Text

Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315
	ML18026A471
Person / Time
Site:	Susquehanna
Issue date:	02/11/1997
From:	; PENNSYLVANIA POWER & LIGHT CO.
To:	;
Shared Package
ML18026A472	List: ML18026A471; ML18030A576; PLA-4565, Forwards Request for Amend to ITS Approving Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315;
References
	NUDOCS 9702190318
	Download: ML18026A471 (25)
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i SPECIAL TEST EXCE ION SPECIAL TEST EXCEPTiON 3/4.10.7 SINGLE CONTROL ROD WITHDRAWAL-HOT SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.10.7 The reactor mode switch position specified in Table 1.2 for OPERATIONAL CONDITION 3 may be changed to include the Refuel position to allow withdrawal of a single control rod, provided the following requirements are met:

a.

The refuel position one-rod-out interlock shall be OPERABLE.

b.

The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

c.

Allother control rods are fullyinserted; and d.

1.

a.

LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 requirements for Functions 1.a, 1.b, 8.a, S.b, 11, and 12 of Table 3.3.1-1, and b.

Each withdrawn control rod shall be OPERABLE.

OR All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "Shutdown Margin", OPERATIONAL CONDITION 3 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY:

OPERATIONAL CONDITION 3 with the reactor mode switch in the Refuel position.

9702190318 970211 t

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PDR ADQCK 05000387I PDR+

SUSQUEHANNA-.UNIT 1 3/4.10-'7 Amendment No.

4

, ~

SPECIAL TEST EXCE ION ACTION:

a.

With one or more of Functions 1.a, 1.b, 8.a, 8.b, 11 and 12 of Table 3.3.1-1 OPERATIONAL CONDITION 5 requirements not being met:

1.

immediately enter the ACTION Statement for that function **,

OR 2.

immediately initiate action to fully insert all insertable control rods and within one hour place the reactor mode switch in the Shutdown position.

b. With the refuel position one-rod-out interlock inoperable,

1. immediately suspend control rod withdrawal, 2.

immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, and 3.

place the reactor mode switch in the Shutdown position.

c. With one or more required control rod position indication channels inoperable, 1.

a. immediately suspend in-vessel fuel movement

b. immediately suspend control rod withdrawal,

c. immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, OR 2.

a. initiate action to fullyinsert the control rod associated with the inoperable position indicator, and

b. initiate action to disarm the control rod drive associated with the fully inserted control rod, OR 3.

a. immediately initiate action to fullyinsert all insertable control rods in core cells containing one or more fuel assemblies, and

b. within one hour place the reactor mode switch in the Shutdown position.

SUSQUEHANNA - UNIT 1 3/4.10-8 Amendment No.

'PECIAL TEST EXCE

[ON

'CTION (Continued)

d. With one or more withdrawn control rods inoperable, immediately initiate action to fully insert inoperable withdrawn control rods and within one hour place the reactor mode switch in the Shutdown position.

e. With all other control rods in a five by five array centered on the control rod being withdrawn not disarmed, immediately initiate action to fully insert the withdrawn control rod and within one hour place the reactor mode switch in the Shutdown position.

f.

With all other control rods not fully inserted, immediately initiate action to fully insert all control rods and within one hour place the reactor mode switch in the Shutdown position.

SURVEILLANCEREQUIREMENTS 4.10.7.1 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify reactor mode switch locked in Refuel position.

4.10.7.2 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a. verify all control rods, other than the control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.+

b. verify all control rods, other than the control rod being withdrawn, are fully inserted.

4.10.7.3 Once per 7 days, a.

perform a CHANNELFUNCTIONALTEST on the Refuel position one-rod-out interlock.*

b. insert each withdrawn control rod at least one notch.¹ c.

verify each withdrawn control rod scram accumulator pressure is a 940 pslg.

4.10.7.4 Each time the control rod is withdrawn from the "full-in" position, verify the required channel has no "full-in" indication on each control rod that is not "full-in".

4.10.7.5 Perform LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 Surveillance Requirements for Functions 1.a, 1.b, 8.a, 8.b, 11, and 12 of Table 4.3.1.1-1 SUSQUEHANNA - UNIT 1 3/4.10-9 Amendment No.

( ~

SPECIAL TEST EXCE ION SURVEILLANCERE UIREMENTS (Continued)

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Not required to be performed until 7 days after the control rod is withdrawn.

+

Not required to be met if LCO requirements are being satisfied by 3.10.7.d.1 requirements.

~~ Except that the one hour to insert all insertable control rods allowed by ACTIONs 3 and 9 of Table 3.3.1-1 is not applicable.

The insertable control rods are to be inserted immediately.

SUSQUEHANNA - UNIT 1 3/4.10-10 Amendment No.

SPECIAL TEST EXCEPTION 3/4.10.8 SINGLE CONTROL ROD WITHDRAWAL-COLD SHUTDOWN LIMITINGCONDITION FOR OPERATION 3;10.8 The reactor mode switch position specified in Table 1.2 for OPERATIONAL CONDITION 4 may be changed to include the Refuel position to allow withdrawal of a single control rod provided the following requirements are met:

a.

Allother control rods are fully inserted; b.

The refuel position one-rod-out interlock shall be OPERABLE, and c.

The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

d.

1.

a.

LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 requirements for Functions 1.a, 1.b, S.a, 8.b, 11, and 12 of Table 3.3.1-1, and b.

Each withdrawn control rod shall be OPERABLE.

OR 2.

All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "Shutdown Margin", OPERATIONAL CONDITION 4 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY:

OPERATIONAL CONDITION 4 with the reactor mode switch in the Refuel position.

SUSQUEHANNA - UNIT 1 3/4.10-11 Amendment No.

I SPECIAL TEST EXCE ION ACTION:

a.

Ifthe affected control rod is insertable:

1. With one or more of Functions 1.a, 1:b, 8.a, 8.b, 11 and 12 of Table 3.3.1-1 OPERATIONAL CONDITION 5 requirements not being met:

a.

immediately enter the ACTION Statement for that function **,

OR b.

immediately initiate action to fully insert all insertable control rods and within one hour place the reactor mode switch in the Shutdown position.

2. With the refuel position one-rod-out interlock inoperable, a.

immediately suspend control rod withdrawal,

b. immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, and c.

place the reactor mode switch in the Shutdown position.

3. With one or more required control rod position indication channels inoperable, a.

i. immediately suspend in-vessel fuel movement ii. immediately suspend control rod withdrawal, iii.immediately initiate action to fullyinsert all insertable control rods in core cells containing one or more fuel assemblies, OR b.

i. initiate action to fullyinsert the control rod associated with the inoperable position indicator,and ii. initiate action to disarm the control rod drive associated with the fully inserted control rod, SUSQUEKQTNA - UNIT 1 3/4.10-12 Amendment No.

J C

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t

1

'PECIALTEST EXCE ON AUCTION C i

d c.

i. immediately initiate action to fullyinsert all insertable control rods in core cells containing one or more fuel assemblies, and ii. within one hour place the reactor mode switch in the Shutdown position.

4. With one or more withdrawn control rods inoperable, immediately initiate action to fully insert inoperable withdrawn control rods and within one hour place the reactor mode switch in the Shutdown position.

5. With all other control rods in a five by five array centered on the control rod being withdrawn not disarmed immediately initiate action to fully insert the withdrawn control rod and within one hour place the reactor mode switch in the Shutdown position.

6. With all other control rods not fully inserted, immediately initiate action to fully insert all control rods and within one hour place the reactor mode switch in the Shutdown position.

b.

Ifthe affected control rod is not insertable:

1.

Immediately suspend withdrawal of the control rod, AND 2.

a.

immediately initiate action to fullyinsert all control rods, OR b.

immediately initiate action to satisfy the requirements of this LCO.

SURVEILLANCEREQUIREMENTS 4.10.8.1 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify reactor mode switch locked in Refuel position.

SUSQUEHANNA-UNIT 1 3/4.10-13 Amendment No.

SPECIAL TEST EXCE ION SURVEILLANCERE UIREMENTS Continued 4.10.8.2 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a.

verify all control rods, other than the control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.+

b. verify all control rods, other than the control rod being withdrawn, are fully inserted.

c.

verify a control rod withdrawal block is inserted.++

4.10.8.3 Once per 7 days, a.

perform a CHANNELFUNCTIONALTEST on the Refuel position one-rod-out interlock.*

b.

insert each withdrawn control rod at least one notch.4 c.

verify each withdrawn control rod scram accumulator pressure is a 940 pslg.

4.10.8.4 Each time the control rod is withdrawn from the "full-in" position, verify the required channel has no "full-in" indication on each control rod that is not "full-in".

4.10.8.5 Perform LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 Surveillance Requirements for Functions 1.a, 1.b, 8.a, 8.b, 11, and 12 of Table 4.3.1.1-1 Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

¹ Not required to be performed until 7 days after the control rod is withdrawn.

+

Not required to be met if LCO requirements are being satisfied by 3.10.8.c.1 requirements.

++ Not required to be met if LCO requirements are being satisfied by 3.10.8.b.1 requirements.

~ Except that the one hour to insert all insertable control rods allowed by ACTIONs 3

'nd 9 of Table 3.3.1-1 is not applicable.

The insertable control rods are to be inserted immediately.

SUSQUEHANNA-UNIT 1 3/4.10-14 Amendment No.

'FEB GS '97 i8:ZiAN PP SRA4 P.XS SASES The requirement for PRIMARY CONTAINMENTINTEGRITY is not applicable during tho period when upon vassal tests ara being performed during tha low power PHYSICS TESTS.

In order to perform tha tests required in the technlcIII spaclftcsttons it is necessary to bypass tha saquanco restraints on control rod movamant, The additional surveillance requirements ensure that tho specifications on heat generation rates and shutdown margin requirements are not exceeded during the period when these teste are being performed and that Individual rod worths do not exceed tho values assumed in the safety analysis.

Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions In order to ensure that criticality does not occur.

These additional restrictions are specified in this I.CO.

This special test exception pormits reactor critlcallty under no ftow conditions and is required to perform certain atartup and PHYSICS TESTS while st low THERMALPOWER levels.

This special test exceptton permits training stsrtupa to be performed with tho reactor vessel daprassurtsed at Iow THERMAL POWER and temperature white controlling RCS temperature with one RHR subsystem aligned ln the shutdown cooltng mode in order to minimize contaminated water discharge to the radioactive waste disposal system, This special tost excoptlon eltows reactor vessel inservtca task and hydrostatic testing to be performed In OpERATIONAL CONDITION 4 with reactor coolant temperatures 5212eF.

The additionatty imposed OPERATtONAI.

CONDITION 3

requirement for SECONDARY CONTAINMENT INTEGRITY provides conservatism ln the rosponso of tho unit to an operational event.

This allows ftexibillty since temperatures approach ZOO'P during the testing and csn ddft higher because of decay and'mochanlcsl heat.

Tho reactor coolant temparatura is controltad to insure that it docs not exceed 21 2eF, Since the reactor coolant temperature Is at or below 212eP, minimum water level ln the suppression chamber tn OPERATIONAI. CONDITION 4 is sufficient to provide pressure suppression and adequate NPSH for ECCS pump operation.

This condition Is bounded by the analysis providad in support of 60-100-103 for prassuro suppression.

g yggavd A'USQUEHANNA

~ UNIT 1 B 3/4 10-1 82, Amendment No.

$ 42

INSERT A 3/4.10.7 SINGLE CONTROL ROD WITHDRAWAL-HOT SHUTDOWN The purpose of this OPERATIONAL CONDITION 3 Special Test Exception is to permit the withdrawal of a single control rod for testing while in Hot Shutdown, by imposing certain restrictions.

In OPERATIONALCONDITION 3, the reactor mode switch is in the Shutdown position and all control rods are inserted and blocked from withdrawal. Many systems and functions are not required in these conditions, due to the other installed interlocks that are actuated when the reactor mode switch is in the Shutdown position.

However, circumstances may arise while in OPERATIONAL CONDITION 3 that present the need to withdraw a single control rod for various tests (e.g., friction tests, scram timing, and coupling integrity checks).

These single control rod withdrawals are normally accomplished by selecting the Refuel position for the reactor mode switch.

The withdrawn control rod is considered to be OPERABLE if the scram accumulator pressure is t 940 psig and the control rod is capable of being automatically inserted upon receipt of a scram signal.

3/4.10.8 SINGLE CONTROL ROD WITHDRAWAL-COLD SHUTDOWN The purpose of this OPERATIONAL CONDITION 4 Special Test Exception is to permit the withdrawal of a single control rod for testing while in Cold Shutdown, by imposing certain restrictions.

In OPERATIONALCONDITION 4, the reactor mode switch is in the Shutdown position and all control rods are inserted and blocked from withdrawal. Many systems and functions are not required in these conditions, due to the other installed interlocks that are actuated when the reactor mode switch is in the Shutdown position.

However, circumstances may arise while in OPERATIONAL CONDITION 4 that present the need to withdraw a single control rod for various tests (e.g., friction tests, scram timing, and coupling integrity checks).

These single control rod withdrawals are normally accomplished by selecting the Refuel position for the reactor mode switch.

The withdrawn control rod is considered to be OPERABLE if the scram accumulator pressure is z 940 psig and the control rod is capable of being automatically inserted upon receipt of a scram signal.

Technical Specification 3/4.9.10.1 governs single control rod removal in OPERATIONAL CONDITION 4.

.'. FEB'85 '97 18:22AN PP8 A4 I

I

'\\

P. 17 TABLE 1.R OPERATIONALCONDITIONS, CONDITION 1.

Power Operation 2.

Stertup 3.

Hot Shutdown 4.

Cold Shutdown 5.

Refueling'ODE SWITCH POSITION Run Startup/Hot Standby

~ ~ ~

Shutdown Shutdown'

~

~ 0 Shutdown 'r

~ 0 Refuel AVERAGE REACTOR COOLANTTEMPERATURE Any temperature Any temperature

> 2004F 2004F

'S 140~F Tho reactor mocle switch rn0y bo placed in the Run or Startup/Hot Standby position to test the switch Interlock functions provided that tha control rods ere verified to remain fully Inserted by e second licensed operator or other technically qualNed mdmber of the unit technical staff.

¹¹ The reactor mode switch may be placed In the Refuel position while o single control rod drive ls being removed from tho reactor pressure vessel per Specificstloh 3.9..10.1.

Fuel in the reactor vessel with the vessel head closure bolts less than fullytensioned or with the head removed, See Special Test Exceptions 3,10.1 and 3.10.3.

The reactor mode switch may be placed in the Refuel positIon while a single controt rod is being recouplad provided that the one-rodwut interlock is OPERABLE, /.'/i;; >~V.

S,~c'.a.

~ </ ~eii" Zr'c.c~>+~ '~4 2-i<c 7 <~

Z. r0 8'aa Special Test Exception 3,10.6.'USQUEHANNA

- UNIT 2

>-I0 Amen ment Na. 112

e SPECIAL TEST EXCE ION SPECIAL TEST EXCEPTION 3/4.10.7 SINGLE CONTROL ROD WITHDRAWAL-HOT SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.10.7 The reactor mode switch position specified in Table 1.2 for OPERATIONAL CONDITION 3 may be changed to include the Refuel position to allow withdrawal of a single control rod, provided the following requirements are met:

a.

The refuel position one-rod-out interlock shall be OPERABLE.

b.

The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

c.

All other control rods are fully inserted; and d.

1.

a.

LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 requirements for Functions 1.a, 1.b, 8.a, 8.b, 11, and 12 of Table 3.3.1-1, and b.

Each withdrawn control rod shall be OPERABLE.

OR All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "Shutdown Margin", OPERATIONAL CONDITION 3 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY:

OPERATIONAL CONDITION 3 with the reactor mode switch in the Refuel position.

SUSQUEHANNA - UNIT2 3/4.10-7 Amendment No.

SPECIAL TEST EXCE ION ACTION:

a.

With one or more of Functions 1.a, 1.b, 8.a, 8.b, 11 and 12 of Table 3.3.1-1 OPERATIONALCONDITION 5 requirements not being met:

1.

immediately enter the ACTION Statement for that function *~,

OR 2.

immediately initiate action to fully insert all insertable control rods and within one hour place the reactor mode switch in the Shutdown position.

b. With the refuel position one-rod-out interlock inoperable, 1.

immediately suspend control rod withdrawal, 2.

immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, and

3. place the reactor mode switch in the Shutdown position.

c.

With one or more required control rod position indication channels inoperable, 1.

a. immediately suspend in-vessel fuel movement

b. immediately suspend control rod withdrawal,

c. immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, OR 2.

a. initiate action to fullyinsert the control rod associated with the inoperable position indicator, and

b. initiate action to disarm the control rod drive associated with the fully inserted control rod.

OR 3.

a. immediately initiate action to fullyinsert all insertable control rods in core cells containing one or more fuel assemblies, and

b. within one hour place the reactor mode switch in the Shutdown position.

SUSQUEHANNA - UNIT2 3/4.10-8 Amendment No.

0 I

SPECIAL TEST EXCE ON ACTION (Continued)

d. With one or more withdrawn control rods inoperable, immediately initiate action to fully insert inoperable withdrawn control rods and within one hour place the reactor mode switch in the Shutdown position.

e. With all other control rods in a five by five array centered on the control rod being withdrawn not disarmed, immediately initiate action to fully insert the withdrawn control rod and within one hour place the reactor mode switch in the Shutdown position.

f.

With all other control rods not fully inserted, immediately initiate action to fully insert all control rods and within one hour place the reactor mode switch in the Shutdown position.

SURVEILLANCEREQUIREMENTS 4.10.7.1 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify reactor mode switch locked in Refuel position.

4.10.7.2 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a. verify all control rods, other than the control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.+

b. verify all control rods, other than the control rod being withdrawn, are fully inserted.

4.10.7.3 Once per 7 days, a.

perform a CHANNEL FUNCTIONALTEST on the Refuel position one-rod-out interlock.*

b.

insert each withdrawn control rod at least one notch.¹

c. verify each withdrawn control rod scram accumulator pressure is z 940 psig.

4.10.7.4 Each time the control rod is withdrawn from the "full-in" position, verify the required channel has no "full-in" indication on each control rod that is not "full-in".

4.10.7.5 Perform LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 Surveillance Requirements for Functions 1.a, 1.b, 8.a, 8.b, 11, and 12 of Table 4.3.1.1-1 SUSQUEHANNA-UNIT2 3/4.10-9 Amendment No.

~,

J SPECIAL TEST EXCE ION SURVEILLANCERE UIREMENTS (Continued)

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

¹ Not required to be performed until 7 days after the control rod is withdrawn.

+

Not required to be met if LCO requirements are being satisfied by 3.10.7.d.1 requirements.

- Except that the one hour to insert all insertable control rods allowed by ACTIONs 3 and 9 of Table 3.3.1-1 is not applicable.

The insertable control rods are to be inserted immediately.

SUSQUEHANNA - UNIT2 3/4.10-10 Amendment No.

SPECIAL TEST EXCEPTION 3/4.10.8 SINGLE CONTROL ROD WITHDRAWAL-COLD SHUTDOWN LIMITINGCONDITION FOR OPERATION I

3.10.8 The reactor mode switch position specified in Table 1.2 for OPERATIONAL CONDITION 4 may be changed to include the Refuel position to allow withdrawal of a single control rod provided the following requirements are met:

a.

Allother control rods are fullyinserted; b.

The refuel position one-rod-out interlock shall be OPERABLE, and c.

The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

d.

1.

a.

LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 requirements for Functions 1.a, 1.b, 8.a, 8.b, 11, and 12 of Table 3.3.1-1, and b.

Each withdrawn control rod shall be OPERABLE.

OR All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "Shutdown Margin", OPERATIONAL CONDITION 4 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY:

OPERATIONAL CONDITION 4 with the reactor mode switch in the Refuel position.

SUSQUEHANNA-UNIT2 3/4. 10-11 Amendment No.

SPECIAL TEST EXCE ON ACTION:

a.

Ifthe affected control rod is insertable:

1. With one or more of Functions 1.a, 1.b, S.a, 8.b, 11 and 12 of Table 3.3.1-1 OPERATIONAL CONDITION 5 requirements not being met:

a.

immediately enter the ACTION Statement for that function **,

OR b.

immediately initiate action to fully insert all insertable control rods and within one hour place the reactor mode switch in the Shutdown position.

2. With the refuel position one-rod-out interlock inoperable, a.

immediately suspend control rod withdrawal, b.

immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, and c.

place the reactor mode switch in the Shutdown position.

3. With one or more required control rod position indication channels inoperable, a.

i. immediately suspend in-vessel fuel movement ii. immediately suspend control rod withdrawal, iii.immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies, and OR b.

i. initiate action to fullyinsert the control rod associated with the inoperable position indicator, and ii. initiate action to disarm the control rod drive associated with the fully inserted control rod, OR c.

i.

immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies,and ii. within one hour place the reactor mode switch in the Shutdown position.

SUSQUEHANNA - UNIT2 3/4.10-12 Amendment No.

SPECIAL TEST EXCE ON ACTIONS (Continued)

4. With one or more withdrawn control rods inoperable, immediately initiate action to fully insert inoperable withdrawn control rods and within one hour place the reactor mode switch in the Shutdown position.

5. With all other control rods in a five by five array centered on the control rod being withdrawn not disarmed, immediately initiate action to fully insert the withdrawn control rod and within one hour place the reactor mode switch in the Shutdown position.

6. With all other control rods not fully inserted, immediately initiate action to fully insert all control rods and within one hour place the reactor mode switch in the Shutdown position.

b.

Ifthe affected control rod is not insertable:

1

~ Immediately suspend withdrawal of the control rod, AND 2.

a.

immediately initiate action to fully insert all control rods, OR b.

immediately initiate action to satisfy the requirements of this LCO.

SURVEILLANCEREQUIREMENTS 4.10.8.1 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify reactor mode switch locked in Refuel position.

4.10.8.2 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a. verify all control rods, other than the control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.+

b. verify all control rods, other than the control rod being withdrawn, are fully inserted.

c. verify a control rod withdrawal block is inserted.++

SUSQUEHANNA-UNIT2 3/4.10-13 Amendment No.

l 4p

~ 0

I

,L SPECIAL TEST EXCE ON SURVEILLANCERE UIREMENTS Continued 4.10.8.3 Once per 7 days, a.

perform a CHANNELFUNCTIONALTEST on the Refuel position one-rod-out interlock.*

b.

insert each withdrawn control rod at least one notch.¹ c.

verify each withdrawn control rod scram accumulator pressure is z 940 pslg.

4.10.8.4 Each time the control rod is withdrawn from the "full-in" position, verify the required channel has no "full-in" indication on each control rod that is not "full-in".

4.10.8.5 Perform LCO 3.3.1, "Reactor Protection System Instrumentation,"

OPERATIONAL CONDITION 5 Surveillance Requirements for Functions 1.a, 1.b, 8.a, 8.b, 11, and 12 of Table 4.3.1.1-1 Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

¹ Not required to be performed until 7 days after the control rod is withdrawn.

+

Not required to be met if LCO requirements are being satisfied by 3.10.8.c.1 requirements.

++ Not required to be met if LCO requirements are being satisfied by 3.10.8.b.1 requirements.

- Except that the one hour to insert all insertable control rods allowed by ACTIONs 3 and 9 of Table 3.3.1-1 is not applicable.

The insertable control rods are to be inserted immediately.

SUSQUEHANNA-UNIT2 3/4.10-14 Amendment No.

FEB GS '97 18:26AN PP SRA4 I

BASES Tho requirement for PRIMARY CONTAINMENTINTEGRITY is not spplicablo during the period whon open vassal tests ero being performed during the low power PHYSICS TESTS.

In order to perform tho tests required in tho tcchnical specifications it is necessary to bypass tho sequence restraints on control rod movement.

Tho additional surveillance requirements ensure that tho specifications on heat generation rates and shutdown margin requirements are not exceeded during tho poriod whon theso toots a'e being performed and that individual'od worths do nct exceed tha values assumed in tho safety analysis.

I Performance of shutdown margin demonstrations with the.vassal head removed requfros additional restrictions in order to ensure that crltlcallty does not occdr.

These additional restrictions aro.specified In this LCO..

t This sp'acial tost exception permits reactor criticality'under no flow conditions and is required to perform certain stanup and PHYSICS TESTS white at low THERMAI.POWER levels, I

I This spocial test exception permits training startups to be performed with the ronctor vassal dopressunzed et lcw THERMAI. POWER and temperature while controlling RCS temperature with one RHR subsystem aligned in the shutdown cooling mode ln order to minimizo contaminated water discharge tc the radioactive waste disposal system.

This special test oxcoption allows reactor vessel Inservica leak and hydrostatic testing to be performed in OPERATIONAl CONDITION 4 with reactor coolant temperatures 8212 F.

The additionally. imposed OPERATIONAI.

CONDITION 3

requirement for SECONDARY CONTAINMENT INTEGRITY provides conservatism In the response of the'unit to on operational event.

This allows flexibility since temperatures approach 200'F during tho tasting and can drift higher because'of docay and mechanicai heat.

The reactor coolant temperature ts contra'lied to insure that it does not exceed 2124F.

Since the reactor coolant temperature is at or bolow 2124F, minimum water lovel in tho suppression chamber in OPGRATIONAI. 'ONDITION 4 Is sufficient to provldo pressure suppression ond adequato NPSH for ECCS pump operation.

This cbnditlon is bounded. by the, analysis provided in support of EO.200-103 for prcssure suppression.

Q~ycN A SUSQUEHANNA ~ UNIT2

.8 3/4 10-1, N,

Amendmant No. 112

INSERT A 3/4.10.7 SINGLE CONTROL ROD WITHDRAWAL-HOT SHUTDOWN The purpose of this OPERATIONAL CONDITION 3 Special Test Exception is to permit the withdrawal of a single control rod for testing while in Hot Shutdown, by imposing certain restrictions.

In OPERATIONAL CONDITION 3, the reactor mode switch is in the Shutdown position and all control rods are inserted and blocked from withdrawal. Many systems and functions are not required in these conditions, due to the other installed interlocks that are actuated when the reactor mode switch is in the Shutdown position.

However, circumstances may arise while in OPERATIONAL CONDITION 3 that present the need to withdraw a single control rod for various tests (e.g., friction tests, scram timing, and coupling integrity checks).

These single control rod withdrawals are normally accomplished by selecting the Refuel position for the reactor mode switch.

The withdrawn control rod is considered to be OPERABLE if the scram accumulator pressure is z 940 psig and the control rod is capable of being automatically inserted upon receipt of a scram signal.

3/4.10.8 SINGLE CONTROL ROD WITHDRAWAL-COLD SHUTDOWN The purpose of this OPERATIONAL CONDITION 4 Special Test Exception is to permit the withdrawal of a single control rod for testing while in Cold Shutdown, by imposing certain restrictions.

In OPERATIONAL CONDITION 4, the reactor mode switch is in the Shutdown position and all control rods are inserted and blocked from withdrawal. Many systems and functions are not required in these conditions, due to the other installed interlocks that are actuated when the reactor mode switch is in the Shutdown position.

However, circumstances may arise while in OPERATIONAL CONDITION 4 that present the need to withdraw a single control rod for various tests (e.g., friction tests, scram timing, and coupling integrity checks).

These single control rod withdrawals are normally accomplished by selecting the Refuel position for the reactor mode switch.

The withdrawn control rod is considered to be OPERABLE if the scram accumulator pressure is a 940 psig and the control rod is capable of being automatically inserted upon receipt of a scram signal.

Technical Specification 3/4.9.10.1 governs single control rod removal in OPERATIONAL CONDITION 4.

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ML18026A471

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