Text

Amends 65 & 47 to Licenses DPR-53 & DPR-69,respectively, Changing Operability & Test Requirements for Containment Purge Intake & Exhaust Isolation Valves
	ML20041D281
Person / Time
Site:	Calvert Cliffs
Issue date:	02/01/1982
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20041D283	List: ML20041D281; ML20041D285; ML20041D286;
References
	NUDOCS 8203050131
	Download: ML20041D281 (36)
	v • d • e

'.

8 [+= mu,Io u

8 UNITED STATES 7[

,n NUCLEAR REGULATORY COMMISSION g

/.j WASM NGTON, D. C. 20555

%,o...*/

BALTIMORE GAS AND ELECTRIC COMPANY p

DOCKET NO. 50-317 CALVERT CLfFFS NUCLEAR POWER PLANT UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas & Electric.

Company (the licensee) dated December 7,1981, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonabla assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safcty of the public,'and (ii) that such activities will be conducted in compliance g

with the Commission's regulations; D.

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

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

i.

I 8203050131 820201 l

PDR ADOCK 05000317 l

P PDR

_2_

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2)~ of Facility Operating License No. DPR-53 is hereby amended to read as follows-(2) Technical Specifications The Techr:ical Specificatiens centeined in ~ Appendices A and B, as revised through Amendtrent No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULAT.ORY COMMISSION Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the TechnicaT Specifications Date of Issuance: February 1, 1982 O

ATTACHMENT TO LICENSE AMEN 0 MENT. NO. 65 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3-13 3/46-9a(new) 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-25 i

e o

e 9

l

l TABLE 3.3-3 (Continued)

' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTUMENTATION

=

l

-4 MINIMUM r,

[

TOTAL.NO.

CHANNELS CHANNELS APPLICABLE j}

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 6.

CONTAINTIENT PURGE ji VALVES ISOLATION

-4

-e a.

Manual (Purge Valve Control Switches) 2/ Penetration 1/ Penetration 2/ Penetration 5, 6 8

\\,

b.

Containment Radiation -

High Area Moritor 4

2 3

6 8

7.

LOSS OF POWER us 31 a.

4.16 kv Dnergency Bus Undervoltage (Loss of u)

Voltage) 4/ Bus 2/ Bus 3/ Bus 1,2,3 7*

b.

4.16 kv Dnergency Bus Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

di Eh

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

m

@r

.Ei C?

Of

9 TABLE 3.3-3(Continued) g 9

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION i

P

=

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE a

l FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE' MODES ACTION c_

2 H

8.

CVCS ISOLATION a.

Manual (CVCS 1/ Valve 1/ Valve 1/ Valve I, z, a, 4 6

a f

Isolation Valve Centrol Switches) b.

West Penetration 4

2 3

1,2,3,4 7

Room / Letdown Heat mp Exchanger Room Pressure - High m

.L-

^

3.

AUXILIAr'l FEED'JATER y,

a.

Manual 2

1 2

1,2,3 6

I E

b.

Steam Generator Level Low 4

2 3

1,2,3 7

g.

l f

g I

e l

=

l l

m____

4 CONTAINMENT SYSTEMS

_SL'RVEILLANCE REQUIREMENTS (Continued) b.

Removing one uire from each of a dome, vertical and. hoop tendon checked for 1 ft off force and determining that over the entire length of the removed wire that:

1.

The tendon wires are free of corrosion.

2.

There are no changes in physical appearance of the sheathinq filler grease.

3.

A minimu.n tensile strength value of 240 Ksi (guaranteed ultimate strength of the tendon material) for at least three wire samples (one from each end and one at mid-length) cut from each removed wire.

Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.

4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchcrage concrete exterior surfaces or tne concrete crack patterns adjacent to the end anchorages.

Inspections of the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure.

4.6.1.6.3 Liner Plate The structural integrity of the containment liner plate shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.~2) by a visual inspection of the plate and verifying no apparent changes in appearance or other abnormal degradation.

4.6.1.6.4 Reports Any abnormal degradation of the containment structure detected during the above required tests and inspections shall be reported to the Commission pursuant to Specification 6.9.1.

This report shall include a description of tLe tendon condition, the condition of the concrete (especially at terdon anchorages), the inspection procedure, the tolerances on cracking, and the corrective actions taken.

j CALVERT CLIFFS - UNIT 1 3/4 6-9

CONTAINMENT SYSTEMS ENTAINMENT PURGE SYSTEM LIMITING CONDITION FOR OPERATION

3. 6.1. 7 The containment purge supply and exhaust isolation valves shall be closed by isolating air to the air operator and maintaining the solenoid air supply valve deenergized.

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

With one containment purge supply and/or one exhaust isolation valve open, a.

close the open valve (s) within one hour or be in at least H0T 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 .

b.

With one containment purge supply valve inoperable due to high leakage, repair the valve (s) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.7 The 48-inch cont'ainment purge supply and exhaust isolation valves shall be determined closed at least once per 31 days, by verifying that power to the solenoid valve is removed.

CALVERT CLIFFS - UNIT 1 3/4 6-9a Amendment No.6 5 s

to CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a Containment Spray Actuation Signal ~and Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.

Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY: MODES 1, 2, and 3*.

ACTION:

With one containment spray, system inoperable, restore the inoperable 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 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 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERA 3LE' shutdown cooling heat exchangar is established.

Verifying)that each valve (manual, power operated orin the i

2.

automatic from the RWT on a Containment Pressure-High test signal.

3 l

With pressurizer pressure > 1750 psia.

t 1

CALVERT CLIFFS - UNIT 1 3/4 6-10

0 CONTAINMENT SYSTEMS t

3/4.6.4 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolaticn times as shown in Table 3.6-1.

APPLICABILITY,: M00ES 1, 2, 3 and 4.

ACTION:

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

Restore the inoperable valve (s) to OPERABLE status within 4 a.

hours, or 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 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 .

SURVEILLANCE REQUIREMENTS 4.6.4.1.1 The isolation valves specified in Table 3.6-1 shall be demon-strated 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.

CALVERT CLIFFS - UNIT 1 3/4 6-17

3 CONTAINMENT SYSTEMS SURVEILLANCE REQUIRI.MENTS (Continued) 4. 6. 4.1. 2 Each isolation valve specified in Table 3.6-1 shall be demonstrated f

OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by; Verifying that on each containment isolation Channel A or Channel B a.

test signal, each required isolation valve actuates to its isolation position.

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, Verifying that on each Safety Injection Actuation Channel' A or c.

Channel B test signal, each required isolation valve actuates to its isolation position.

4. 6. 4.1. 3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within.its limit when tested pursuant to Technical Specification 4.0.5.

4. 6. 4.1. 4 Containment purge isolation valves shall be demonstrated OPERABLE at least once every 6 months 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. The leakage rate for the containment purge isolation valves shall also be compared to the previously measured leakage rate to detect excessive valve degradation.

CALVERT CLIFFS - UNIT 1 3/4 6-18 Amendment No. 6 5 a

TABLE 3.6-1 n?

8 CONTAINt1ENT ISOLATION VALVES

'8 PENETRATION ISOLATION ISOLATION VALVE ISOLATION E

NO.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECONDS) n 3*

1A SIAS A CV-5465 R.C. and Pressurizer Sampling

<7 SIAS A CV-5466 3

SIAS A CV-5467 17 p

SIAS B CV-5464 17 1B SIAS A CV-2180 Containment Vent Header

'4aste

<7

~

SIAS B CV-2181 Gas 3

1C SIAS A CV-506 RCP Seals Controlled Bleedoff

~<7 SIAS B CV-505 7

t' a

?

10 SIAS B SV-6529 0xygen Sample 17 G

2A SIAS A CV-515 Letdown Line

<l 3 SIAS B CV-516 71 3

~A N

NA 7113 - 1 NA 7M3-1 NA '

F B

g-2B NA CV-517 Charging Line NA g

NA CV-518 NA NA CV-519 NA

~~

g NA SP-210M3-2 NA NA 210M3-2 NA m

CJ1 d

TABLE 3.6-1 (Continued) n CONTAINMENT ISOLATION VALVES

=

[

PENETRATION ISOLATION.

ISOLATION VALVE ISOLATION r-NO.

CHANNELS IDENTIFICATION NO.

FUNCTION TIME (SECONDS)

~n

~5 7A NA Blind Flange ILRT NA NA NA 19-1 E

~

NA

[

7B NA Blind Flange ILRT NA NA 19-1 i

8 SIAS A MOV-5462 Containment Normal Sump

<l 3 SIAS B MOV-5463

<13

.R 9

NA 238M3-1 Containment Spray NA NA m

NA 238M3-2 B

10 NA 238M3-1 Containment Spray NA NA 238M3-2 NA 1

SIAS A, CRS A CV-1410 (3)

Purge Air Inlet

<7**

I

[

SIAS B, CRS.B CV-1411 (3)'

D**

I h

i E

O CM 1

.~

TABLE 3.6-1 (Continued)

)

r-

E CONTAINMENT ISOLATION VALVES 25 ISOLATION-PENETRATION ISOLATION.

ISOLATION VALVE E;

NO.-

CHANNELS IDENTIFICATION NO.

FUNCTION TIME (SECONDS) c3 4

14 5IAS A. CRS A CV-1412 (3)

Purge Air Outlet 5.7**

7$ **

SIAS B, CRS B CV-1413 (3)

E Z

<7 15 SIAS A CV-5291 Purge Air Monitor

_7_7 SIAS B CV-5292 16 CIS A CV-3832 Component Cooling Water Inlet

$18 4

1 18 CIS B CV-3833 Component Cooling Water Outlet

$18 r

?'

5 19A NA 223-1 Instrument Air NA CIS A M0V-2080

$13 19B NA 19-2

Plant Air NA NA NA -

130-1

h*

NA j!

20A NA 223-1 Nitrogen Supply NA 8t NA CV-612

NA.

j!

NA CV-622

NA NA CV-632

NA if NA CV-642

o

@)

M

TABLE 3.6-1 (Continued) n?

C0fiTAltMENT ISOLATION VALVES 4

ISOLATION PENETRATION ISOLATION ISOLATION VALVE C

NO.

CHANNEL IDENTIFICATION NO.

FUNCTI'ON TIME _(SECONDS) n

~4 NA NA 223-1 Nitrogen Supply

'e 20B NA NA 223-2 E

NA M

20C flA 223-1 Nitrogen Supply NA NA 223-2 23-SIAS A CV-4260 R.C. Drain Tank Drains

<J d

24 SIAS B SV-6531 0xygen Sample Line

<J

.n.

?

NA y

37 NA 29-1 Plant Water NA NA 142-1 38 NA CV-5460

Demineralized Water NA y

39 NA 130M3-1 Safety Injection Tank Test Line NA NA NA 130M3-2 g

8" 41 NA MOV-652 (2)

Shutdown Cooling NA NA g

NA MOV-651 (2) m us

i TABLE 3.6-1 (Continued) jf 1b CONTAINiiENT ISOLATION VALVES Ej ISOLATION O

PENETRATION ISOLATION ISOLATI0ft VALVE NC.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECONDS) s' 44 NA 238-1 Fire Protection NA NA c:

NA 238-1 NA E5 NA MOV-6200 *

-i NA 47A NA SV-6540A Hydrogen Sample Outlet

- NA NA SV-6507A 47B NA SV-6540E Hydrogen Sample Outlet NA NA 10 '

NA SV-6507E o.

T E$

47C NA SV-6540F Hydrogen Sample Outlet NA NA NA SV-6507F 470 NA SV-6540G Hydrogen Sample Return NA NA NA SV-6507G Ng 48A NA MOV-6900 Hydrogen Purge Outlet NA NA NA MOV-6901

' cp m

rt if b

Ln 1

4 e

d

TABLE 3.6-1 (Continued) h CONTAINMENT ISOLATION VALVES 3

ISOLATION P

PENETRATION ISOLATION' ISOLATION VALVE TIME (SECONDS)

^

9 NO.

CHANNEL IDENTIFICATION N0.

FUNCTION

- 3 NA e

48B NA 238-1 Hydrogen Purge Inlet NA NA MOV-6903 c

w NA 49A NA SV-6540B Hydrogen Sample

~

NA NA SV-65078 i

NA 49B NA SV-6540C Hydrogen Sample NA NA SV-6507C R

NA 49C NA SV-65400 Hydrogen Sample NA cn NA SV-65070 g

NA i

1 50 NA Blind Flange ILRT NA NA Blind Flange NA 59 NA 29M3-1 Refueling Pool Inlet NA g

NA 29M3-1 to g

Steam to Reactor Head Laydown' NA k

60 NA 130-2 NA NA 19-1 g

Q

e TABLE 3.6-1 (Continued)

CONTAINf1ENT ISOLATION VALVES ISOLATION b

PENETRATION ISOLATION ISOLATION VALVE TIME (SECONDS)

NO.

CHANNEL IDENTIFICATION 110.

FUNCTION NA 61 NA 76Y-1 Refueling Pool Outlet NA NA 293ff-l NA NA 293M-1 NA E

NA 293t1-1 H

62 SIAS A MOV-6579 Containment Heating Outlet

<l3 64 NA 238-1 Containment Heating Inlet NA (1) Manual or remote manual valve which is closed during plant operation.

.g

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

l (3) Containment purge isolation valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7.

May be open on an intermittent basis under administrative control.

- Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during which time Isolation time is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7 during which these valves may be opened.

g time these valves must remain closed.

h O

tJ1

CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN ANALY2ERS LIMITING CONDIT 0N FOR OPERATION 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen analyzer inoperable *, restore the inoperable analyzer l

[

to OPERABLE status within 30 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

SURVEILLANCE REQUIREMENTS Ea'ch hydrogen analyzer shall be demonstrated OPEPABLE at least 4.6.5.1 once per 92 days on a STAGGERED TEST BASIS t,y performing a CHANNEL CALIBRATIDN using sample gases containing:

Zero' volume percent hydrogen, balance nitrogen, and a.

Three vo10me percent hydrogen, balance nitrogen.

b.

Until August 1,1982, one hydrogen analyzer may be made inopercole, at any given time, for the purpose of performing modifications relating to THI Action Plan Item II.F.1 6.

During this time, Specification 3.0.4 is not applicable to this requirement.

4 Amendment No. 60 CALVERT CLIFFS - UNIT 1 3/4 6-26 l

?!

1 auc uq)g UNITED STATES NUCLEAR REGULATORY COMMISSION

[

g WASHINGTON, D. C. 20555 3

j

%,.....)

BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACIt.ITY OPERATING LICENSE Amendment No. 47 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated December 7,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) ahd the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

F P' 9-

._ 2.

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

(2) Technical Specifications The Technical Specifications ' contained in Appendices A and B, as revised through Amendment No. 47, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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

Attachment:

Changes to the Technical. Specifications Date of Issuance: February 1, 1982

-r

l l

l ATTACHMENT TO LICENSE AMENDMENT NO. 4 7 FACILITY OPERATING LICENSE NO. DPR-69 i

DOCKET NO. 50-318 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf,pages are also provided to maintain document completeness.

Pages 3-13 3/4 6-9a (new) 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4.6-23~

3/4 6-24 3/4 6-25 4

0 B

4

TABLE 3'.3-3 (Continued)

ENGINEERED SAFETY FEATURE' ACTUATION SYSTEM INSTRUMENTATION MINIMUM n

TOTAL NO.

CHANNELS CHANNELS APPLICABLE gj FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

?!

n

~^

6.

CONTAINMENT PURGE 8

VALVES ISOLATION.##

Th v'

a.

Manual (Purge Valve Control Switche's) 2/ Penetration 1/ Penetration 2/ Penetration 5, 6 8

~

SE b.

Containment Radiation q

High Area Monitor 4

2 3

6 8

n, jh 7.

LOSS OF POWER a.

4.16 kv Emergency Bus Undervoltage (Loss of Voltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

w b.

4.16 kv Emergency Bus Undervoltage (Degradsd Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

B" '

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

g E

a n

sib N

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUM5NTATION I$

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE b~

MODES ACTION q

OF CHANNELS TO TRIP OPERABLE FUNCTIONAL UNIT vs

8..CVCS ISOLATION gj Z

v,{+; a. Manual (CVCS Control Switches) 1/ Valve 1/ Valve 1/ Valve 1,2,3,4 6

Isolation Valve y

b.

West Penetration lj Room / Letdown Heat Exchanger Room 2

3 1,2,3,4 7*

Pressure - High 4

w 3:

9.

AUXILIARY FEE 0 WATER 2

1 2

1,2,3 6

w la a.

Manual Level - Low 4

2 3

1,2,3 7

b.

Steam Generator

?.

a g.

Br W$

53 m

n-se se ses e o w

e o

e q

m

CONTAINMENT SYSTEMS,

SURVEILLANCE REQUIREMEllTS (Continued)

-Liner Plate The structural integrity of the containment 4.6.1.6.3 liner plate shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the plate and verifying no apparent changes in appearance or other abnormal degradation.

4.6.1.6.4 Reports Any abnormal degradation of the containment structure detected during the above required tests and inspections shall be reported to the Commission pursuant to Specification 6.9.1.

This r.eport shall j

include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedure, the tolerances on cracking, and the corrective actions taken.

4 5

0

).

5 2

4 CALVERT CLIFFS'- UNIT 2 3/4 6-9 1

f

CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEM i

LIMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust isolation valves shall be closed by isolating air to the air operator and maintaining the solenoid air supply valve deenergized.

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

With one containment purge supply and/or one exhaust isolation valve open, a.

close the open valve (s) within one hour 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 .

b.

With one containment purge supply valve inoperable due to high leakage, repair the valve (s) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.7 The 48-inch containment purge supply and exhaust-isolation valves shall be determined closed at least once per 31 days, by verifying that power to the solenoid valve is removed.

CALVERT CLIFFS - UNIT 2 3/4 6-9a Amendment No 4 7 f

(

l CONTAINMENT SYSTEMS l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTIM_

LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with l

each spray system capable of taking suction from the RWT on a Containment Spray Actuation Signal and Safety Injection Actuation Signal and automati-cally transferring suction to the containment sump on a Recirculation Actuation Signal. Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY: MODES 1, 2, and 3*.

ACTION:

With one containment spray system inoperable, restore the inoperable 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 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 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

Verifying)that each valve (manual, power operated orin the flow path is pos 2.

automatic from the RWT on a Containment Pressure-High test signal.

With pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 2 3/4 6-10

CONTAINMENT SYSTEMS i

3/4.6.4 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.

APPLICASILITY: MODES 1, 2, 3 and 4.

ACTION:

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

Restore the inoperable valve (s) to OPERABLE status within 4 a.

hours, or 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 b.

least one deactivated automatic valve secured in the isolation position, or c.

Ifrolate 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 .

f SURVEILLANCE REQUIREMENTS The isolation valves specified in Table 3.6-1 shall be demon-4.6.4.1.1 strated 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.

CALVERT CLIFFS - UNIT 2 3/4 6-17 I

ur e-

l t

l i

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

Each isolation valve specified in Table 3.6-1 shall be demonstrated

4. 6. 4.1. 2 OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

Verifying that on each containment isolation Channel A or Channel B a.

test signal, each required isolation valve actuates to its isolation

position, 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.

Verifying that on each Safety Injection Actuation Channel A or c.

Channel B test signal, each required isolation valve actuates to its isolation position.

4. 6. 4.1. 3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Technical Specification 4.0.5.

4.6.4.1.4 Containment purge isolation valves shail be demonstrated OPERABLE at least once every 6 months 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 th'an or equal to 0.60 La. The leakage rate for the containment purge isolation valves shall also be compared to the previously measured leakage rate to detect excessive valve degradation.

.4 CALVERT CLIFFS - UNIT 2 3/4 6-18 Amendment No. 4 7 4

TABLE 3.6-1 g

CONTAINitENT ISOLATION VALVES a

' ISOLATION VALVE ISOLATION PENETRATION ISOLATION C

NO.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECONDS) n 5

1A SIAS A CV-5465 R.C. and Pressurizer Sampling 17 SIAS A CV-5466 E

SIAS A CV-5467 O

SIAS B CV-5464 ro IB SIAS A CV-2180 Containment Vent Header to Waste

<7

~7 1

SIAS B CV-2181 Gas 1C SIAS A CV-506 RCP Seals Controlled Bleedoff

<7 R

SIAS B CV-505 57 a

7' G

10 SIAS B SV-6529 0xygen Sample 17 2A SIAS A CV-515 Letdown Line

<l3 71 3 SIAS B CV-516 NA 7f13-1 NA NA 7M3-1 NA E

m h

2B NA CV-517 Charging Line NA NA CV-518 NA 5

NA CV-519 NA

=

NA SP-210M3-2 NA P

NA 210M3-2 NA

.r.

I i

r

TABLE 3.6-1 g

r-CONTAINt1ENT ISOLATION VALVES y

PENETRATION ISOLATION ISOLATION VALVE ISOLATION C

NO.

CHANNEL IDENTIFICATION NO.

F' UNCTION TIME (SECONDS) lA SIAS A CV-5465 R.C. and Pressurizer Sampling 17 n

SIAS A CV-5466 E

SIAS A CV-5467 Z

SIAS B CV-5464 m

18 SIAS A CV-2180 Containment Vent Header to Waste

<7 SIAS B CV-2181 Gas 57 1C SIAS A CV-506 RCP Seals Controlled Bleedoff

<7 77 R

SIAS B CV-505 a

T G

ID SIAS B SV-6529 0xygen Sample 17 2A SIAS A CV-515 Letdown Line

<l3 71 3

-SIAS B CV-516

'NA NA 7t13-1 NA NA 7M3-1 b'

a 2B NA CV-517 Charging Line NA NA CV-518 NA NA CV-519 NA E

NA S P-210M3-2 NA NA NA 210M3-2

TABLE 3.6-1 (Continued) 9G CONTAINMENT ISOLATION VALVES E

ISOLATION H

PENETRATION ISOLATION ISOLATION VALVE l2 NO.

CHANNELS IDENTIFICATION-NO.

FUNCTION TIME (SEC0hDS)

' T NA a

7A

.NA Blind Flange ILRT NA NA 19-1 E

U 7B NA Blind Flange ILRT NA NA N

NA 19-1 I

8 SIAS A MOV-5462 Containment Normal Sump

<l 3

<l3 SIAS B H0V-5463 9-NA.

238M3-1 Containment Spray NA NA

_NA 238M3-2 b

10 NA-238M3-1 Containment Spray NA NA NA 23.8M3-2 i

13 SIAS A. CRS A CV-1410 (3)

Purge Air Inlet

<7**

7**

y SIAS B, CRS B CV-1411 (3) a R

Sn i

~

i an l

M 1

0 4

TABLE 3.6-1 (Continued) 9 G

CONTAINMENT ISOLATION VALVES 9

ISOLATION

~i PENETRATION ISOLATION ISOLATION VALVE P

NO.

CHANNELS IDEllTIFICATION NO.

FUNCTION TIME (SECONDS) tb

<7**

U 14 SIAS A, CRS A CV-1412 (3)

Purge Air Outlet SIAS B, CRS B CV-1413 (3) 7_7**

E

<7 15 SIAS A CV-5291 Purge Air Monitor

~d 57 SIAS B CV-5292 16 CIS A CV-3832 Component Cooling Water Inlet

$18 18 CIS B-CV-3833 Component Cooling Water Outlet

$18

,3g s.

c,

'a 19A

!!A 223-1 Instrument Air NA CIS A MOV-2080

$13

~

19B NA 19-2

Plant Air NA NA NA 130-1

R 20A NA 223-1 Nitrogen Supply NA NA m

5 NA CV-612

NA 5

NA CV-622

NA 5

NA CV-632

NA NA CV-692

e

.r.

N

ThBLE 3.6-1 (Continued) 9 CONTAINMENT ISOLATION VALVES l

hj t

ISOLATION PENETRATION ISOLATION ISOLATION VALVE TIME (SECONDS)

P NO.

CHANNEL IDENTIFICATION NO.

FUNCTION j

ui 20B NA 223-1 Nitrogen Supply NA NA 223-2

~

NA i

E 20C NA 223-1 Nitrogen Supply NA

-d NA

.NA 223-2 j

(~

23 SIAS A CV-4260 R.C. Drain Tank Drains

$7 24 SIAS B SV-6531

~ 0xygen Sample Line 37

)$

37 NA 29-1 Plant Water NA

(

NA l

NA 142-1 m,

N i

'38 NA CV-5460

Demineralized Water NA i

39 NA 130M3-1 Safety Injection Tank Test Line NA NA g7 NA 130M3-2 El I,

5 l

5 41 NA MOV-652 (2)

Shutdown Cooling NA NA NA MOV-651 (2) z P

a~

M J

52 TABLE 3.6-1 (Continued)

G E!

CONTAINt!ENT ISOLATION VALVES

[]

PENETRATION ISOLATION ISOLATION VAEVE ISOLATION i

NO.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECONDS) a i

44 NA 238-1 Fire Prot'ection NA NA c-NA 238-1 i43 0;

NA MOV-6200

a N

47A NA SV-6540A Hydrogen Sample Outlet NA NA SV-6507a NA 478 NA SV-6540E Hydrogen Sample Outlet NA NA SV-6507E NA R

a m

47C NA SV-6540F Hydrogen Sample Outlet NA

{;

NA SV-6507F NA 47D NA SV-6540G Hydrogen Sample Return NA NA SV-6507G NA II 48A NA MOV-6900 Hydrogen Purge Outlet NA NA MOV-6901 NA E

F 9

=%

'J

El TABLE 3.6-1 (Continued)

G9 CONTAINMENT ISOLATION VALVES

-4 p

PENETRATION ISOLATION ISOLATION VALVE ISOLATION q

NO.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECONDS)

.5 Hydrogen Purge. Inlet NA 488 NA 238-1 NA MOV-6903 NA c

2 Z

^*.

49A'

' NA SV-6540B Hydrogen Sample NA NA' SV-6507B NA 49B NA SV-6540C

' Hydrogen Sample NA NA SV-6507C NA

- k2 l-49C-NA SV-6540D Hydrogen Sample NA A3 NA.

-SV-6507D NA a

50 NA Blind Flange ILRT NA.

NA.

Bl.ind Flange NA 29M3-1 Refueling Pool Inlet NA 59 NA.

f(

' NA 29H3-1 NA o

~ Steam to' Reactor Head Laydown NA

~60

'NA' l130-2

=

2 FA 19-1 NA

.is.

a

TABLE 3.6-1 (Continued)_

,.]

CONTAINitENT ISOLATION VALVES-

\\

9&

ISOLATION 9

PENETRATION ISOLATION ISOLATION VALVE TIME (SECONDS)

NO.

CHANNEL IDENTIFICATION N0.

FUNCTION P

Refueling Pool Outlet NA M

61 NA 76Y-1 NA 5

NA 293M-1 NA

(

NA 293M-1 NA l

e I

NA 293ft-1 c

G

<13 62 SIAS A MOV-6579 Containment Heating Outlet l

L NA 64 NA 238-1 Containment Heating Inlet Manual or remote manual valve which i.s closed during plant operation.

(1) w2 l

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

p l

Containment purge isolation valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7.

(3)

May be open on an intermittent basis under administrative control.

- Containment purge' isolation valves isolation times will only apply for MODES 5 and 6 during which time Isola tion time' is NA for MODES.1, 2, 3 and 4 per TS 3/4 6.1.7 during which s

these valves may be opened.

time these. valves must remain closed.

E n

g b

J q

r

l l

CONTAlhMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL l

HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen analyzer inoperable *, restore the inoperable analyzer

[

to OPERABLE status within 30 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 .

SURVEILLANCE REQUIREMENTS 4.6.5.1 Each' hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:

Zero volume percent hydrogen, balance nitrogen, and a.

b.

Three volume percent hydrogen, balance nitrogen.

Until August 1,1982, one hydrogen analyzer may be made inoperable, at I

any given time, for the purpose of performing modifications relating to

_ Tlil Action Plan Item II.F.1.6.

During this time, Specification 3.0.4 i

is not applicable to this requirement.

CALVERT CLIFFS - UNIT 2 3/4 6-26 Amendment No. 42 k

e

<

ML20041D281

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