Text

Amends 165 & 137 to Licenses NPF-14 & NPF-22,respectively, Revising TSs to Reflect Two Sections of Requested Improved Tss,Lco 3.10.3, Single CR Withdrawal Hot Shutdown, & LCO 3.10.4, Single CR Withdrawal Cold Shutdown
	ML17158C116
Person / Time
Site:	Susquehanna
Issue date:	04/23/1997
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Pennsylvania Power & Light Co, Allegheny Electric Cooperative
Shared Package
ML17158C117	List: ML17158C116; ML17158C118; ML17158C119;
References
	NPF-14-A-165, NPF-22-A-137 NUDOCS 9705010339
	Download: ML17158C116 (39)
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t uNn'FD STATES NUGlEAR REGULATORY GOMMlSSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER

8. LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.

DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.>6>

License No'.

NPF-14 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power 5 Light Company, dated February ll, 1997, and as amended on April 7,

1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2)

Technical S ecif cations'nd Enviro mental Protection Pla The Technical Specifications contained in Appendix A, as revised through Amendment No.

165 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license'.

PPLL shall operate the facility in accordance 'with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 23, 1997 John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO. 165 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

RENOVE 1-10 INSERT 1-10 3/4 10-7 3/4 10-8 3/4 10-9 3/4 10-10 3/4 10-11 3/4 10-12 3/4 10-13 3/4'0-14 B 3/4 10-la

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 Shutdown Shutdown Shutdown" "'

or Refuel'"

'VERAGE REACTOR COOLANT TEMPERATURE Any temperature Any temperature 200oF 200oF 140oF

¹ The 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 unit technical staff.

¹¹ The reactor mode switch may be placed in the Refuel position while a single 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 3.10.1 and 3.10.3.

The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE. Also see Special Test Exception 3.10.7 and 3.10.8.

+

See Special Test Exception 3.10.6.

SUSQUEHANNA - UNIT 1

, 1-10 Amendment No. iÃ

LIMITINGCONDITION FOR OPERATION 1'.10.7 The reactor mode switch position specified in Table 1.2 fpr 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, S.a, S.b, 11 and 12 of Table 3.3.1-1, and b, Each withdrawn control rod shall be OPERABLE.

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 3 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

OPERATIONAL CONDITION 3 with the reactor mode switch in the Refuel

, position.

SUSQUEHANNA - UNIT 1 3/4 10-7 Amendment No.

/g 1'

~

a.

With one or more of Functions 1.a, 1.b, S.a, S.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 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, 2.

a.

initiate action to fully insert 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, 3.

a.

immediately initiate action to fully insert 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, 165

, kQIIQH,{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 4.1 0.7 '

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 c 940 pslg.

4.1 0.7.4 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, S.a, S.b, 11, and 12 of Table 4.3.1.1-1

~

SUSQUEHANNA - UNIT 1 3/4 10-9 Amendment No.165

(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 - UNIT 1 3/4 10-10 Amendment No. i6~

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.

All other 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, 8.a, B.b, 11 and 12 of Table 3.3.1-1, and

b. Each withdrawn control rod shall be OPERABLE.

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.

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

SUSQUEHANNA - UNIT 1 3/4 10-11 Amendment No. 165

hQILQIR:

a.

If the 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 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, b.

i.

initiate action to fully insert 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, 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 - UNIT 1 3/4 10-12 Amendment No. i6~

'ggJ395 (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.

If the 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, 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. i65

0

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(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 ail 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 CHANNEL FUNCTIONAL TEST on the Refuel position one-rod-out interlock."

b.

insert each withdrawn control rod at least one notch.

c.

verify each withdrawn control rod scram accumulator pressure is 2 940 psig.

4.10.8A Each tim'e 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.d.1 requirements.

++

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

SUSQUEMANNA - UNIT 1 3/4 10-14 Amendment No

,BASES 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 2 940 psig and the control rod is capable of being automatically inserted upon receipt of a scram signal.

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 2 940 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.

SUSQUEHANNA - UNIT 1 B 3/4 10-1a Amendment No. ~65

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 PENNSYLVANIA POWER

& LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.

DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.137 License No.

NPF-22 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power Light Company, dated February 11,

1997, and as amended on April 7,

1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.

NPF-22 is hereby amended to read as follows:

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 1>>

a'nd the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PPEL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION John F. Stolz, Director, Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 23, 1997

0

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO, NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE 1-10, INSERT 1-10 3/4 10-7

'3/4 10-8 3/4 10-9 3/4'0-10 3/4 10-11 3/4 10-12 3/4 10-13 3/4 10-14 8 3/4 10- 1 a

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 Shutdown Shutdown'" """

Shutdown" ""

or Refuel""

AVERAGE REACTOR COOLANT TEMPERATURE Any temperature Any temperature

) 200'F 200oF 5 140~F

¹ The 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 unit technical staff.

¹¹ The reactor mode switch may be placed in the Refuel position while a single 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 3.10.1 and 3.10.3.

The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE. Also see Special Test Exceptions 3.10;7 and 3.10.8."

+

See Special Test Exception 3.10.6.

SUSQUEHANNA - UNIT 2 1-10 Amendment No. ~37

LIMITINGCONDITION FOR OPERATION I

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, S.a, S.b, 11 and 12 of Table 3.3.1-1, and

b. Each withdrawn control rod shall be OPERABLE.

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 3 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

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

SUSQUEHANNA - UNIT 2 3/4 10-7 Amendment No. 137

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:

0 ~

1.

immediately enter the ACTION Statement for that function 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 suspendin-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, 2.

a.

initiate action to fully insert 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, QB 3.

a.

immediately initiate action to fully insert 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 2 3/4 10-8 Amendment No. 13?

'~1(95 fContinued) 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 FUNCTIONAL TEST on the Refuel position one-rod-out interlock. "

b.

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

verify each withdrawn control rod scram accumulator pressure is 2 940 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, S.a, S.b, 11, and 12 of Table 4.3,1.1-1.

SUSQUEHANNA - UNIT 2 3/4 10-9 Amendment No. ].37

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 2 3/4 10-10 Amendment No.137

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.

All other 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, B.a, B.b, 11 and 12 of Table 3.3.1-1, and

b. Each withdrawn control rod shall be OPERABLE.

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.

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

SUSQUEHANNA - UNIT 2 3/4 10-11 Amendment No. 137

a.

If the affected control rod is insertable:

1.

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

I ~

a.

immediately enter the ACTION Statement for that function 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, b.

i.

initiate action to fully insert 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, c.

i.

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

SUSQUEHANNA - UNIT 2 3/4 10-12 Amendment No. i37

hQIIQH (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 ail control rods and within one hour place the reactor mode switch in the Shutdown position.

b.

If the 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.

SURVEILLANCE REQUIREMENTS 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 - UNIT 2 3/4 10-13 Amendment No.137

(Continued) 4.10.8.3 Once per 7 days, a.

perform a CHANNEL FUNCTIONAL TEST on the Refuel position one-rod-out interlock."

b.

insert each withdrawn control rod at least one notch.

c.

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

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.d.1 requirements.'ot required to be met if LCO requirements are being satisfied by 3.10.8.b and 3.10.8.c 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 2 3/4 10-14 Amendment No. 137

BASES

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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.