ML20011E686

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Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for ESFAS Instrumentation, Radiation Monitoring Instrumentation & Control Room Emergency Ventilation Sys
ML20011E686
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 02/07/1990
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20011E683 List:
References
NUDOCS 9002220190
Download: ML20011E686 (8)


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Atttchment III to iM 90-002'6 P;ge.11cf 8.

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PROPOSED TECIDEICAL SPECIFICATION CBANGES n

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. Attachment III to WM 90-0026 Page 2 of 8 INSTRUMElil A71014 3/4.3.2 ENG!NEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g MITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABillTY:

As shown in Table 3.3-3.

ACTION:

With an ESFAS Instrumentation or Interlock Trip Setpoint less conserva-a.

tive than the value shown in the Trip Setpoint column but more conser-vative than the value shown in the Allowable Value column of Table 3.3-4. adjust the Setpoint. consistent with the Trip-Setpoint value.

b.

With an ESFAS Instrumentation or Interlock Trip Setpoint less conser-vative than the value shown in the Allowable Values column of Table 3.3-4, either:

1.

Mjust the Setpoint consistent with the Trip Setpoint value of j

Table 3.3-4 and d6.termine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 I

was satisfied for the affected channel, or

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2.

Declare the channel inoperable and apply the applicable ACTION stettment requirements of Table 3.3-3 until the channel is a

restored to OPERABLE status with its Setpoint adjusted consistent 1

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with the Trip Setpoint value.

Equation 2.2-1 2 + R + S < TA 3

Where:

2

= The value from Column 2 of Table 3.3-4 for the af fected channel,

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R = The "as measured" value (in percent span) of rack error for the affected channel, S

= Either the "as measured" value (in percent span) of the sensor error, or the value from Column 5 (Sensor Error) of i

Table 3.3-4 for the affected channel, and 1

TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel, 1

With an ESFAS instrumentation channel or interlock inoperable, take c.

I the ACTION shown in Table 3.3-3.

SURVEILLANCE RE0UIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.

4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of eacn ESFAS function snall be demonstrated to be within the limit at least once per 18 months.

Each

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test shall include at least one train such that both trains are tested at least once per 36 months and on2 channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

WOLF CREEK - UNIT 1 3/4 3-13

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TNDLE 3.3-3 (Continued) g ENGINEERED SAFETY FEATURES ACTUATI0ft SYSTEM IriSTRUMEtiTATI0ft

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..g-E MINIMUM "i-TOTAL 110.

CilANNELS

. CllANNELS

' APPLICABLE l R@

I.,S FUNCTI0ftAL UNIT

' 0F CilANflELS TO TRIP OPERABLE-H0 DES A;TIOil

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Control Room Isolation

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Manual Initiation 2

1 2

All 26 z.

b.

Automati: Actuation

'e Logic and Actuation ~

j Relays (SSPS)

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2 1, 2, 3,'4 26 g

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Automatic Actuation 2

1 2

.All 26 Legic and Actuation Relays (BOP ESFAS) d.

Phase "A" Isolation

. See Item 3.a. above for all Phase "A

Isolation initiating

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functions and requirements.

10.

Solid-State Load Sequencer 2-1/ train 1/ train 2-1/ train 1, 2, 3, 4 25 11.

Engineered Safety Features Actuation System' Interlocks a.

Pressurizer Pressure, 3_

2 2

1,2,3 20 P-11 b.

Reacter Trip, P-4 4-2/ Train 2/ Train 2/Trairi 1, 2, 3 22 e

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1 Attachment !II to WM 9000026 Page 4 of 8 1 AM E 3. 3-3 (Continued)

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ACT10N STATEMEN15 (Continued) b.

The Minimum Channels OPERABLE requirement is met: however, the inoperable channel may be bypassed for us to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With less than the Minimum Channels OPERABLE. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciater window (s) that the interlock is in its required state for thE existing plant condition, or apply Specification 3.0.3.

ACTION 21 " With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANUBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for us to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 provided the o

other channel is OPERABLE.

ACTION 22 - With the numver of OPERABLE channels one less than the Tota's Numoer of Cnannels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at lea.t HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the associated valve inoperable and take the action required by Specification 3.7.1.5.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected auxiliary feedwater pump inoperable and take the ACTION required by Specification 3.7.1.2.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected diesel generator and off-site power source inoperable and take the ACTION required by Specification 3.8.1.1 ACTION 26 - With the number of OPERABLE channel oneless than the Minimum Channels OPERABLE requirement, re ore the inoperable channel to OPERABLE status within fS h = s or initiate and maintain operation of the Control Room Emergency Ventilation System.=

ACTION 27 With the riumber of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is O_PERABLE.

_%m During operation in MODE 5 and 6, the provisions of Specification 3.0.4 are not applicable.

WOLF CREEK - UNIT 1 3/4 3-21

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Attachm:nt 111 to WM 90-0026 u

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Page 5 of C L

IN51RUMENIA110fJ

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3/4.3.3 MONilORING INSTRUMENIA110N RADIAllPN MONITORING FOR PLANT O_PERA110NS LIMITING COND1110N FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations sho n in Table 3.3-6 shall be OPERARLE with their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable, b.

Wjth one or more radiation mortitoring channels for plant operations inoperable, take the AC110N shown in Table 3.3-6, C

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c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, SURVEILLANCE hEQUIREMENTS 4.3.3.1 Each radiation honitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CAllBRATION and ANALOG CHANNEL OPERATIONAL TEST for the MODE 5 and at the fre-quencies shown in Table 4.3-3.

h WOLF CREEK - UN11 1 3/4 3-39

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TABLE 3.3-6

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RADIATION MONITORING INSTRUMENIATION FOR PLANT OPERATIONS

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MINIMUM

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3,:s CHANNELS CHANNEL 5 APPLICABLE ALARM /IRIP A

FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES

$ETPOIf/T ACTI0rt oo

.x 5

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1.

Containment z

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a.

Containment Atmosphere-ac Gaseous Radioactivity-l3 High (GT-RE-31 & 32) 1 1

A11 26 E,

b.

Gaseous Radioactivity-8-

RCS Leakage Detection (GT-RE-31 & 32)

N.A.

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

29 c.

Particulate Radioactivity-M RCS Leakage Detection

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(GT-RE-31 & 32)

N.A.

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

29 2.

Fuel' Building a.

Fuel Building Exhaust-Gaseous Radioactivity-High (GG-RE-27 & 28)

I' 2

30 b.

Criticality-High Radiation Level j

1) Spent Fuel Pool 1

1

< 15 mR/h (SD-RE-37 or 38) 28

2) New Fuel Pool 1

1

< 15 mR/h 23 (SD-RE-35 or 36)

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Control Room E

Air Intake-Gaseous f.

Radioactivity-High (GK-RE-04 & 05) 1 2

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  • Page 7 of 8 l ABli 3. 'l-f3 (Continued)

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TABtt N01A110N5

  • With fuel in the respective fuel storage pool, j
    • With irradiated fuel in the f uel storage areas or fuel building.
  1. Trip Setpoint concentration value (pCi/cm3) is to be established such that the actual submersion dose rate would not exceed 2 mR/h in the control rnom.
    1. 1 rip Setpoint concentration value (pCi/cm3) is to be established such that the. actual submersion dose rate would not exceed 4 mR/h in the fuel building.
      1. Trip Setpoint concentration value (pCi/cm3) is to be established such that the actual submersion dose rate would not exceed 9 mR/h in the containment building.

The Setpoint value may be increased up to the equivalent limits of Specification 3.11.2.1 in accordance with the methodology and parameters '

in the ODCM during containment purge or vent provided the Setpoint value does not exceed twice the maximum concentration activity in the containment determined by the sample analysis performed prior to each release in accordance with Table 4.11-2.

ACTION STATEMENTS ACTION 26 - W4th less than the Minimum Channels OPERABLE requirement, opera-tion may continue provided the containment purge valves are main-tained closed.

l ACTION 27 - With the number of OPERABLE channels one less than the Minimumi Channels OPERABLE requirement, isolate the Control Room Emergency l

Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode within p ?2 h =, or with no OPERABLE channels within I hour.

A 28 - With less than the Minimum Channels OPERABLE requirement, opera -

tion may continue for up to 30 days provided an appropriate pnrtable continuous monitor with the same Alarm Setpoint is provided in the fuel area.

Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement.in the fuel building.

ACTION 29 - Must satisfy the ACTION requirements for Specification 3.4.6.1.

ACTION 30 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, isolate the fuel Building Ventila-tion System and initiate operation of the Emergency Exhaust System l

to maintain the fuel building at a negative pressure within

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72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OPERABLE channels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

WOLF CREEK - llNii 1 3/4 3-41 Amendment No. 10

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Page 8'of 8 L,,

t PLANT SYSTEMS s

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATICN SYSTEM i

LIMITING CONDITION 4 OPERATION r

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3.7.6 Two independent Control Room Emergency Ventilation Systems shall oe OPERABLE.

I APPLICABILITY: All MODES.

ACTION:

MODES 1, 2, 3 and 4:

With.one Control Room Emergency Ventilation System inoperacle, restore tne inuperable system to OPERABLE status within 7 days or be in at least F07 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 SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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MODES 5 and 6:

~With one Control Room E'mergr.ncy Ventilation System inc;er3314.

+

a.

restore the it; operable system to OPERABLE status within 7 cays or initiate and maintain operation of the remaining OPERAELE Control Room Emergency Ventilation System in the recirculation mece. +

b.=

' With both Control Room Emergency Ventilation Systems iroperable, or with the OPERABLE Control Room Emergency Ventilation-System, required to be in the recirculation mode by ACTION a,, not capanie of being powered by an.0PERABLE emergency power source, suspend-all ocerations-involving CORE ALTERATIONS or positive reactivity changes.

.The provisions of Specification SURVEILLANCE REOUIREMENTS 3.0l4 are not applicable,

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" 4, 7. 6 Each Control Room Emergency Ventilation System shall be cemonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control rcen air temperature is less than or equal to 84*F; b.

At least once per 31 days on a STAGGERED TEST SASIS ty 'ni.iat:ag, from the control room, flow througn the HEPA filters aN craccoa:

adsorbers of-both the Fi1Leation and Pressuri:stian i;.iters and verifying that the Pressuri:ation Systcm oarates fc n :e u t

.10 continpous hours with the heaters operating; 3/4 7-14 2...