,200 SCCM), the test schedule for. subsequent Type A' tests shall be reviewed and approved by -the Commission. if two consecutive '

Type A Tests fail. to. meet either.,75 La.(259,500 SCCM) or.75 L '

t (46,200 SCCM), a Type A; test shall be performed at least every 18 months until two consecutive Type 'A tests meet either.75 La -(259,$00 SCCM) or. 75 L (46,200 SCCM) at which time the above test schedule t

may be resumed.

c.

The accuracy of each Type A test shall be verified by a supplemental test which:

1.

Confirms the accuracy of the Type A test-by verifying that the difference between supplemental..and' Type A test data is within 0.25 La (86,500 SCCM) or 0.25 Lt (15,400 SCCM).

2.

Has a duration sufficient to establish accurately the change in leak--

age between the Type A test' and supplemental test.

3.

Requires the quantity ef' gas injected into the containment' or bled from the containment during the supplemental. test to be equivalent

l to at least 25 percent of the total measured leakage rate at Pa (50 psig) or P (25 psig).

t d.

Type B and C tests shall be conducted with gas at Pa (50 psig) at intervals no greater than 24 months except for tests involving air locks.

Air locks shall be tested and demonstrated OPERdBLE per e.

Surveillance Requirement 4.6.1.3.

f.

All test leakage rates shall be calculated using observed' data converted to absolute values. Error. analyses shall be performed to select a bal-anced integrated leakage measurement system, g.

Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 from power operation modes,' unless the last surveillance test has been' performed within the past 6 months or any time after being opened and prior to entering. MODE 4 from shutdown modes by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Technical Specification 4.6.13.d for all other Type B or C penetrations, the combined leakage'. ate is less-than or equal to 0.60 La (207,600 SCCM). The leakage rata for the containment purge isolation valves shall also be compared '.o. the previ-ously measured leakage rate to detect excessive valve deg'.adation.

i h.

The containment purge isolation valve seals shall be replaced with new seals at a frequency to ensure no individual-seal remains in service greater than 2 consecutive fuel-reload cycles, l

CALVERT CLIFFS - UNIT 1 '

3/4 6-3 Amendment No. h,128

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CONTAINMENT SYSTEMS 1

l CONTAINMENT AIR LOCKS L1HITINCi CONDITION FOR OPERATION' a

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3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for. normal l

transit entry and exit through the containment, then at least one 4

air lock door shall be closed, and

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50 psig.

l.

b. - An overall air lock leakage rate of < 0.05 L, (17,300 SCCM) at P,,

4 APPLICABILITY: MODES 1, 2, 3 and 4.

)

ACTION:

a.

With an air lock inoperable, except as a result of an inoperable l

door gasket, restore the air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i

or 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' SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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b.

With an air lock inoperable due to an inoperable door gasket:

1.

Maintain the remaining door of the affected air lock closed and sealed, and j

2.

Restore the air lock to OPERABLE status within 7 days or 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 i

and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j SURVEILLANCE REQUIREMENTS l

1 1

4. 6.1. 3 Each containment air lock shall be demonstrated OPERABLE:

a.* After each opening, except when the air lock is being used for mu'ltiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by verifying that the seal leakage is < 0.0002 L (69.2 SCCM) as determined l

by precision flow measurement when the volume between the door seals is pressurized to a constant pressure of 15 psig,

Exemption to Appendix "J" of 10 CFR 50.

i CALVERT CLIFFS - UNIT I 3/4 6-4 Amendment No.75

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CONTAINMENT SYSTEMS l

CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 Two independent groups of containment air recirculation and cooling units shall be OPERABLE with two units to each group.

l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

-l a.

With one group of required containment air recirculation and j

cooling units inoperable and both containment spray systems

)

OPERABLE, restore the inoperable group of air recirculation and 1

cooling units to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With three required containment air recircebtion and cooling units inoperable and both containment spray systems OPERABLE, restore at least one required air recirculation and cooling unit to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore both above required groups of contain--

ment air recirculation and cooling units to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , f

c.

With one group of required containment air recirculation and cool-ing units inoperable and one containment spray sptem inoperable, restore the inoperable containment spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 Restore the inoperable group of containment air recirculation and I

cooling units to OPERABLE status within 7 days of initial loss or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

J l

SURVEILLANCE REQUIREMENTS i

4.6.2.2 Each containment air recirculation and cooling unit shall be demonstrated OPERABLE:

}

I a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting each unit from the control room.

J 2.

Verifying that each unit operates for at least 15 minutes.

4 3.

Verifying a cooling water flow rate of > 2000 gpm to each cooling unit when the full flow service water outlet valves are fully open.

i b.

At least once per 18 months by verifying that each unit starts I

automatically on a Containment Spray Actuation test signal.

-i CALVERT CLIFFS - UNIT 1 3/4 6-12 Amendment No. 93 j

l

~

f CONTAINMENT SYSTEM 3

.C

}/4.6.3 IODINE REMOVAL SYSTEM -

LT)fiTING CONDITION ' FOR OPER ATION 3.6.3.1 Three independent containment iodine filter trains shallIbe OPERABLE.

i i

APPLICABILITY:

MODES 1, 2, 3' and 4.

11 ACTION:

With one iodine filter train inoperable;, restore the inoperable. train to OPERABLE 1 status within 7 days'or 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

'I COLD SHUTDOWN within the following'30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 i

SURVEILLANCE REQUIREMENTS I

i 4.6.3.1 Each iodine filter train shall be demonst. rated OPERABLE 1

l At least once per 31 days on a STAGGERED TEST BASIS by j

a.

initiating, from the control room, flow through the HEPA' filter

{

and charcoal adsorber train and verifying that the train operates j

for at least 15 minutes.

~

,l b.

At least once per refueling interval or (1) after any structural.

maintenance on the HEPA filter or charcoal adsorber housings, or

{

(2) following painting, fire or chemical release in any ventilation zone communicating with the system by; 1.

Verifying that the charcoal adsorbers remove z 99% of a j

halogenated hydrocarbon' refrigerant test gas when they are i

tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm

~ 10E 2.

Verifying that the HEPA filter banks remove 199% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train ~ at a flow rate of 20,000 cfm i 10%

i

,CALVERT CLIFFS - UNIT 1 3/4 6-13 Amendment No 128

.n,

4 CONTAINMENT SYSTEMS I

SURVEILLANCE REQUIREMENTS (Continued) 3.

Verifying within 31 days af ter remov'a1. that a laboratory-analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of-the charcoal adsorbers demonstrates a removal effi-ciency of > 95%' for radioactive elemental iodine when' the sample is tested in accordance with ANSl'N510-1976 (130'C, 95% R.H.). ~ The carbon samples not'obtained from test canisters shal.1 be: prepared by emptying a representative sample from an adsorber test tray section','. mixing the adsorbent thoroughly, and obtaining samples'at least two.

inches in diameter and with a length equal to the thit kness of the bed. Successive. samples will be removed from dif ferent i.est tray. sections.

4.

Verifying a filter train flow rate of 20,000 cfm + 10%

l during system operation when tested in accordance with I

ANSI N510-1975.

j l

c.

Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal ~that'a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 95% for radio-active elemental iodine when the sampTe is tested in accor-q dance with ANSI N510-1975 (130*C, 95% R.H.); or j

)

2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a-removal efficiency of > 95% for radioactive elemental-

. iodine when the samples are tested in accordance with ANS!' N510-1975 (130*C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber l

test tray section, mixing the adsorbent thcroughly, and obtaining samples at least two inches in diameter and with a length equal'to the thickness of the bed. Successive samples will be removed from different test tray sections.

1 e

CALVERT CLIFFS - UNIT 1 3/4 6-14 Amendment No.83 f

L d

.p;

')

ll CONTAINMENT SYSTEMS j

SURVEILLANCE REQUIREMENTS (Cont nued) 8

. Subsequent to' reinstalling the adsorber tray used for.

. obtaining the carbon sample, the filter train shall be dem-1 onstrated OPERABLE by also verifying that-the charcoal

'l adsorbers remove a 99%' of. a: halogenated hydrocarbon refrigerant' test gas when they'are tested in-place in accordance with ANSI N510-1975.while operating th'e filter train. at a flow rate -

of 20,000 cfm i 10%.

d.

At least once per refueling interval by:

.i 1.

Verifying that the pressure drop across the combined HEPA i

fiP,ers and charcoal adsorber banks is < 6 inches Water j

Gauge while. operating the filter train at a flow rate of ~

l 20,000' cfm i 10%.

1 2.

Verifying that' the filter. train ' starts on a Containment.

Isolation test signal.

l l

1 1

I 1

l

,4 CALVERT CLIFFS - UNIT 1 3/4 6-15 Amendment No. //,[,3 128

W '

i 1

CONTAINMENT SYSTEMS a

SURVEILLANCE: REQUIREMENTS (Continued) j I

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 1 99! of

.j the DOP when they are. tested in place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm 1 10*2.

]s

.f.

After each complete or partial replacement of'a charcoal i

9 adsorber bank by verifying that the. charcoal adsorbers remove 1 99% of a halogenated hydrocarbon' refrigerant test gas when they are tested in-place in accordance with. ANSI N510-1975 while operating the filter train at a flow rate of 90,000 cfm 1 106 g.

After maintenance affecting the air flow distribution by testing in-place and varifying that the air. flow distribtuion 1

is uniform within 12C% of the average flow per unit when tested in accordance with_the provisions of Section 9 of j

" Industrial Ventilation" and Section 8 of ANSI N510-1975.

ll J

l 4

I u

i CALVERT CLIFFS - UNIT 1 3/4 6-16 Amendment No. 38

,,._n-----------

,- -- --- - - = -

~

CONTAINNIENT SYSTEh1S 3 /4.6.4 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPER ATION

-l 3.6.4.1 The containment isolation valves specific'd in Table 3.6-1 'shall be

~

' OPERABLE with isolation times as shown in Table 3.6-1.

,{

APPLICABILITY:

MODES 1, 2, 3, and 4.

s3 1

ACTION:

)

i With one or more of the isolation va'Ive(s) specified in Table 3.6-1 inoperable, either:

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,. or a.

i

]

b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at -least one deactivated automatic valve secured in the isolation position,~ or i

Isolate the affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one i

c.

closed manual valve or blind flange; or

j d.

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 .

The provisions of Specification.3.0.4 are not applicable provided that the i

e.

affected penetration is isolated.

.]

SURVEILL ANCE REQUIREMENTS i

4.6.4.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit by performance of a cycling test and verification of. isolation time.

'I I

CALVERT CLIFFS - UNIT I 3/4 6-17 Amendment No.128

i CONTAINMENT SYSTEMS SURVEILL ANCE REQUIREMENTS (Continued) 4.6.4.1.2 Eawh isolation valve specified in Table 3.6-1 shall be demonstrated OPERABI E during the COLD SHUTDOWN or REFUELING MODE at least once per refueling interval by:

a.

Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation posi-tion.

b.

Verifying that on each Containment Radiation-High Test Channel A or Channel B test signal, both required containment purge valves actuate to their isolation position.

c.

Verifying that on each Safety Injection Actuation Channel A' or Channel B test signal, each. required isolation valve actuates to its. isolation position.

I 4.6.4.1.3 The isolation time of each power operated or automatic valve of Ta '

ble 3.6-1 shall be determined to be within its limit when tested pursuant to Techni-cal Specification 4.0.5.

l i

1 1

Amendment No, f, f. h.128 CALVERT CLIFFS - UNIT 1 3/4 6-18

CONTAINMENT SYSTEMS

. ELECTRIC HYDROGEN RECOMBINERS - W.

LIMITING CONDrr10N FOR. OPERATION

~ 3.6.5.2 Two independent. containment hydrogen recombiner systems shall. be OPERABLE.

)

i APPLICABILrrY: MODES 1 and 2.

i ACTION:

1

. With on hydrogen recombiner system inoperable, restore the inoperable system' to

.)

OPERABLE status within 30 days or be in at least HOT STANDBY within.the next 6 j

hours.

)

SURVEILLANCE REOUTREMENTS i

4.6.5.2 Each hydrogen recombiner system shall be demonstrated-OPERABLE:

At least once per 6 months by verifying during a recombiner a.

system functional test that the minimum heater sheath temperature increases to a 7000F within 90 minutes and is maintained for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b.

At least once per refueling interval by:

1.

Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

2.

Verifying through a visual-examiriation that there is no evidence of abnormal conditions within the recombiners

)

(i.e., loose wiring or structural connections, deposits of j

foreign materials, etc.)-

j 4

q 3.

Verifying during a recombiaer system functional test that the heater sheath temperature increase to a 12000F within 5.

hours and is maintained for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

-i 4.

Verifying the integrity of the heater ~ electrical circuits by performing a continuity and resistance to-ground test following the above required functional test. The resis-tance to ground for any heater phase shall-be y,10,000 i

j ohms.

1 d

CALVERT CLIFFS - UNIT 1 3/4 6-27 Amendment No. 128 Y

l 4

)

I CONTAINMENT SYSTEMS i

3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM 1

LIMITING CONDITION FOR OPERATION

)

Two independent containment penetration room exhaust air filter 3.6.6.1 trains shall be OPERABLE.

l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one containment penetration room exhaust air filter train inoperable, restore the inoperable train to OPERABLE status within 7 days or 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 SHUTDOW the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS Each containment penetration room exhaust air filter train shall 4.6.6.1 be demonstrated OPERABLE:

At least once per 31 days on STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filter and charcoal a.

adsorber train and verifying that the train operates for at least 15 minutes.

At least once per 18 months or (1) after any structural b.

maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

f Verifying that the charcoal adsorber; remove > 99% of 1.

a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 2000 cfm + 10%.

CALVERT CLIFFS - UNIT 1 3/4 6-28

^

PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMI.TATION LIMITING CONDITION FOR OPERATION The temperatures of both the primary and secondary coolants in 3.7.2.1

'the steam generators shall be > 80*F when the pressure of either coolant-l l

in the steam generator is >.200 psig.

APPLICABILITY: At all times.

ACTION:

With the requirements of the above specification not satisfied:

a.

Reduce the steam generator pressure' of the applicable. side' to.

< 200 psig within 30 minutes, and b.

Perform.an engineering evaluation to detemine the effect of the overpressurization on the structural integrity of the j

steam' generator. Determine that the steam generator remains acceptable for' continued operation prior to increasing its temperatures above 200'F.

I SURVEILLANCE REQUIREMENTS 4.7.2.1 The pressure in each side of the steam generators shall be detemined to be < 200 psig at least once per hour when the temperature of either the primary'or secondary coolant < 80*F.

l i

4 CALVERT CLIFFS-UNIT 1 3/4 7-13 Amendment No. 82

_.______._.____.___.__.______i._.____

i

t i

PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING % ATER ' SYSTEM LIMITING CONDTTION FOR OPER ATION 3.7.3.1 At least two component cooling water loops shall be OPERABLE. At least one component cooling water heat exchanger shall be operating and the remaining component cooling water heat exchanger may be in standby.-

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one. component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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 .

.I SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water loops 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 that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety injection Actuation test signal.

CALVERT CLIFFS - UNIT 1 3/4 7-14 Amendment No.

,128

a i

i PLANT SYSTEMS 1

3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPER ATION 3.7.4.1 At least two independent service water loops shall be OPERABLE, APPLICABILITY:

MODES 1, 2,' 3 and 4 ACTION:

With only one service water loop OPERABLE, restore at least two loops. to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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 .

?

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two service' water loops shall be demonstrated OPERABLE i

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

operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per refueling interval during shutdown, by verifying that l

each automatic valve servicing safety related equipment actuates to its correct position on Safety injection Actuation and Containment Spray l

Actuation test signals.

3

-i 1

1 i

I l

i CALVERT CLIFFS - UNIT I 3/4 7-15 Amendment No.

128 1

1 1

1 PLANT SYSTEMS l

3/4.7.5 SALTWATER SYSTEM LTMITING CONDITION FOR OPER AT10N l

~

3.7.5.1 At least two independent saltwater loops shall be OPERABLE.

1 APPLICABILITY:

MODES 1, 2, 3 and 4.

j 1

ACTION.

With only one saltwater loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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' l

in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l l

l SURVEILLANCE REOUTREMENTS q

l l

4.7.5.1 At least two saltwater loops shall be OPERABLE.

At least once per 31 days be verifying that each valve '(manual power a.

operated or automatic) in the flow path-that is not locked, sealed, or

~

otherwise secured in position, is in'its correct position, j

b.

At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety injection Actuation test signal.

1 I

i l

CALVERT CLIFFS - UNIT I 3/4 7-16 Amendment No. [, 128 tU-__

i RE ACTTVITY CONTROL SYSTEMS j

FLOW PATHS - OPER ATING LIMITING CONDITION FOR OPER ATION 3 J.2.2 At least two of the following three boron injection flow paths and one associated heat tracing circuit shall be OPERABLE-1 Two flow paths from the boric acid storage tanks required to be a.

OPERABLE pursuant to Specifications 3.1.2.8 and 3.1.2.9 via either a boric acid pump or a gravity feed connection, and a charging pump to the Reactor Coolant System,' and

{

b.

The flow path from the refueling water tank via a charging pump to the Reactor Coolant System.

\\

APPLICABILITY:

MODES 1, 2, 3 and 4.

l ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY j

and borated to a SHUTDOWN MARGIN equivalent to at least 3% 4 k/k at 2000F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMEN'T3 1

4.1.2.2 At least two of the above required flow paths shall be demonstrated.

OPERABLE:

At least once per 7 days by verifying that the temperature of the a.

heat traced portion of the flow path from the concentrated boric acid tanks is above the temperature limit line shown on Figure 3.1 - 1.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct posi-.

tion.

)

I c.

At least once per refueling interval by verifying on a SIAS test

- signal that:

1 (1) each automatic valve in the flow path actuates to its correct position, and 1

(2) each boric acid pump starts.

t I

Amendment No. % ((, (( M CALVERT CLIFFS - UNIT 2 3/4 1-9 l

)

REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN I

LIMITING CONDITION FOR OPERATION j

i 3.1.2.3 At.least one charging pump or one high pressure ' safety injection:

1 pump in the boron injection-flow path required OPERABLE pursuant to-j Specification 3.1.2.1 shall be OPERABLE and capable of being powered 1

from an OPERABLE emergency bus.

l M3PL I CABl'.17 (: MODES 5 and 6.

i

' CT'10N-W% nt,

..arging pump or high pressure safety injection pump OPERABLE, 4

cr pend all operations involving CORE ALTERATIONS or. positive reactivity

.ct,anges until at least one of the. required pumps is restored to OPERABLE status.

}

SURVEILLANCE REQUIREMENTS l

4.1.2.3 No additional Surveillance Requirements other than those required j

by Specification 4.0.5.

i i

{

l i

CALVERT CLIFFS-UNIT 2 3/4 1-10

1

)

l

\\

REACTTVITY CONTROL SYSTEMS CH ARGING PUMPS - OPER ATING LIMITING CONDITION FOR OPER ATION 3.1.2.4 At least two charging pumps shall be OPERABLE.*

APPLICABTLTTY:

MODES 1, 2, 3 and 4, ACTION:

I With only one charging pump OPERABLE, restore at least two charging pumps to.

OPERABLE status within 72-hours or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3% A k/k at 2000F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE:

At least once per refueling interval by verifying that each charg-a.

ing pump starts automatically upon receipt of a Safety Injection Actuatior. Test Signal.

b.

No additional Surveillance Requirements other than those required by Specification 4.0.5.

l i

Above 80% RATED THERMAL POWER the two OPERABLE charging pumps shall have independent power supplies.

i Amendment No. [f, ff '110 CALVERT CLIFFS - UNIT 2 3/4 1-11 i

u

.1 1

l REACTIVITY CONTROL SYSTEMS-BORIC ACID PUMPS - SHUTDOWN q

]

LIMITING CONDITION FOR OPERATION q

3.1. 2. 5 At least one boric. acid pump shall' be OPERABLE and capable of.

being powered from er OPERABLE emergency bus if only the flow path

(

l through the boric acid pump in Specification 3.1.2.la above, is OPERABLE.

J

q APPLICABILITY: MODES 5 and 6.

j

^

ACTION:

.j Wi' h' no boric acid pump OPERABLE as required' to complete the flow path -

1 t

of Specification 3.1.2.la, suspend all _ operations : involving CORE ALTERA-

]

TIONS or positive reactivity changes. until at least'one boric acid pump q

is restored to OPERABLE status.

1 i

SURVEILLANCE REQUIREMENTS l

q l

4.1. 2. 5 No additional Surveillance Requirements other than those required by Specification 4.0.5.

l l

l 1

i l

\\

l 1

i l

l i

CALVERT CLIFFS-UNIT 2 3/4 1 12

=_

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.13 One reactor coolant system vent path consisting of two solenoid valves in series shall be OPER\\BLE and closed at each of the following locations:

a.

Reactor vessel head b.

Pressurizer vapor space APPLICABILITY: MODES 1 and 2 ACTION:

With the reactor vessel head vent path inoperable, maintain the a.

inoperable vent path closed with power removed from the actuator of the solenoid valves in the inoperable vent path, and:

1.

If the pressurizer vapor space vent path is also inoperable, restore both inoperable vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or 2.

If the pressurizer vapor space vent path is OPERABLE, restore the inop'erable reactor vessel head vent path to OPERABLE status within 30 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

~

b.

With only the pressurizer vapor space vent path inoperable, maintain the inoperable vent path closed with power removed from the valve actuator of the solenoid valves in the inoperable vent path, and:

1.

Verify at least one PORV and its associated flow path is OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the inoperable pressurizer vapor space vent path to OPERABLE status prior to entering MODE 2 following the next HOT SHUTDOWN of sufficient duration, or 2.

Restore the inoperable pressurizer vapor space vent path to OPERABLE status within 30 days, or be in at least HOT STANDSY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The provisions of Specification 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.4.13.1 Each reactor coolant system vent path shall be demonstrated OPERABLE by testing each valve in the vent path per Specification 4.0.5.

CALVERT CLIFFS - UNIT 2 3/4 4-33 Amendment No.101 4

i i

i REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS i

SURVEILLANCE REOUTREMENTS (Continued) 4,4.13.2 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per refueling interval by:

l 4

Verifying all manual isolation valves in each vent path are locked a.

in the open position, b.

Verifying flow through the reactor coolant system vent paths with the vent valves open.

)

CALVERT CLIFFS - UNIT 2 3/4 4-34 Amendment No.((,110

b i

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SAFETY INJECTION TANKS 1

LIMITING CONDITION FOR OPERATION 3.5.1. Each' reactor coolant system safety injection tank shall be OPERABLE with:

a.

The isolation valve open, b.

A contained borated water volume of:between 1113'and 1179 cubic feet of borated water (equivalent to tank levels of between 187 and 199 inches. respectively),

A boron concentration of between 2300 and 2700 ppm,-and c.

l d.

A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

With one safety injection tank inoperable, except as a result a.

of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

With one safety injection tank inoperable due to the isolation valve being closed, either imediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

a.

1.

Verifying the contained borated water volume and nitrogen-cover-pressure in the tanks, and 2.

Verifying that each safety injection t4nk isolation valve is open.

With pressurizer pressure 1 1750 psia.

CALVERT CLIFFS - UNIT 1 Amendment No. (8, 55 CALVERT CLIFFS - UNIT 2 3/4 5-1~

Amendment 460. H. 38 a

0-

n EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOU1REMENTS (Continued) b.

At least once per 31 days by verifying the boron concentration of the safety injection tank solution, At least once per 31 days when the RCS pressure is above 2000 psig, by c.

verifying that power to the isolation valve operator is removed by main-taining the feeder breaker open under administrative control, d.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to increasing the RCS pressure above 1750 psia by.

verifying, via local indication at the valve, that the tank isolation valve is open.

At least once per refueling interval by verifying that each safety injection l

l e.

tank' isolation valve opens automatically under each of the following condi-tions:

1.

When the RCS pressure exceeds 300 psia, and j

2.

Upon receipt of a safety injection test signal.

f.

Within one hour prior to each increase in solution volume of a 1% of normal tank volume by verifying the boron concentration at the operating high pressure safety injection pump discharge is between 2300 and 2700 ppm.

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

128 CALVERT CLIFFS - UNIT 2 Amendment No 110 1P

,a EMERGENCY CORE COOLING SYSTEMS.

SURVEILLANCE REQUIREMENTS (Continued) i cl " '

(

e, At least once per refueling' Interval b).'

[

1.

Verifying automatic isolation and interlock-action of the shutdown cooling system from.the Reactor Coolant System ' '

when the Reactor Coolant System L pressure is above 300 :

psia.

2.

A visual inspection of the containment sump.and verifying that the subsystem suction inlets are not restricted by,

j debris and that the sump components (trash racks, 1

screens, etc.) show no ' evidence of structural distress or l

Corrosion.

3.

Verifying -that a minimum total of 100 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is con-:

. tained within the TSP storage' baskets.

4.

Verifying that when a representative sample of-4.0 t~0.l grams of TSP from a TSP storage basket is submerged, without agitation, in 3.5 10.1 liters of 77 i 100 F borated water from the RWT, the. pH of the mixed solution is raised to E 6 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

f.

At least once per refueling ir+erval, during shutdown, byi

.ll 1.

Verifying that each automatic valve in the flow path actu--

)

ates to its correct position on a Safety injection : Actuation

'i test signal.

2.

Verifying that each of the following pumps start automati-cally upon receipt of a Safety injection Actuation Test Signal:

e High-Pressure Safety injectiori pump.

a.

]

b.

Low-Pressure Safety Injection pump.

i

l a

.)

s 1

j l

i L

h r

y CALVERT CLIFFS - UNIT 2 3/4 5-5

~ Amendment No. /f, //, /)/,110' 4

.r

__...-.-.m

4 EMERGENCY CORE COOLING SYSTEMS.

il SURVEILLANCE REQUIREMENTS (Continued) j I

l.

l g.

By performing a flow balance test during' shutdown following i.

i completion of HPSI system modifications. that alter system flow characteristics and verifying the following flow rates _ for a j

single HPSI pump system *:

j 1.

The sum of the three lowest flow legs shall be greater ~

i 1

tnan'470** gpm.

l-h.

By verifying that the HPSI pumps develop a total head of 2900 ft

. i on recirculation flow to the refueling water tank when tested pursuant to Specification 4.0.5.

l l

J i

A HPSI pump system is a HPSI _ pump and one of two safety injection headers.

C---- - -

.**These limits-contain allowances for instrument error, drift or fluctuation.

CALVERT CLIFFS - UNIT 2 3/4 5-Sa Amendment No. 16,55,pp, 99 4

_d.

.1

,(.'

CONTAINMENT SYSTEN1S '

SURVEILLANCE REQUIREMENTS (Continued)

~

b.

If any ~ periodic Type - A test-fails; to meet either.75. La (259,500 SCCM) or.75 Lt (33,400 SCCM), the test schedule for subsequent Type A tests shall be reviewed and approved by, the Commission. If. two consecutive t

Type A Tests rail to meet either a75: La (259,500 SCCM)' or.75 ' Lp (33,400 SCCM), a: Type A test shall be performed at least every 18 months until two consecutive Type A tests meet either.75 La (259,500 SCCM) or.75 Lt (33,400 SCCM) at which time the above -test schedule.

may be resumed.

.)

c.

The accuracy of-each Type A' test shall be verified by a' supplemental.

test which:

1.

Confirms the accuracy'of the Type A test by verifying that the.

difference between supplemental'and Type A test data-is within0.25 La (86,500 SCCM) or 0.25 L !.11,100 SCCM).

t 2.

Has a duration sufficient to establish accurately the change inileak-age between the Type A test snd. supplemental test.

3.

Requires the quantity of gas injected into the' containment or bled from the containment;during the supplemental test to be equivalent l to at least '25 percent of the total measured leakage; rate at Pa (50' psig) or-P (25 psig),

t d.

Type B and C tests shall be conducted with gas at Pa (50 psig) at

-l intervals no greater than 24 months except for tests involving air locks.

1 Air locks shall be tested and demonstrated OPERABLE per e.

Surveillance Requirement 4.6.1.3.

f.

All test leakage rates shall be calculated using observed data ' converted to absolute values. Error analyses shall be performed.to select'a' bal-

]

anced integrated leakage measurement system.

g.

Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 from power operation modes, unless the last surveillance test has been. performed within the past 6 months or.any

]

time after being opened and prior to entering ' MODE.4 from shutdown modes by verifying that when the measured leakage rate is' added to the leakage rates determined pursuant to Technical Specification 4.6.1.2.d..

for all other Type B or C penetrations, the combined leakage rate is less than or equal to.0.60.La (207,600 SCCM). : The leakage rate for the containment purge isolation valves shall also be compared to the previ-ously measured ~ leakage rate to detect excessive valve degrad tion.L

-h.-The contairiment purge isolation ' valve seals shall 5 replaced with new seals s'. a frequency to ensure no individual seal. remains in service greater than 2 consecutive fuel reload cycles, i

CALVERT CLIFFS -- UNIT 2 3/4' 6-3 --

Amendment No.

110

'I CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3. '6.1. 3 Each containment air lock ~ shall be OPERABLE with:

a.

Both doors closed except when the air lock'is.being: Used for normal transit entry and exit through the containment, then at'least one l

~

air lock door shall be closed, and J

b.

An overall air ' lock leakage rate of i 0.05 L, (17,300 SCCM), at P,..

l

]

50 psig.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With an air lock inoperable, except as a result of an. inoperable door gasket, restore the' air lock to OPERABLE status within 24. hours

~

or 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 .

l

.)

b.

With an air lock inoperable due to' an inoperable door gasket:

1.

Maintain the remaining door of the affected air lock closed and sealed, and j

2.

Restore the air lock to OPERABLE status within 7 days or 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:-

a'.* Af ter each opening, except when the airlock'is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by verifying that the seal leakage is < 0.0002 L (69.2 SCCM) as determined l

by precision flow measurement wheh the volume between the door seals is pressurized to a constant-pressure of 15 psig,

Exonption to Appendix "J" of 10 CFR 50.

CALVERT CLIFFS - UNIT 2 3/4.6-4 Amendment _No. 56

1 CONTAINMENT SYSTEMS SURVEILLANCE REOUTREMENTS (Continued) b.

At least once per refueling interval, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actu-ates to its correct position on Safety injection Actuation test signal, j

}

2.

Verifying that each spray pump starts automatically on a Containment Spray ' Actuation test signal.

c.

At least once per 5 years by performing an air or smoke flow test k

through each spray header and verifying each spray nozzle is unobstructed.

4 I

.i d

1 l

t i

1 l

l h

l 1

i 1

i i

I CALVERT CLIFFS - UNIT 2 3/4 6-11 Amendment No.110

'l 1

0

(

CONTAINMENT SYSTEMS' CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 Two independent groups of containment air recirculation'and cooling-units shall be OPERABLE with two units to each group.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With one group of required containment air recirculation and cooling units inoperable and both containment spray systems-OPERABLE, restore the inoperable group'of air recirculation and.

cooling units to OPERABLE status within 7 days 'or_ be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With three required containment air recirculation and cooling units inoperable and both containment spray. systems 0PERABLE, restore at least one required air recirculation and cooling unit to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at.least HOT. SHUTDOWN j

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .. Restore both above required groups of contain-

)

ment air recirculation and cooling units to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 c.

With one group of required containment air recirculation and cool-units inoperable and one containment spray system inoperable, restore the inoperable containment spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within-12 hours.

Restore the inoperable group of containment air recirculation and cooling units to OPERABLE status within 7 days of initial loss or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.2.2 Each containment air recirculation and cooling unit shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting each unit from the control room, f

2.

Verifying that each unit operates-for.at least 15 minutes, a

~

3.

Verifying a cooling water flow rate of [2000 gpm to each cooling unit when the full flow service water outlet valves j

are fully open.

b.

At least once per 18 months by verifying that each unit starts automatically on a Containment Spray Actuation test signal.

j CALVERT CLIFFS - UNIT 2 3/4 6-12 Amendment No. 74 lj

.s

i CONTAINMENT SYSTEMS-j

}/4.63 IODINE REMOVAL SYM l

LIMITING CONDITION FOR OPERATION 3.6.3.)

Three independent containment' lodine filter trains shall be OPERABLE, y

APPLICABILITY:

MODES 1, 2, 3' and ~ 4.

ACTION:

With one lodine filter train inoperable, restore the' inoperable train to OPERABLE status within 7 days or 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 .

SURVEILLANCE REOUIREMENE 1

4.6.3.1 Each iodine filter train shall be demonstrated OPERABLE:

At least once per 31 days on 2 STAGGERED TEST BASIS.by initiating,

.a.

from.the control room, flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at lee.st 15 minutes.

y 1

b.

At least once per refueling interval or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings,. or (2) l following painting, fire or chemical release in any ventilation zone communicating with the system by:

Verifying that the charcoal adsorbers remove a 99%' of a halogenated

' l 1.

hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the filter train.at a' flow rate of 20,000 cfm i 10%

2.

Verifying that the HEFA filter banks-remove z 99% of the DOP when they are tested in-place in accordance with ANSI N5101975 while operating the filter train at a flow rate of 20,000 cfm 10 %

t CALVERT CLIFFS - UNIT 2 3/4 6-13 Amendment No.' 110 x

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

i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.

Verifying.within 31 days af ter removal that a laboratory analysis of a carbon sample from'either'at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers. demonstrates a removal effi -

ciency of > 95% for radioactive elemental iodine when the Satple is tested 'in accordance with ANSI N510-1975 (130*C, j

95% R.H.).

The carbon samples not obtained from test canisters shall be prepared by emptying a representative sample from an adsorber-test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness.

l of the bed. Successive samples' will be removed. from 1

f different test tray sections.

a 4.

Verifying a filter train flow rate of 20,000 cfm + 10%

during system operation when tested in accordance with ANSI N510-1975.

]

c.

Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

]

1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 95", for radio-active elemental iodine when the sampTe is tested in accor-dance with ANSI N510-1975 (130*C, 95% R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of > 95% for radioactive elemental iodine when the samples are tested in accordance with ANSI N510-1975 (130*C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and j

obtaining samples at least twc inches in diameter and with j

a length equal to the thickness of the bed. Successive ' samples will be removed from different test tray sections.

'i CALVERT CLIFFS -- UNIT 2- - -- -

3/4__6-14 Amendment No. 6 6 l

A i

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (ContinuedF.

' Subsequent to reinstalling the adsorber, tray used for obtaining the.

carbon, sample, the filter trairtshall be demonstrated OPERABLE by-also verifying that the charcoal adsorb' rs remove t 99% of a e

halogenated -hydrocarbon, refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating. the l

filter train at a flow-rate of 20,000 cfrn 110%,

l d.

At least once per refueling interval byi 1

l 1.

Verifying that the pressure drop across the. combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while oper -

. sting the fil;er train at a flow rate.of.~20,000 cfm 10%.

2.

Verifying that the filter train starts on a Containment Isolation test

'l signal.

i i

l I

I CALVERT CLIFFS - UNIT 2 3/4 6-15 Amendment No.

,//,110

,a y

m.. t.

1 21 s (

l CONTAINMENT SYSTEMS-'

4

'l 4

SURVEILLANCE REQUIREMENTS'(Continued)- ",

_q m

.]

i d

h e.

After eacs complete or partial' replacement of a HEPA filter.

V':

bank by verifying that the HEPA filter banks; removeL> 991 of!

i the DOP when they are tested in place in accordance with ANSI N510-1975 while operating 1the filter trairi at' a flow rate of' 4

20,000 cfm 1.10 7

1 f.

After each complete or partial replacement 'of a charcoal..

adsorber bank by verifying'that '.the charcoal.adsorbers. remove

g

> 99'iof.a halogenated hydrocarbon: refrigerant test ga:;.when they are tested.in-place in accordance.with ANSI N510-1975 i.

While operating the filter train atla flow rate of; 20,000.cfm i 10%.

j g.

After maintenance affecting the' air flow distribution by testing in-place and' verifying that :the air flow distribution

'{

is uniform within i 20% of theLaverage flow per' unit when tested-in accordance with the provisions of-Section 9 of 4

" Industrial' Ventilation" and Section=8.of ANSI'N510-1975.

~

J i

a

)

/

6

-)

l i

l 0

]

1 1

d 4

)

.)

1 i

l i

(

CALVERT CLIFF.S - UNIT 2 3/4 6 Amendment No. 21 1!

m__

f h

m________.

m_.

1 w

a

CONTAINMENT SYSTEMS -

j t

3/4.6.4 CONTAINMENT ISOLATIOQiM i

1IMITING CONDITION FOR OPER ATION" l

)

3.6.4.1

.The containment isolation valves'specified in Table 3.6-1 shall be t

3 OPER ABLE witt. isolation times as'shown in-Table 3.6-l'.

l APPLICABILITY:

. MODES 1, 2, 3 and. 4.-

ACTIONi

'I l

J With' one or twre ci the isolation valve (s) specified in Table 3,6-l? inoperable, either:

4 Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or:

I a.

1 b.

Isolate. each affected. penetration within.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one l-deactivated automatic valve secured in the iso!ation position, or.

p c.

Isolate the. affected penetration within~ 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or. blind flange; or d.

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 .

1 l

The provisions of Specification 3.0,4'are not applicable provided that' the j

e.

affected penetration is isolated.

R SURVEILL ANCE REQUIREMENTS 4.6.4.1.1 The isolation vaives specified in Table 3,6-lL shalls be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair, or replacement work is. performed on the valve'or its associated actuator, control, or l.

power circuit by performance of a cycling test and verification of isolation time, j

1 l

l-

' i l

- i

' CALVERT CLIFFS - UNIT 2 3/4 6-17 Amendment No.110 9

_____..m_.___

c

}

L l

f a

1 l

CONT AINM ENT ' SYSTE MS

)

i SURVEILL ANCE REQUIREMENTS (Continuedf f

4.6.4.1.2

-Each. isolation valve specified in Table' 3.6-1 shall be ' demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least.once per 1

refueling interval by:

]

a.

Verifying that on each containment isolation Channel A. or Channel B test signal, each required isolation. valve actuates to its isolation posi-tion.

b.

Verifying that on each' Containment Radiation-High Test Channel A or Channel B test signal, both required containment purge valves actuite to their isolation position.

c.

Verifying that on each Safety Injection Actuation' Channel A or Channel B test signal, each required isolation valve actuates to its isolation f

I position.

.i 4.6.4.1.3 The isolation time' of each power operated or automatic valve of Ta-I ble 3.6-1 shall be determined to be within its limit when tested pursuant to Techni-cal Specification 4.0.5.

f i

)

i I

L i

i CALVERT CLIFFS - UNIT 2 3/4 6-18 Amendment No. [, //,[,110 1

.{

4 4

CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS - W ~

l LIMITING CONDITION FOR OPERATION i

y 3.6.5.2 Two ' independent ' containment hydrogen recombiner systems shall b'e l]

OPERABLE.

l APPLICABILITY: MODES l ~ and 2.

1 ACTION:

With on hydrogen recombiner system inoperable, restore the inoperable system to i'

OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 '

hours.

l

$ SURVEILLANCE REQUIREMENTS 4.6.5.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

At least once per 6 months by verifying during a recombiner a.

system functional test that the minimum heater sheath temperature increases to a 7000F within 90 minutes and is maintained for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , t.

At least once per refueling interval by:

1.

Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

2.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3.

Verifying during a recombiner system functional test that the heater sheath temperature increase to a 12000F 'within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and is maintained for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.

Verifying the integrity of the heater electrical circuits by performing a continuity and resistance to ground test following the above required functional test. The resis-tance to ground for any heater phase shall be a 10,000 ohms.

CALVERT CLIFFS - UNIT 2 3/4 6-27 Amendment No. 110'

I 4

4 CONTAINMENT SYSTEMS 3/4.6.6. PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 4

3.6.6.1 Two independent containment penetration room exhaust air filter trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one containment penetration room exhaust air filter train inoperable, restore the inoperable train ~to OPERABLE status within 7 days or 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 j

the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l SURVEILLANCE REQUIREMENTS 4.6.6.1 Each containment penetration room exhaust air filter train shall

(

be demonstrated OPERABLE:

j At least once per 31 days on 'ST AGGERED TEST BASIS'.by initiating, a.

from the control room, flow through the HEPA' filter and charcoal i

adsorber train and verifying that the train operates for'at least 15 minutes.

b.

At least once per 18 months or (1) after any. structural l

maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1.

Verifying that the charcoal adsorbers remove 3,99% of a halogenated hydrocarbon refrigerant test gas.when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 2000 cfm + 10%.

CALVERT CLIFFS - UNIT 2

-3/4 6-28

.o

i

j

.]

.1 PLANT SYSTEMS _-

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION-1 J

' LIMITING CONDITION FOR OPERATION-3.7.2.1 The _ temperatures of both the. primary and secondary coolants in the steam generators shall be > 90*F when the pressure'of either coolant

]

U in the steem generator is' > 200 psig.

3 l

APPLICABILITY: At all times.

I ACTION:

With the requirements of the above specification not satisfied:

a.

Reduce the steam generator pressure of the applicable side to

< 200 psig-within 30 minutes, and b.

Perform an engineeririg evaluation to determine the effect of the overpressurization on the stru'ctural integrity of the steam generator. Determine that the steam generator. remains -

l acceptable for continued operation prior _to increasing its i

temperatures above 200*F.

1 l

, SURVEILLANCE REQUIREMENTS l

.)

4.7.2.1 The pressure in each side of the steam generators shall be determined to be < 200 psig at least once per hour when the temperature of either the primary or secondary coolant < 90*F.

1 l

l l

l CALVERT CLIFFS-UNIT 2 3/4 7-13 Amendment No. 65

-q l

PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPER ATION j

3.7.3.1 At least two component ' cooling water loops shall be OPERABLE. At least one component cooling water heat exchanger shall be operating and the remaining component cooling water heat exchanger may be'in standby.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at.least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 j

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

~

1 SURVEILLANCE REOUIREMEN13 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

J a.

At least once per 31 days by verifying that each valve (manual, power cperated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

.i b.

At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its.

correct position on a Safety injection Actuation test signal.

j 1

CALVERT CLIFFS - UNIT 2 3/4 7-14 Amendment No.

110

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM s

LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent service water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2,- 3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two' loops to OPERABLE' status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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 .

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE At least once per 31 days by verifying that each valve (manual, power a.

t operated or automatic) in the flow path that is not locked, serled, or' otherwise secured in position, is in its correct position, j

b.

At least once per refueling interval during shutdown, by verifying that

. l each automatic valve servicing safety related equipment actuates to its correct position on Safety injection Actuation and Containment Spray Actuation test signals.

CALVERT CLIFFS - UNIT 2 3/4 7-15 Amendment No.[,110 1

l

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]

l PLANT SYSTEMS 3/4.7.5 SALTWATER SYSTEM LIMTITNG CONDITION FOR OPERATION 3.7.5.1 At least two independent saltwater loops shall be OPERABLE.

j q

APPLICABILITY:

MODES 1, 2, 3 and 4.

.]

ACTION:

]

With only one saltwater loop OPERABLE, restore at least two loops to OPERABLE' status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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

-1 in COLD SHUTDOWN within the following 30 hourc.

SURVEILLANCE REOUIREMEN"I3 f

4.7.5.1 At least two saltwater loops shall be OPERABLE.

I a.

At least once per 31 days be verifying that each valve (manual power '

I operated or automatic) in the flow path that is not locked, sealed, or i

otherwise secured in position, is in-its correct position.

b.

At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety 'related equipment actuates to its correct position on a Safety Injection Actuation test signal.

I i

4 No./f,110 -

CALVERT CLIFFS - UNIT 2 3/4 7-16 Amendment :

m

e 0Rhody[0k.

UNITED STATES.

5

+

'[

g-NUCLEAR REGULATORY COMMISSION -

y 7,

j WASHINGTON, 0. C. 20555 y.....,/

b

_ BALTIMORE GAS AND' ELECTRIC COMPANY.

DOCKET NO. 50-317 j

~CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 s

AMENDMENT TO FACILITY OPERATING' LICENSE i

bR-3 e

o 1.

TheNuclearRegulatoryCommission(theCommission)-hahfoundthat:

A.

The applications for amendment by Baltimore Gas'and Electric Company' (the licensee) dated July 31,:0ctober 17 'and November 24, 1986, as supplemented on January 12, February 23, March.24,. April 3, and' l

June 29, 1987, comply with the standards:and requirements of-the-1 Atomic Energy Act of 1954, as amended (the Act):and the Commission's R

rules and regulations set forth in~10'CFR Chapter I;;-

1 i

B.

The facility will operate in conformity.with the application -

j the provisions of the Act, and the rules and regulations of the a

Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering ~ the health

.i and safety of the public, and (ii) that such activities will-be '

q conducted in compliance with the Commission's regulations; q

l D.

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

1 and

~

.j E.

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

l 1

2.

Accordingly, the license is amended by changes to the Technical

]

Specifications as indicated in the attachment to this license i

amendment, and paragraph 2.C.(2) of. Facility Operating License No. DPR-53 is hereby amended to read as follows:

j i

l

.I

______________1._______________.__________________

._ J

o,

i -

l i

1 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.128, are hereby incorporated in the license. 'The licensee shall operate the facility in accordance with'the Technical q

Specifications..

1 3.

This license amendment is effective as of the date of its issuance to be implemented within 30 days.

1 i

FOR THE NUCLEAR REGULATORY COMMISSION

. 1

% L.s o.. C w 1

[

Robert A. Capra, Acting Director

.)

Project Directorate I-1 Division of Reactor Projects,.I/II

.i

Attachment:

l Changes to the Technical 4

Specifications

)

Date of Issuance: November 3, 1987 l

i l

)

.)

I a

i l

l l

.l l

l 11

._a,

---a------,.~a a--x----

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UNITED STATES

)

{.

')

g

' NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D. C 20555

%,***.* /

1 1

. BALTIMORE GAS AND ELECTRIC COMPANY j

DOCXET NO. 50-318~

q CALVERT CLIFFS NUCLEAR' POWER PLANT, UNIT 1 1

AMENDMENT TO FACILITY OPERATING LICENSE

.j Amendment No.110 1

License No. DPR-69 t

i 1.

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

1 A.

The applications for amendment by Baltimore Gas and Electric Company

.l l

(the licensee) dated July 31, October 17 and November 24, 1986,'as; l

supplemented January 12, February 23, March 24, April 3, and June 29, 1987, comply with the standards and-requirements of the Atomic Energy Act of 1954,.as amended (the Act) and the Commission's rules and i

regulations set forth in 10 CFR Chapter It' i

B.

The fdility will operate in confonnity with the~ application, the provisions of the Act, and the rules and regulations of the l

Comission; 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 I

conducted in compliance with the Comission'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; I

and E.

The issuance of this amendment is in accordance with 10 CFR-Part I

51 of the Comission's regulations and all applicable requirements have been satisfied.

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. 0PR-69 is hereby arnended to read as follows:

l

=

R

.k 2

l (2) Technical Specifications The Technical. Specifications contained in Appendices A and B, as revised through Amendment No.110, are hereby incorporated in the license. The licensee shall-I operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuence'.to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION 1

WU 0.. (W Robert A.' Capra, Acting Director Project Directorate I-I j

Division of Reactor Projects, I/II

)

Attachment:

Changes to the Technical i

Specifications j

Date of Issuance: November 3, 1987 i

conu

[

UNITED STATES

'y-p, NUCLEAR REGULATORY COMMISSION 5

j-WASHlNGTON, D. C 20555 3

p$

r ATTACHME'NT TO LICENSE AMENDMENTS AMENDMENT NO. 128 -FACILITY OPERATING LICENSE NO. DPR AMEhDMENT NO, 110 FACILITY OPERATING LICENSE NO. DPR-69 j

DOCKET NOS. 50-317 AND 50-318' Revise Appendix A as f6110ws:

Remove _Pages Insert Pages.

l 3/4 1-9 3/4 1 l 3/4 1-10*

3/4 1-10*

3/4 1-11 3/4 1,

3/4 1-12*

3/4 1-12*'

l 3/4 4-32* (1) 3/4 4-32* (1) 3/4 4-33 (1) 3/44-33(1) i 3/44-33*(2) 3/44-33*(2) 3/4.4-34(2) 3/44-34(2)

)

l 3/4 5-1*

3/4 5-1*

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3/4 5-5 3/4 5-5' 3/4 5-Sa*

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3/4 6-11' 3/4 6-11 1

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l 3/4 6-13

'3/4 6-13 i

3/4 6-14*

-3/4 6-14*

3/4 6-15 3/4 6-15 3/4 6-16*-

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3/4 6-28*

l 3/4 7-13*

3/4 7-13*

3/4 7-14 3/4 7-14 3/4 7-15 3/4 7-15 l

3/4 7-16 3/4 7-16 l

1 l-

Overleaf pages provided to maintain document completeness (1) remove /insertforDPR-53only (2) remove / insert for DPR-69 only l

l

_ _ _ _ _ _ _

ML20236M049

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ML20236M049
Site:	Calvert Cliffs (DPR-53-A-128, DPR-69-A-110)
Issue date:	11/03/1987
From:	Capra R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236M053	List: ML20236M049 ML20236M064
References
NUDOCS 8711120021
Download: ML20236M049 (61)
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ML20236M049

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