ML060400035

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Units, 1 and 2 - Tech Spec Pages for Amendment 271 and 153 Containment Conversion from Subatmospheric to Atmospheric Operating Conditions
ML060400035
Person / Time
Site: Beaver Valley
Issue date: 02/06/2006
From:
Plant Licensing Branch III-2
To:
References
TAC MC3394, TAC MC3395
Download: ML060400035 (25)


Text

V' 71,~e TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.

OF CHANNELS MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE FUNCTIONAL UNIT

1.

SAFETY INJECTION AND FEEDWATER ISOLATION

a. Manual Initiation
b. Automatic Actuation Logic
c. Containment Pressure-High
d. Pressurizer Pressure-Low
e. Steamline Pressure-Low 2

2 1

1 2

2 2

2 ALLOWABLE VALUE Not Applicable Not Applicable

  • 5.33 psig

> 1841 psig APPLICABLE MODES 1,

2, 3,

4 1,

2, 3,

4 1,

2, 3

1, 2,

3(1) 1, 2,

3(1)

ACTION 18 13, 36 3

2 14 I

3 2

14 14 3/loop 2/loop 2/loop 2 495.8 psig steam any loop any loop line pressure BEAVER VALLEY - UNIT 3

3/4 3 -15 Amendment No. 271

sI *dt TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.

OF CHANNELS MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE FUNCTIONAL UNIT ALLOWABLE VALUE APPLICABLE MODES ACTION 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RE-CIRCULATION MODE

a. Manual Initiation 2 sets 2 switches/

set 1 set 2 sets Not Applicable 1, 2, 3, 4 18

b. Automatic Actuation Logic Coincident with Safety Injection Signal
c. Refueling Water Storage Tank Level-Low 2

1 2

3 Not Applicable 2 13' 9" and

< 14' 4" 1,

2, 3

1, 2, 3 4,

2 18 16 BEAVER VALLEY -

UNIT 1 3/4 3 -16 Amendment No.271

.1 :

1 -

ENGI FUNCTIONAL UNIT

2.

CONTAINMENT SPRAY

a. Manual
b. Automatic Actuation Logic
c. Containment Pressure--

High-High

3.

CONTAINMENT ISOLATION

a. Phase "A" Isolation
1) Manual
2) From Safety Injection Automatic Actuation Logic
b. Phase "B" Isolation
1) Manual
2) Automatic Actuation Logic
3) Containment Pressure--High-High TABLE 3.3-3 (Continued)
NEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS ALLOWABLE OF CHANNELS TO TRIP OPERABLE VALUE 2 sets 2

4 2

2 2 sets (2 switches/

set) 2 4

1 set 2 switches 1

2 1

1 1 set 1

2 2 sets Not Applicable 2

Not Applicable 3

  • 11.43 psig 2

Not Applicable 2

Not Applicable 2 sets Not Applicable 2

Not Applicable 3

< 11.43 psig APPLICABLE MODES 1,

2, 3,

4 1, 2, 3, 4 1, 2, 3 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3 ACTION 18 13 16 18 13 18 13 16 BEAVER VALLEY -

UNIT 1 3/4 3-17 Amendment No 271

l.

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE ALLOWABLE VALUE APPLICABLE MODES FUNCTIONAL UNIT ACTION

4.

STEAM LINE ISOLATION

a. Manual 2/steam line 1/steam 2/operat-line ing steam line Not Applicable 1, 2, 3 18
b. Automatic Actuation Logic
c. Containment Pressure Intermediate -High-High
d. Steamline Pressure-Low
e. Steamline Pressure Rate-High Negative 2

1 2

2 Not Applicable

< 7.33 psig 1, 2, 3 1, 2, 3 13 3

2 14 I

3I/3oop 3/loop 2/loop 2/loop any loop any loop 2/loop 2/operat-any loop ing loop

> 495.8 psig steam line pressure

< 104.2 psi with a time constant 2 50 seconds 1, 2, 3(1) 14 3(2) 14

5.

TURBINE TRIP & FEEDWATER ISOLATION

a. Steam Generator Water Level--High-High, P-14 3/loop 2 loop in any operating loop 2/loop in each operating loop

2, 3

14 BEAVER VALLEY - UNIT 1 3/4 3 -18 Amendment No. 271

TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REOUIRED

1. SAFETY INJECTION AND FEEDWATER ISOLATION
a.

Manual Initiation

b.

Automatic Actuation Logic

c.

Containment Pressure-High

d.

Pressurizer Pressure--Low

e.

Steam Line Pressure--Low N.A.

N.A.

S S

S N.A.

N.A.

Re2> (3)

R R

R M(l)

Q 42 (3)

Q Q

1, 2, 3, 1, 2, 3, 1,

2, 3

1, 2, 3 1, 2, 3 4

4 I

BEAVER VALLEY -

UNIT 1 3/4 3 -29 Amendment No.271

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL UNIT 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE

a.

Manual Initiation

b.

Automatic Actuation Logic Coincident with Safety Injection Signal

c.

Refueling Water Storage Tank Level-Low CHANNEL FUNCTIONAL TEST R

M(1)

Q (2,.3.

MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, 3, 4 1, 2, 3 1, 2, 3 N.A.

N.A.

N.A.

N.A.

S R"'

2 ) 3 I

l

2.

CONTAINMENT SPRAY

a.

Manual Initiation N.A.

b.

c.

Automatic Actuation Logic Containment Pressure-High-High N.A.

S N.A.

N.A.

Ra l2 3)

R MU)

Q 12)13) 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3 I

BEAVER VALLEY -

UNIT 1 3/4 3-29a Amendment No.271

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT

3.

CONTAINMENT ISOLATION

a.

Phase "A" Isolation

1)

Manual

2)

From Safety Injection Automatic Actuation Logic

b.

Phase "B" Isolation

1)

Manual

2)

Automatic Actuation Logic

3)

Containment Pressure--High-High CHANNEL CHECK N.A.

N.A.

N.A.

N.A.

S CHANNEL CALIBRATION N.A.

N.A.

N.A.

N.A.

R(2) (3)

CHANNEL FUNCTIONAL TEST R

MMl R

M )(3 Q(2) (3)

MODES IN WHICH SURVEILLANCE REOUIRED 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3 I

BEAVER VALLEY -

UNIT 1 3/4 3 -30 Amendment No.- 271

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL UNIT

4.

STEAM LINE ISOLATION

a.

Manual

b.

Automatic Actuation Logic

c.

Containment Pressure--Intermediate-High-High

d.

Steamline Pressure--Low

e.

Steamline Pressure Rate-High Negative

5.

TURBINE TRIP & FEEDWATER ISOLATION

a.

Steam Generator Water Level--High-High

6.

LOSS OF POWER

a.

4.16kv Emergency Bus Under-voltage (Loss of Voltage) Trip Feed & Start Diesel

b.

4.16kv and 480v Emergency Bus Undervoltage (Degraded Voltage)

CHANNEL FUNCTIONAL TEST R

Q(2) (3)

MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, 3 1, 2, 3 1,

2, 3

N.A.

N.A.

S N.A.

N.A.

R (2) 43)

I S

S R

R S

R Q

Q Q

Q Q

1, 2,

3 1, 2, 3 1, 2, 3 1,

2, 3,

4 1, 2, 3, 4 N.A.

R N.A.

R BEAVER VALLEY -

UNIT 1 3/4 3 -31 Amendment No. 271

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

a.

By performing the following air lock leakage rate testing at the frequency specified in the Containment Leakage Rate Testing Program:

1.

Verify no detectable seal leakage when the gap between the door seals is pressurized for at least 2 minutes to:

a)

Personnel air lock > Pa (43.3 psig).

b)

Emergency air lock > 10.0 psig.

or, quantify(7) the air lock door seal leakage to ensure that the leakage rate is < 0.0005 La when tested at > Pa (43.3 psig) for, the personnel air lock and < 0.0005 La when tested at 2 10.0 psig for the emergency air lock.

2.

Conduct the overall air lock leakage tests, (8) at 2 Pa (43.3 psig), and verify the overall air lock leakage rate is < 0.05 La when tested at 2 Pa (43.3 psig):

a)

At the frequency specified in the Containment Leakage Rate Testing Program, and b)

Following maintenance performed on the outer personnel air lock door which may result in a decrease in closure force on any part of the door sealing surface.

b.

At least once per 18 months during shutdown by verifying that only one door in each air lock can be opened at a time.

(7) An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

(8) Results shall be evaluated against the acceptance criteria applicable to LCO 3.6.1.2.

BEAVER VALLEY - UNIT 1 3/4 6-5b Amendment No. 271

CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Containment internal air pressure shall be 2 12.8 psia and

< 14.2 psia.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment internal air pressure not within the above limits, restore the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS I

4.6.1.4 The containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I BEAVER VALLEY -

UNIT 1 3/4 6-6 (next page is 3/4 6-8)

Amendment No.271 I

CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5

< 1050F.

Containment average air temperature shall be 2 70'F and APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment average air temperature not within the above limits restore the average air temperature to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS I

4.6.1.5 The containment average air temperature shall be determined to be within limits at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

BEAVER VALLEY -

UNIT 1 3/4 6-8 (next page is 3/4 6-10)

Amendment No.271 I

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c.

At least once per 6 months by:

1.

Verifying the contained solution volume in the tank, and

2.

Verifying the concentration of the NaOH solution by chemical analysis.

d.

At least once per 18 months, during shutdown, by:

1.

Cycling each valve in the chemical addition system flow path that is not testable during plant operation, through at least one complete cycle of full travel.

2.

Verifying that each automatic valve in the flow path actuates to its correct position on a test signal.

3.

Verifying that each chemical injection pump starts automatically on a test signal.

BEAVER VALLEY -

UNIT 1 3/4 6-16 Amendment No.271-'

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued),:,

b.

With one or more penetration flow paths with two containment isolation valves inoperable, isolate the affected penetration flow path within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With one or more penetration flow paths with one containment isolation valve inoperable, isolate the affected penetration flow path within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange; and verify the affected penetration flow path is isolated at least once per 31 days.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.3.1 Each containment isolation valve shall be demonstrated OPERABLE*:

a.

By verifying each purge supply and exhaust valve is deactivated in the closed position at least once per 31 days for valves outside containment and prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for valves inside containment.

b.

By verifying, at the frequency specified in the Inservice Testing Program, the isolation time of each automatic power operated containment isolation valve that is not locked, sealed, or otherwise secured in position, and required to be closed during accident conditions, is within limits.

c.

By verifying, at least once per 18 months, each automatic power operated containment isolation valve that is not

locked, sealed, or otherwise secured in position, and required to be closed during accident conditions, actuates to the isolation position on an actual or simulated actuation signal.

Locked or sealed closed valves, except for the containment purge supply and exhaust valves, may be opened on an intermittent basis under administrative control.

BEAVER VALLEY - UNIT 1 3/4 6 -18 Amendment No.271

ADMINISTRATIVE CONTROLS OFFSITE DOSE CALCULATION MANUAL (ODCM)

(Continued)

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

6.16 Moved to the PROCESS CONTROL PROGRAM.

6.17 Containment Leakage Rate Testinq Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and t1 CFR 50, Appendix J, Option B, as modified by approved exemptions This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, except that the next Type A test performed after the May 29, 1993 Type A test shall be performed no later than May 28, 2008.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 43.3 psig.

The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.

Leakage Rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is < 1.0 La for the overall Type A leakage test and < 0.60 La for the Type B and Type C tests on a minimum pathway leakage rate (MNPLR) basis.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria 51re

< 0.60 La on a maximum pathway leakage rate (MXPLR)') basis for Type B and Type C tests and < 0.75 La for Type A tests.

(1) Exemptions to Appendix J of 10 CFR 50 dated November 19, 1984, December 5, 1984, and July 26, 1995.

(2) For penetrations which are isolated by use of a closed valve(s),

blind flange(s), or de-activated automatic valve(s), the MXPLR of the isolated penetration is assumed to be the measured leakage through the isolation device(s).

BEAVER VALLEY -

UNIT 1 6-25 Amendment No.271

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE ALLOWABLE VALUE APPLICABLE MODES ACTION

1.

SAFETY INJECTION AND FEEDWATER ISOLATION

a. Manual Initiation
b. Automatic Actuation Logic and Actuation Relays
c. Containment Pressure-High
d. Pressurizer Pressure-Low 2

1 2

1 2

2 2

2 N.A.

N.A.

< 5.3 psig

> 1852 psig 1, 2, 3, 4 18 13, 36 1, 2, 3, 4 3

3 2

2 1, 2, 3 3

14 I

14

e. Steamline Pressure-Low 3/loop 2/loop 2/oper-any loop ating loop 2 494 psig*

14 1.1 SAFETY INJECTION-TRANSFER FROM INJECTION TO THE RECIRCULATION MODE

a. Automatic Actuation Logic Coincident with Safety Injection Signal b.. Refueling Water Storage Tank Level-Extreme Low 2

1 2

3 N.A.

1, 2,

3, 4

18 16 4

2

> 31' 8" and

< 31' 10" 1, 2, 3, 4 Time constants utilized in the lead-lag controllers for Steam Line Pressure-Low are Tl Ž 50 seconds and T2 ' 5 seconds.

CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

BEAVER VALLEY -

UNIT 2 3/4 3 -16 Amendment No.153

ENGI FUNCTIONAL UNIT

2.

CONTAINMENT SPRAY

a. Manual Initiation
b. Automatic Actuation Logic and Actuation Relays
c. Containment Pressure--

High-High

3.

CONTAINMENT ISOLATION

a. Phase "AA" Isolation
1) Manual Initiation
2) Automatic Actuation Logic and Actuation Relays
3) Safety Injection
b. Phase "B" Isolation
1) Manual Initiation
2) Automatic Actuation Logic and Actuation Relays
3) Containment Pressure--High-High TABLE 3.3-3 (Continued)

NEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS ALLOWABLE OF CHANNELS TO TRIP OPERABLE VALUE 2-sets 1 set 2 sets N.A.

(2 switches/

set) 2 1

2 N.A.

4 2

3

< 11.4 psig APPLICABLE MODES 1, 2, 3, 4 1, 2, 3, 4 1,

2, 3

ACTION 18 13 16 I

2 See Item 1. above requirements.

2 sets 1

(2 switches/

set) 2 4

1 2

1 2

for all Safety N.A.

1, 2,

3, 4

N.A.

1, 2, 3, 4 Injection initiating functions and 18 13 set 1

2 2 sets 2

3 N.A.

N.A.

< 11.4 psig 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 18 13 16 I

BEAVER VALLEY -

UNIT 2 3/4 3 -17 Amendment No. 1 53

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE ALLOWABLE VALUE APPLICABLE MODES ACTION

4.

STEAM LINE ISOLATION

a. Manual Initiation
1.

Individual 1/steam line 1/steam h/oper-line ating steam line N.A.

1, 2, 3 41

2.

System

b. Automatic Actuation Logic and Actuation Relays 2 sets (2 switches/

set) 2 1 set 2 sets N.A.

1, 2, 3 1, 2, 3 18 13 1

2 N.A.

c. Containment Pressure Intermediate -High-High 3

2 2

< 7.3 psig 1, 2, 3 14 I

d. Steamline Pressure-Low
e. Steamline Pressure Rate--High Negative 3/loop 3/loop 2/loop 2/oper-any loop ating loop 2/loop 2/operat-any loop ing loop 2 494 psig*

5 103.6 psi with a time constant 2 50 seconds 3

3(2) 14 14 Time constants utilized in the lead-lag controllers for Steam Line Pressure-Low are Ti 2 50 seconds and T2< 5 seconds.

CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

BEAVER VALLEY -

UNIT 2 3/4 3-18 Amendment No.153

TABLE 4.3-2 ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL UNIT

1.

SAFETY INJECTION AND FEEDWATER ISOLATION

a.

Manual Initiation

b.

Automatic Actuation Logic and Actuation Relays

c.

Containment Pressure-High

d.

Pressurizer Pressure--Low

e.

Steam Line Pressure--Low 1.1 SAFETY INJECTION-TRANISFER FROM IN ECTION TO THE RECIRCULATION MODE

a.

Automatic Actuation Logic Coincident with Safety Injection Signal

b.

Refueling Water Storage Tank Level-Extreme Low N.A.

N.A.

N.A.

N.A.

S S

S R (2) (3 R

R CHANNEL FUNCTIONAL TEST R

Mll)

Q( 2) (3)

Q Q

M( 1 )

Q(2) (3)

MODES IN WHICH SURVEILLANCE REQUIRED 1,

2, 3,

4 1,

2, 3,

4 1, 2, 3

1, 2,

3 1,

2, 3

1, 2,

3, 4

1, 2, 3, 4 I

N.A.

N.A.

S R(2) (3)

I BEAVER VALLEY - UNIT 2 3/4 3 -33 Amendment NO.153

TABLE 4.3-2 (Continued)

ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED

2.

CONTAINMENT SPRAY

a.

Manual Initiation

b.

Automatic Actuation Logic, and Actuation Relays

c.

Containment Pressure-High-High N.A.

N.A.

S N.A.

N.A.

R(2) (3)

R MU1)

Q (2) 13) 1, 2, 3, 4 1, 2, 3, 4 1,

2, 3

I I

3.

CONTAINMENT

a.

Phase 1.

2.

ISOLATION "A" Isolation Manual Initiation Automatic Actuation Actuation Relays N.A.

N.A.

N.A.

N.A.

R MMt 1,

2, 3,

4 1, 2, 3, 4 Logic and

3.

Safety Injection

b.

Phase "s" Isolation

1.

Manual Initiation

2.

Automatic Actuation Actuation Relays See Functional Unit 1 above Surveillance Requirements.

for all Safety Injection N.A.

N.A.

N.A.

N.A.

R M1 1, 2, 3, 4 1, 2, 3, 4 Logic and

3.

Containment Pressure--High-High S

R 2 ) (3)

Q(2) 13) 1, 2, 3, 4 I

BEAVER VALLEY -

UNIT 2 3/4 3 -34 Amendment No.153

TABLE 4.3-2 (Continued)

ENGINEERING SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL UNIT

4.

STEAM LINE ISOLATION

a.

Manual Initiation

1.

Individual

2.

System

b.

Automatic Actuation Logic and Actuation Relays

c.

Containment Pressure--Intermediate-High-High

d.

Steamline Pressure--Low

e.

Steamline Pressure Rate-High Negative

5.

TURBINE TRIP AND FEEDWATER ISOLATION

a.

Automatic Actuation Logic and Actuation Relays

b.

Steam Generator Water Level--High-High, P-14

c.

Safety Injection N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL FUNCTIONAL TEST R

R Q.,} (3)

Q Q

S a (2) (3)

MODES IN WHICH SURVEILLANCE REQUIRED 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 Injection I

S S

R R

N.A.

N.A.

S Q 2) (3)

See Functional Unit 1 above for all Safety Surveillance Requirements.

BEAVER VALLEY -

UNIT 2 3/4 3 -35 Amendment No.153

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

a.

By performing the following air lock leakage rate testing at the frequency specified in the Containment Leakage Rate Testing Program:

1.

Verify no detectable seal leakage when the gap between the door seals is pressurized for at least 2 minutes to:

a)

Personnel air lock 2 Pa (44.9 psig).

b)

Emergency air lock 2 10.0 psig.

or, quantify (7) the air lock door seal leakage to ensure that the leakage rate is < 0.0005 La when tested at > Pa (44.9 psig) for the personnel air lock and < 0.0005 La when tested at 2 10.0 psig for the emergency air lock.

2.

Conduct the overall air lock leakage tests, (8) at 2 Pa (44.9 psig), and verify the overall air lock leakage rate is < 0.05 La, when tested at > Pa (44.9 psig):

a)

At the frequency specified in the Containment Leakage Rate Testing Program, and b)

Following maintenance performed on the outer personnel air lock door which may result in a decrease in closure force on any part of the door sealing surface.

b.

At least once per 18 months during.shutdown by verifying that only one door in each air lock can be opened at a time.

(7) An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

(8) Results shall be evaluated against the acceptance criteria applicable to LCO 3.6.1.2.

BEAVER VALLEY - UNIT 2 3/4 6-5a Amendment No. 153

CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Containment internal air pressure shall be 2 12.8 psia and S 14.2 psia.

I APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment internal air pressure not within the above limits, restore the internal pressure to within the limits within I

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.4 The containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I BEAVER VALLEY -

UNIT 2 3/4 6-6 (next page is 3/4 6-8)

Amendment No.153 I

CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5

< 105 0 F.

Containment average air temperature shall be 2 700 F and APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment average air temperature not within the above limits restore the average air temperature to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS I

4.6.1.5 The containment average air temperature shall be determined to be within limits at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

BEAVER VALLEY - UNIT 2 3/4 6-8 Amendment No.153

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

b.

With one or more penetration flow paths with two containment isolation valves inoperable, isolate the affected penetration flow path within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With one or more penetration flow paths with one containment isolation valve inoperable, isolate the affected penetration flow path within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange; and verify the affected penetration flow path is isolated at least once per 31 days.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.3.1 Each containment isolation valve shall be demonstrated OPERABLE*:

a.

By verifying each purge supply and exhaust valve is deactivated in the closed position at least once per 31 days for valves outside containment and prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for valves inside containment.

b.

By verifying, at the frequency specified in the Inservice Testing Program, the isolation time of each automatic power operated containment isolation valve that is not locked, sealed, or otherwise secured in position, and required to be closed during accident conditions, is within limits.

c.

By verifying, at least once per 18 months, each automatic power operated containment isolation valve that is not

locked, sealed, or otherwise secured in position, and required to be closed during accident conditions, actuates to the isolation position on an actual or simulated actuation signal.
  • Locked or sealed closed valves, except for the containment purge supply and exhaust valves, may be opened on an intermittent basis under administrative control.

BEAVER VALLEY - UNIT 2 3/4 6-16 Amendment No.153

ADMINISTRATIVE CONTROLS CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued)

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 44.9 psig.

The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.

Leakage Rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is < 1.0 La for the overall Type A leakage test and < 0.60 La for the Type B and Type C tests on a minimum pathway leakage rate (MNPLR) basis.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria WiFe <

0.60 La on a maximum pathway leakage rate (MXPLR) (

basis for Type B and Type C tests and < 0.75 La for Type A tests.

b.

Air lock testing acceptance criteria and required action are as stated in Specification 3.6.1.3 titled "Containment Air Locks."

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

6.18 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1.

a change in the TS incorporated in the license; or (2) For penetrations which are isolated by use of a closed valve(s),

blind flange(s), or de-activated automatic valve(s), the MXPLR of the isolated penetration is assumed to be the measured leakage through the isolation device(s).

BEAVER VALLEY -

UNIT 2 6-26 Amendment No. 153