Text

Amends 215 & 205 to Licenses DPR-77 & DPR-79,respectively. Amends Address Operation W/Rod Urgent Failure Condition, Including Limited Operation W/One Control or Shutdown Bank Inserted 18 Steps Below Insertion Point
	ML20094N525
Person / Time
Site:	Sequoyah
Issue date:	11/21/1995
From:	Hebdon F; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20094N527	List: ML20094N525; ML20094N534;
References
	NUDOCS 9511280073
	Download: ML20094N525 (18)
	v • d • e

I Q

p nciouq p*

4 UNITED STATES s

j NUCLEAR REGULATORY COMMISSION l

WASHINGTON, D.C. 20656 4 001

%4.....,&

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0VOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 License No. DPR-77 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 7, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and 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 rules and regulations of the Comission; 1

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the hesith and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.

l 9511280073 951121 PDR ADOCK 05000327 P

PDR

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 215, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION h

Frederick J. Hebd n, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 21, 1995

1 l

ATTACHMENT 1 TO LICENSE AMENDMENT NO. 215 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMQYE INSERT 3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15 3/4 1-20 3/4 1-20 3/4 1-21 3/4 1-21 B 3/4 1-4 8 3/4 1-4 B 3/4 1-4a 1

i

-.m

N 0

REACTIVITY CONTROL SYSTEMS _

3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and wontrol) rods shall be OPERABLE and positioned within t 12 steps (indicated pesitions of their group step counter demand position.

APPLICABILITY: MODES 1* and 2*

ACTION:

a.

With one or more full length rods untrippable, determine that the l

SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With more than one full length rod misaligned from the group step l

counter demand position by more than t 12 steps (indicated position),

be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one full length red misaligned from its group step counter l

demand height by more than 12 steps (indicated position), POWER OPERATION may continue provided that within one hour either:

1.

The rod is restored within the above alignment requirements, or l

2.

The remainder of the rods in the group with the misaligned rod are aligned to within t 12 steps of the misaligned rod while maintaining the rod sequence and insertion limit of specification 3.1.3.6.

The THERMAL POWER level shall be lR159 restrictec pursuant to specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

i

See Special Test Exceptions 3.10.2 and 3.10.3.

SEQUOYAH - UNIT 1 3/4 1-14 Amendment No. 114, 155, 215

b.

REACTIVITY CONTROL SYSTEMS 1

)

ACTION:

(Continued)

[

a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these

-conditions.

b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is FP determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c)

A power distribution map is obtained from the movable N

incere detectors and F (Z) and F are verified to be g

within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next '4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at l

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be trippable by verifying rod freedom of movement by movement of a 10 steps in either direction at least once per 92 days.

l i

SEQUOYAH - UNIT 1 3/4 1-15 Amendment No. 215 i

=

i

i i

t I

REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT i

' LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be limited in physical insertion as specified lR159 in the COLR.

i APPLICABILITY: HODES 1* and 2*#

ACTION:

i a.

With a maximum of one shutdown rod inserted beyond the insertion R159 limit specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2 or when complying with ACTION b of this specification, within one hour either j

1.

Restore the rod to within the insertion limit specified in the l

COLR, or 2.

Declare the rod to be inoperable and apply ACTION 3.1.3.1.c.3.

l

[

b.

With a maximwn of one shutdown bank inserted beyond the insertion limit specified in the COLR during surveillance testing pursuant to

' Specification 4.1.3.1.2 and immovable due to malfunctions in the rod control system, POWER OPERATION may continue provided that:

1.

The shutdown bank is inserted no more than 18 steps below the insertion limit as measured by the group step counter demand position indicators, 2.

The affected bank is trippable, 3.

Each shutdown and control rod is aligned to within 12 steps of its respective group step counter demand position, 4.

The insertion limits of Specification 3.1.3.6 are met for each control bank, I

5.

No reactor coolant system boron concentration dilution

)

activities or power level increases are allowed, I

6.

The SNUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined to be met at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or upon insertion of the controlling bank more than 5 steps from the initial position, and 4

7.

The shutdown bank is restored to within the insertion limit specified in the COLR within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS e

4.1.3.5 Each shutdown rod shall be determined to be within the insertion limit lR159 specified in the COLR a.

Within 15 minutes prior to withdrawal of any rods in control 4

banks A, B, C or D during an approach to reactor criticality, and

-b.

At least.once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

5

See Special Test Exceptions 3.10.2 and.3.10.3.

j

With K,gg greater than or equal to 1.0.

lR159 SEQUOYAH - UNIT l' 3/4 1-20 Amendment No. 108, 155, 215

4 REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified lR159 in the COLR.

APPLICABILITY: MODES 1* and 2*#,

ACTION:

a.

With the control banks. inserted beyond the above insertion limits, R159 except for surveillance testing pursuant to Specification 4.1.3.1.2 or when complying with ACTION b of this specification,,either:

l 1.

Restore the control banks to within the limits within two hours, j.

or 2.

Reduce THERMAL POWER within two hours to less than or equal to l

that fraction of RATED THERMAL POWER which is allowed by the group position using the insertion limits specified in the COLR, lR159 or 3.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l

{

b.

With a maximum of one control bank inserted beyond the insertion limit specified in the COLR during surveillance testing pursuant to l

ipecification 4.1.3.1.2 and immovable due to malfunctions in the rod i

ontrol system, POWER OPERATION" may continue provided that:

1.

The control bank is inserted no more than le steps below the insertion limit as measured by the group step counter demand position indicators, 2.

The affected bank is trippable, 3.

Each shutdown and control rod is aligned to within 2 12 steps of its respective group step counter demand position, 4.

The insertion limits of Specification 3.1.3.5 are met for each shutdown bank, 5.

No reactor coolant system boron concentration dilution activities or power level increases are allowed, 6.

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined to be met at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or upon insertion of the controlling bank more than 5 steps from the l-initial position, and 7

The control bank is restored to within the insertion limit specified in the COLR within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 1

i l

4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod 1:

positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i

See Special Test Exceptions 3.10.2 and 3.10.3.

l i

With K,gg greater than or equal to 1.0

1. Provision for continued POWER OPERATION does not apply to the controlling bank (s) (normally Control Bank D) inserted beyond the insertion limit.

SEQUOYAH - UNIT l' 3/4 1-21 Amendment No. 41, 114, 155,215 4

.n

- - ~,, -, - -.

e

.- --.~.

~..

6-REACTIVITY CONTROL SYSTEMS l.

BASES I

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.

Misalignment of a rod requires measurement 4

l of peaking factors and a restriction in THERMAL POWER. These restrictions i

provide assurance of fuel rod integrity during continued operation.

In

~

those accident analyses affected by a misalignment rod are reevalu-l

addition, l

ated to confirm that the results remain valid during future operation.

t In the event that a malfunction of the Rod Control System renders. control rods 4

immovable, provision is made for continued operation provided:

i o

The affected concrol rods remain trippable, and o

The individual control rod alignment limits are met.

In the event that a malfunction of the Rod Control System renders control rod j

banks immovable during surveillance testing, provision is made for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of continued operation provided:

a

)

i o

The affected control rod banks' remains trippable, l

o The. individual control red alignment limits are met, 1

1 o

A maximum of one control or shutdown bank is inserted no more than l

1 18 steps below the insertion limit, o

No reactor coolant system boron concentration dilution activities or power level increases are allowed, and a

4 o

The SHUTDOWN MARGIN requirements are verified every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or upon i

insertion of controlling bank during the period the insertion limit l

is not met.

l The requirements to preclude Reactor Coolant System boron concentration dilution, while a control or shutdown bank is below insert limits, will minimize the impact on shutdown margin.

l-1 The controlling bank (s), which is normally Control Bank D, is excluded from the l

72-hour provision since insertion of this bank (s) below the insertion limit is F

not required for control rod assembly surveillance testing. A controlling bank is defined as any control bank that is less than fully withdrawn as defined in the COLR with the exception of fully withdrawn banks that have been inserted in j

accordance with Surveillance Requirement 4.1.3.1.2.

This provision excludes j

the use of the 72-hour allowance for control banks that can be exercised 10 steps in either direction without exceeding the insertion limits.

j Checks are performed for each reload core to ensure that bank insertions of up to 18 steps will not result in power distributions, which violate the DNB criterion for ANS Condition II transients (moderate frequency transients 1

i.

analyzed in Section 15.2 of the UFSAR). Administrative requirements on the i

initial controlling bank position will ensure that this insertion and an l

additional controlling bank insertion of five steps or less will not violate the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 during the repair period.

If the controlling bank is inserted more than five steps deeper than its. initial position, a calculation will be performed to ensure that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is met.

Since no dilution j

or power level increases are allowed, shutdown margin will be maintained as 1.

long as the controlling bank is far enough above its insertion limit to compensate for the inserted worth of the bank that is beyond its insertion s

limit.

J The 72-hour. period for a control rod assembly bank to be inserted below its F

insertion limit restricts the likelihood of a more severe (i.e., ANS Condition III or IV) accident or transient condition occurring concurrently with the insertion limit violation.

l SEQUOYAH - UNIT 1 B 3/4 1-4 Amendment No. 108, 215 l

i REACTIVITY CONTROL SYSTEMS l

BASES The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with T greater than or avg equal to 541*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

3/4.1,3.4 ROD DROP TIME and 3/4.1.3.5 SHUTDOWN RCD INSERTION LIMIT Fully withdrawn for shutdown and control rod banks is defined as a condition where the rod banks are positioned in a range of 222 to 231 steps R112 fully withdrawn. This range is defined to permit axial repositioning of rod banks to mitigate rod wear on internal guide surfaces.

j 1

4 i

I SEQUOYAH - UNIT 1 B 3/4 1-4a Amendment No. 108, 215 l

.. -. -.. - -. - - _ -.. ~.. - - - - -.. -.

,s ut p

4 UNITED STATES g

j NUCLEAR REGULATORY COMMISSION l

- - - - /.

WASHINGTON, D.C. 30eeH001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 k

AMENDMENT TO FACILITY OPERATING LICENSE 4

Amendment No. 205 License No. DPR-79 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August-7, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

j and the Commission's rules and regulations set forth in 10 CFR 1

Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and 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; 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.

L.

k j

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices'A and B, as revised through Amendment No. 205, are hereby incorporated in the license. The licensee shall operate the facility in accordance with j

the Technical Specifications.

l-3.

This license amendment is effective as of its date of issuance, to be implemented within 45 days.

FOR THE NUCLEAR REGULATORY COMISSION Frederick J. Hebd n, Director Project Directorate II-3 Division of Reactor Projects - I/II j

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 21, 1995 I

4 4

l

^

I l

l

('

ATTACHMENT TO LICENSE AMENDMENT NO. 205 i

FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 i

Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the c.aptioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15 3/4 1-20 3/4 1-20 3/4 1-21 3/4 1-21 B 3/4 1-4 B 3/4 1-4 B 3/4 1-4a e

I i

i t

u

~~ -.. - -...-. -. -

_.. -. -... ~.. -.

l REACTIVITY CONTROL SYSTEMS 1

3/4.1.3 MOVARTW CONTROL ASSEMBLIES GROUP HEIGHT i

j

' LIMITING CONDITION FOR OPERATION 4

i 3.1.3.1 All full length (shutdown and control) rods shall be OPERABLE and positioned within t 12 steps (indicated position) of their group step counter 1

. demand position.

=

4 i

}

APPLICABILITY: Modes 1* and 2*.

M1.M 3 c.

With one or more full length rods untrippable, determine that the l

SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied 1

-c within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j b.

With more than one full length rod misaligned from the group step l

counter demand position by more than 2 12 steps (indicated j

position), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one full length rod misaligned from its group step counter l.

demand height by more than 212 steps (indicated position), POWER' i

OPERATION may continue provided that within one hour either:

1.

The rod is restored within the above alignment requirements, l

I 1

or l

2.

The remainder of the rods in the group with the misaligned j

rod are aligned to within t 12 steps of the misaligned rod while maintaining the rod sequence and insertion limit of i

specification 3.1.3.6.

The THERMAL POWER level shall be R146 restricted pursuant to specification 3.1.3.6 during 4

subsequent operation, or a

i 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

I a)

A reevaluation of each accident analysis of Table 3.1-1 l

is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these 4

accidents remain valid for the duration of operation under these conditions.

I

{

See Special Test Exceptions 3.10.2 and 3.10.3.

1 i

i 4

SEQUOYAH - UNIT 2 3/4 1-14 Amendment Nos. 104, l'46,205 3

i,..,..

4 l

REACTIVITY CONTROL SYSTEMS ACTIQN:

(Continued) b)

The SKUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c)

A power distribution map is obtained from the movable incore detectors and F (Z) and F H

i limits within 72 haurs.

d)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be trippable by verifying rod freedom of movement by movement of 10 steps in either direction at least once per 92 days.

a l

l I

1 SEQUOYAH - UNIT 2 3/4 1-15 Amendment No. 205 4

=

1-.

L.

4 REACTIVITY CONTROL SYSTEMS 1

]

SNyTDOWN RCD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 1

4 l.

3.1.3.5 All shutdown rods shall be limited in physical insertion as specified lR146 in the COLR APPLICABILITY: Modes 1* and 2*#.

4.

ACTIQN:

l j

a.

With a maximum of one shutdown rod inserted beyond the insertion l

j limit specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2 or when complying with ACTION b,of this specification, within one hour either:

1.

Restore the rod to within the insertion limit specified in the l

COLR, or 2.

Declare the rod to be inoperable and apply ACTION 3.1.3.1.c.3.

l

?

b.

With a maximum of one shutdown bank inserted beyond the insertion limit specified in-the COLR during surveillance testing pursuant to j-Specification 4.1.3.1.2 and immovable due to malfunctions in the rod i

control system, POWER OPERATION may continue provided that:

+

1.

The shutdown bank is inserted no more than 18 steps below the j

insertion limit as measured by the group step counter demand

+

position indicators, 2.

The affected bank is trippable, 3.

Each shutdown and control rod is aligned to within i 12 steps of its respective group step counter demand position, 4.

The insertion limits of Specification 3.1.3.6 are met for each control bank, 5.

No reactor coolant system boron concentration dilution 2

i activities or power level increases are allowed, 6.

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined to be met at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or upon insertion of the controlling bank more than 5 steps from the initial position, and 7.

The shutdown bank is restored to within the insertion limit specified in the COLR within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , f

SURVEILLANCE REQUIREMENTS 1

4.1.3.5 Each shutdown rod shall be determined to be within the insertion limit lR146 specified in the COLR a.

Within 15 minutes prior to withdrawal of any rods in control banks A, B, C or.D during an approach to reactor criticality, and b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'thereafter.

l

See special Test Exceptions 3.10.2 and 3.10.3.

With K,gg greater than or equal to 1.0 R146 SEQUOYAH -' UNIT 2 3/4 1-20 Amendment No. 98, 146, 205 U

t

... _. _. ~..

i

)

REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS i

LIMITING CONDITION FOR OPERATION t

3.1.3.6 The control banks shall be limited in physical insertion as specified R146 l

in the COLR 1

APPLICAB M : Modes 1* and 2*#.

ACTION:

a.

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2 or when complying with ACTION b of this specification,'either:

1.

Restore the control banks to within the limits within two hours, l

or 2.

Reduce THERMAL POWER within two hours to less than or equal to l

that fraction of RATED THERMAL POWER which is allowed by the group position using the insertion limits specified in the COLR, i

or 1

3.~

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

b.

With a maximum of one control bank inserted beyond the insertion j

limit specified in the COLR during surveillance testing pursuant to i

Specification 4.1.3.1.2 and immovable due to malfunctions in'the rod j

control system, POWER OPERATION" may contlnue provided that:

i

[

1.

The control bank is inserted no mere than 18 steps below the J

insertion limit as measured by the group step counter demand position indicators, 2.

The affected bank is trippable, 3.

Each shutdown and control rod is aligned to within 2 12 steps of its respective group step counter demand position, 4.

The insertion limits of Specification 3.1.3.5 are met for each i

shutdown bank, j

l 5.

No reactor coolant system boron concentration dilution i

activities or power level increases are allowed, 6.

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined to be met at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or upon insertion of the controlling bank more than 5 steps from the I

initial position, and 7.

The control bank is restored to within the insertion limit l

specified in the COLR within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

SURVEILLANCE REQUIREMENTS

)

i I

4.1.3.6 The position of'each control bank shall be determined to be within the.

insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod

. positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

A

See Special Test Exceptions 3.10.2 and 3.10.3.

With K,gg greater than or equal to 1.0.

1. Provision for continued POWER OPERATION does not apply to the controlling bank (s) (normally control Bank D) inserted beyond the insertion limit.

SEQUOYAN'- UNIT 2 3/4 1-21 Amendment No. 33, 104, 146, 205 e

_ _.- ~

~. - - - - -. -.. _ -.

j J

REACTIVITY CONTROL SYSTEMS BASES 1

j-MOVEABLE CONTROL ASSEMBLIES (Continued)

.The ACTION statements which permit limited variations-from the basic requirements are accompanied by additional restrictions which ensure that the j

-original design criteria are met.

Misalignment of a rod requires measurement i

of peaking factors and a restriction in THERMAL POWER. These restrictions j

provide assurance of fuel rod integrity during continued operation.

In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

In the event that a malfunction of the Rod Control System renders control rods j

immovable, provision is made for continued operation provided:

i o

The affected control rods remain trippable, and o

The individual control rod alignment limits are met.

J

]

In the event that a malfunction of the Rod Control System renders control rod

. banks immovable during surveillance testing, provision is made for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of continued operation provided:

)

4 o

The affected control rod banks remains trippable, o

'The individual control rod alignment limits are met, i

o A maximum of one control or shutdown bank is inserted no more than 18 steps below the insertion limit,

)

o No reactor coolant system boren concentration dilution activities' or power level increases are allowed, and o

The SHUTDOWN MARGIN requirements are verified every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or upon insertion of controlling bank during the period the insertion limit is not met.

I The requirements to preclude Reactor Coolant System boron concentration dilution, while a control or shutdown bank is below insert limits, will minimize the impact on shutdown margin.

F The controlling bank (s), which is normally control Bank D, is excluded from the l

72-hour provision since insertion of this bank (s) below the insertion limit is not required for control rod assembly surveillance testing. A controlling bank i

is defined as any control bank that is less than fully withdrawn as defined in a

I j

the COLR with the exception of fully withdrawn banks that have been inserted in i

accordance with surveillance Requirement 4.1.3.1.2.

This provision excludes the use of the 72-hour allowance for control banks that can be exercised 10 steps in either direction without exceeding the insertion limits.

Checks.are performed for each reload core to ensure that bank insertions of up to 18 steps will not result in power distributions, which violate the DNB i

criterion for ANS Condition II transients (moderate frequency transients l

analyzed in Section 15.2 of the UFSAR). Administrative requirements on the 1

4 initial controlling bank position will ensure that this insertion and an additional controlling bank insertion of five steps or less will not violate the SNUTDOWN MARGIN requirement of Specification 3.1.1.1 during the repair period.

If the controlling bank is inserted more than five steps deeper than its initial position, a calculation will be performed to ensure that the l

SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is met.

Since no dilution or power level increases are allowed, shutdown margin will be maintained as long as the controlling bank is far enough above its insertion limit to j

compensate for the inserted worth of the bank that is beyond its insertion limit.

]

i The 72-hour period for a control rod assembly bank to be inserted below its insertion limit restricts the likelihood of a more severe (i.e., ANS Condition III or IV) accident or transient condition occurring concurrently with the insertion limit violation.

SEQUOYAM - UNIT 2 B 3/4 1-4 Amendment'No. 98, 205

REACTIVITY CONTROL SYSTEMS BASES The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with T greater than or avg equal to 541*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions'and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if an automatic monitoring channel is

-inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

3/4.1.3.4 ROD DROP TIME and 3/4.1.3.5 SHUTDOWN ROD INSERTION LIMIT Fully withdrawn for shutdown and control rod banks is defined as a condition where the rod banks are positioned in a range of 222 to 231 steps R98 fully withdrawn. This range is defined to permit axial repositioning of rod banks to mitigate rod wear on internal guide surfaces.

)

l 4

SEQUOYAH - UNIT 2 B 3/4 1-4a AmendmentNo.98,205l

- - -

ML20094N525

Text

Attachment:

Attachment:

Navigation menu

Search