ML17291A222

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Proposed TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances
ML17291A222
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 07/08/1994
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A221 List:
References
NUDOCS 9407190364
Download: ML17291A222 (5)


Text

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CONTROLLED COPY ~

TABLE 1.2 OPERATIONAL CONDITIONS CONDITION 1.

POWER OPERATION 2.

STARTUP 3.

HOT SHUTDOWN 4.

COLD SHUTDOWN 5.

REFUELING" MODE SWITCH POSITION Run Startup/Hot Standby Shutdown¹ **

Shutdown¹ ¹¹ ***

Shutdown or Refuel** ¹ AVERAGE REACTOR

,COOLANT TEMPERATURE Any temperature Any temperature 200 F**%'*

200 F****

s 140 F

¹The reactor mode switch may be placed in the Run or Startup/Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the uni t technical staff.

¹¹The reactor mode switch may be placed in the Refuel position while a sing'le control rod drive is being removed from the reactor pressure vessel per Specification 3.9. 10.1.

  • Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
    • See Special Test Exceptions 3.10. I and 3. 10.3.

" "The reactor mode switch may be laced in the Refuel position while a single control rod is being provided that the one-rod-out interlock is OPERABLE.

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        • See Special Test Exception 3. 10.7.

WASHINGTON NUCLEAR <!MTT ~

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1-10 9407190364 940708 PDR ADOCK 05000597 PDR Amendment No.~

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CONTROLLED COPY REACTIVITY CONTROL SYSTEMS CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position to notch position 6, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed 7 seconds.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a.

With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

1.

Declare the control rod(s) with the slow insertion time inoperable, and 2.

Perform the Surveillance Requirements of Specification 4. 1.3.2c.

at least once per 60 days when operation is continued with three or more control rods with maximum scram insertion times in excess of 7 seconds.

0th rwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

The provisions of Specification

3. 0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.1.3.2 The maximrum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:

For all control rods prior to THERMAL POWER exceeding 40~. of RATED THERMAL POWER following CORE ALTERATIONS" or after a reactor shutdown'hat is greater than 120 days.

b.

C.

for specifically afrected individual control rods following mainten on or modification to the control rod or control rod drive syste

+ $

which could affect the scram insertion time of those specific control rods, and For at least 10K of the control rods, on a rotating basis, at least once per 120 days of POWER OPERATION.

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A CONTROLLED COPY 3/4. 9 REFUELING OPERATIONS 3/4.9.1 REACTOR MOOE.SWITCH LIMITING CONDITION FOR OPERATION 3.9. 1 The reactor mode switch shall be OPERABLE and locked in the Shutdown or Refuel position.

When the reactor mode switch is locked in the Refuel position:

a.

A control rod shall not be withdrawn unless the Refuel position one-rod-out interlock is OPERABLE.

b.

CORE ALTERATIONS shall not be performed using equipment associated with a Refuel position interlock unless at least the following associated Refuel position interlocks are OPERABLE for such equipment.

.1.

2.

3.

4.

APPLICABILITY:

ACTION:

All rods in.

Refuel platform position.

Refuel platform hoists fuel-loaded.

Service platform hoist fuel-loaded.

OPERATIONAL CONPITION 5~ y<

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b.

C.

With the reactor mode switch not locked in the Shutdown or Refuel position as specified, suspend CORE ALTERATIONS and lock the reactor mode switch in the Shutdown or Refuel position.

With,.the one-rod-out interlock inoperable, lock the reactor mode switch in the Shutdown position.

With any of the above required Refuel position equipment interlocks inoperable, suspend CORE ALTERATIONS with equipment associated with the inoperable Refuel position equipment interlock.

" See Special Test Exceptions 3.10.1 and 3.10.3.

4 The reactor shall be maintained in OPERATIONAL CONOITION 5 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

WASHINGTON NUCLEAR - UNIT 2 3/4 9-1

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