Text

Amends 179 & 160 to Licenses NPF-4 & NPF-7,respectively, Revising NA-1&2 TS That Allow Plant Personnel to Effect Repairs to Rod Control Sys in Orderly Manner
	ML20064C218
Person / Time
Site:	North Anna
Issue date:	03/01/1994
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20064C221	List: ML20064C218;
References
	NUDOCS 9403090210
	Download: ML20064C218 (23)
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3 UNITED STATES

[

j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20666-0001 VIRGINIA ELECTRIC AND POWER COMPANY i

OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 179 License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated March 18, 1993, as supplemented by letter dated December 9, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission'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 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 Conaission's regulations and all applicable requirements have been satisfied.

9403090210 940301 PDR ADOCK 05000338 P

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!. l 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and i

paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby i

i amended to read as follows:

l (2) Technical Soecifications i

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 179, are hereby incorporated in the license. The licensee shall operate the facility in-accordance j

with the Technical Specifications.

3.

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

FOR HE NUCLEAR REGULATORY COMMISSION

~'

l Herbert N. Berkow, Director l

Project Directorate 11-2 Division of Reactor Projects - I/II i

Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical j

Specifications i

Date of Issuance: March 1, 1994 i

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i ATTACHMENT TO LICENSE AMENDMENT NO. 179 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO.50-31A Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lins.s indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Paaes Insert Paaes 3/4 1-18 3/4 1-18 3/4 1-24 3/4 1-24 l

3/4 1-24a l

3/4 1-25 3/4 1-25 3/4 1-25a B 3/4 1-4a B 3/4 1-4a i

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1 REACTIVITY CONTROL SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) a.

At least once per 7 days by:

j 1.

Verifying the boron concentration in each water source, 2.

Verifying the contained borated water volume of each i

water source, and 3.

Verifying the boric acid storage system solution i

tempe ra ture.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature.

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NORTH ANNA-UNIT 1 3/4 1-17 Amendment No. 5 b

l REACTMTY CONTROL SYSTRAR 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP ElGHT UMITING CONDITION FOR OPERATION 3.1.3.1 All shutdown and comrol rods shall be OPERABLE and positioned within i12 steps

of their group step counter demand position.

APPLICABILITY: MODES 1" and 2".

M'

a. With one or more rods untrippable, determine within one hour that the SHUTDOWN l

MARGIN requirement of Specification 3.1.1.1 is satisfied and be in HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With more than one rod misaligned from the group step counter demand position by l

more than the above alignment requirements, determine within one hour that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With a maximum of one rod misaligned from the group step counter demand position l

by more than the above alignment requirements, POWER OPERATION may continue provided that within one hour, either:

1. The rod is restored to OPERABLE status within the above alignment requirements, or

2. 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; a) A reevaluation of each accident analysis of Table 3.11 is performed within 5 days. This reevaluation shall confirm that the previous analyzed results of these accidents remain valid for the duration of operation under these conditions, and For power levels below 50% of RATED THERMAL POWER, the position of each rod as determined by its individual rod position indicator may be more than i12 steps from its group step counter demand position for a maximum of one hour in every 24. During this hour, the indicated position of each rod may be no more than i 24 steps from its demand position. The i 24 step / hour limit is not applicable when control rod position is known to be greater than 12 steps from the rod group step counter demand position indication.

See Special-Test Exceptions 3.10.2 and 3.10.3.

NORTH ANNA UNIT 1 3/4 1 18 Amendment NoA4, 448,179

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REACTIVITY CONTROL SYSTEMS l

R00 OROP TIME l

LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from the 229 STEP withdrawn position shall be l'2.7-seconds from beginning l

of decay of stationary gripper coil voltage to dashpot entry with:

a.

T 5

1 00 F, and avg b.

All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

With the drop time of any full length rod determined to exceed a.

the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined with 2 l

reactor coolant pumps operating, operation may proceed provided i

THERMAL POWER is restricted to:

l 1.

< 66% of RATED THERMAL POWER when the reactor coolant 5

stop valves in the nonoperating loop are open, or i

2.

< 71% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are closed.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:

For all rods following each removal of the reactor vessel head, a.

b.

For specifically affected individual rods following any main-tenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and c.

At least once per 18 months.

l NORTH ANNA-UNIT 1 3/4 1-23 Idendment No. MP, 149

SURVElu.ANCE REOUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be within the insertion limit specified in the CORE OPERATING UMITS REPORT

a. Within 15 minutes prior to initial control rod bank withdrawat 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 thereaher.

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l NORTH ANNA UNIT 1 3/4 1 ?4a Amenoment No.179 l

b REACTMTV CONTROL SYST9AS CONTROL RODINSERTION UMITS f

UMITING CONDmON FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified in the CORE OPERATING UMITS REPORT.

APPLICABILITY: MODES 1* and 2'#.

ACTION

a. With the control banks inserted beyond the insertion limits, except for surveillance l

testing pursuant to Specification 4.1.3.1.2, either:

1. Restore the control banks to within the insertion limits within two hours, or l

2. Reduce THERMAL POWER within two hours to less than or equal to that fraction of

.l RATED THERMAL POWER which is allowed by the rod group step counter demand position using the insertion limits specified in the CORE OPERATING LIMITS REPORT, or

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

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b. With a maximum of one control bank inserted beyond the insertion limit specified in the CORE OPERATING LIMITS REPORT 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 control 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 i 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, See Special Test Exceptions 3.10.2 and 3.10.3.

With Ketf 21.0.

1. Provision for continued POWER OPERATION does not apply to Control Bank D inserted beyond the insertion limit.

NORTH ANNA UNIT 1 3/4 1 25 Amendment No.408,446,179

LIMITING CONDITION FOR OPERATION (cont'd.)

5. 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 , and

6. the control bank is restored to within the insertion limit specified in the CORE OPERATING LIMITS REPORT 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 REOUIREMENTS 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 Umit Monitor is inoperable, then verify either the individual rod positions (indicated positions) or the group step counter demand position of each rod group to be within the insertion limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I NORTH ANNA UNIT 1 3/4 125a Arnendment No.179 l

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f NORTH ANNA UNIT 1 3/4 1-26 Amendment No.146

p REACTMTY COffTROL SYST9AS BASES (Continued)

The ACTION statements which permit limited variations from the basic requirements are i

accompanied by additional restrictions which ensure that the original design criteria are met.

l Misalignment of a rod requires measurement of peaking factors or a restriction in THERMAL l

POWER: either of these restrictions provides assurance of fuel rod integrity during continued l

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

l Continuous monitoring of rod position with respect to insertion limits and rod deviation l

is provided by the rod insertion limit monitor and rod position deviation monitor respectively.

l OPERABILITY of the rod position deviation monitor is verified by a functional test at least once per 7 days and by companson of the indicated positions versus the respective demand position indicators at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , if the rod position deviation monitor or the rod insertion limit monitor is inoperable, the frequency of manual comparison of indicated rod (or bank) j position is increased to an interval of at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

In the event that a malfunction of the Rod Control System renders control rods immovable, provision is made for continued operation provided:

the affected control rods remain trippable, and the individual control rod alignment limits are met, 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:

the affected control rod banks remain trippable, l

the individual control rod alignment limits are met, a maximum of one control or shutdown bank is inserted no more than 18 steps below the insertion limit, and the SHUTDOWN MARGIN requirements are verified every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during the period the insertion limit is not met.

Control Bank D is excluded from the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provision since insertion of D Bank below the insertion limit is not required for control rod assembly surveillance testing.

Checks are performed for each reload core to ensure that b nk insertions of up to 18 steps will not result in power distributions which violate the DNB c.narion for ANS Condition ll transients ( moderate frequency transients analyzed in Section 15.2 of the UFSAR) or in a violation of the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 during the repair period.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months period for a, control rod assembly bank to be inserted below its insertion limit restricts the IAelihood of a more severe (i.e., ANS Condition lit or IV) accident or transient condition oacurring concurrently with the insertion limit violation.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the acciden'. analyses. Measurement with Tavg 2 500*F and with all reactor coolant pumps operating er:sures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

NORTH ANNA UNIT 1 8 3/4 14a Amendment NoABB,179

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I t UNITED STATES

i. i^

3 NUCLEAR REGULATORY COMMISSION 3

I WASHINGTON, D.C. 20E0001

%,,.....f VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.160 License No. NPF-7 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated March 18, 1993, as supplemented by letter dated December 9, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission'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 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.

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1 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and 3

paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby l

amended to read as follows.

(2) Technical Soecifications 1

i The Technical Specifications contained in Appendices A and 8, as i

revised through Amendment.No. 160, are hereby incorporated in the i

license.

The licensee shall operate the facility in accordance j

with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall j

be implemented within 30 days, i

FOR THE NUCLEAR REGULATORY COMMISSION

~

H bert N. Berkow, Director 3

Project Directorate II-2 i

3 Division of Reactor Projects - I/II 0ffice of Nuclear Reactor Regulation

Attachment:

l Changes to the Technical Specifications Date of Issuance: March 1, 1994 i

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i ATTACHMENT TO LICENSE AMENDMENT NO. 160 TO FACILITY OPERATING LICENSE NO. NPF-7 i

DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by 8

amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document l

completeness.

Remove Paaes Insert Paaes 4

j 3/4 1-16 3/4 1-16 i

3/4 1-22 3/4 1-22 1

3/4 1-22a 3

3/4 1-23 3/4 1-23

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3/4 1-23a l

B 3/4 1-4a B 3/4 1-4a i

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REACTIVITY CONTROL SYSTEMS i

SURVEILLANCE REQUIREMENTS l

4.1.2.8 Each borated water source shall be demonstrated OPERABLE:

)

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a.

At least once per 7 days by:

i 1.

Verifying the boron concentration in each water source, 2.

Verifying the contained borated water volume of each water j

source, and i

3.

Verifying the boric acid storage system solution temperature.

3 b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature.

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i NORTH ANNA - UNIT 2 3/4 1-15 l

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RCACTMTY CONTROL SYST9AS 3/4.1.3 MOVABLE CONTROL ASSEMBUES GROUP HEIGHT UMITING CONDITION FOR OPERATION 3.1.3.1 All shutdown and control rods shall be OPERABLE and positioned within i 12 steps

of their group step counter demand position.

APPLICABILfTY: MODES 1" and 2".

ACTION:

a.

With one or more rods untrippable, determine within one hour that the SHUTDOWN l

MARGIN requirement of Specification 3.1.1.1 is satisfied 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 rod misaligned from the group step counter demand position by l

more than the above alignment requirements, determine within one hour that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , c.

With a maximum of one rod misaligned from the group step counter demand position l

j by more than the above alignment requirements, POWER OPERATION may continue provided that within one hour, either:

1. The rod is restored to OPERABLE status within the above alignment requirements, or

2. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisi:ed.

POWER OPERATION may then continue provided that; a) A reevaluation of each accident analysis of Table 3.11 is performed within 5 days. This reevaluation shall confirm that the previous analyzed results of these accidents remain valid for the duration of operation under these conditions, and For power levels below 50% of RATED THERMAL POWER, the position of each rod as determined by its individual rod position indicator may be more than i 12 steps from its group step counter demand position for a maximum of one hour in every 24. During this hour, the indicated position of each rod may be no more than i 24 steps from its demand position. The i 24 step / hour limit is not applicable when control rod position is known to be greater than 12 steps from the rod group step counter demand position indication.

See Special Test Exceptions 3.10.2 and 3.10.3.

NORTH ANNA, UNIT 2 3/4 1 16 Amendment NoAs4,160

i REACTIVITY CONTROL SYSTEMS ROD OROP TIME LIMITING CONDITION FOR OPERATION l

3.1.3.4 The individual full length (shutdown and control) rod drop time from the '229 STEP withdrawn position shall. be less than or e' qual to 2.7 seconds from l

beginning of decay of stationary gripper coil vcitage to dashpot entry with:

T,yg greater than or equal to 500*F, and a.

b.

All reactor coolant pumps operating.

APPLICA8ILITY:

MODES 1 and 2.

ACTION:

a.

With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined with 2 reactor coolant pumps operating, operation may proceed provided THERMAL

]

POWER is restricted to:

l 1.

Less than or equal to 66% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are open, or 2.

Less than or equal to 71% of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are closed.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head, b.

For specifically affected individual rods following any main-tenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and i

c.

At least once per 18 months.

NORTH ANNA - UNIT 2 3/4 1-21 Amendment' No. N' 133

ELEACTMTY CONTROL SYST9AS SHUTDOWN ROD INSERTION UMIT l

UMrTING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be limited in physical insertion as specified in the CORE OPERATING UMITS REPORT.

APPLICABILITY: MODES 1* and 2'#.

ACTX)N-

a. With a maximum of one shutdown rod inserted beyond the insertion limit specified in l

the CORE OPERATING UMITS REPORT, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

1. Restore the rod to within the insertion limit specified in the CORE OPERATING l

LIMITS REPORT, or

2. Declare the rod to be misaligned and apply Specification 3.1.3.1 l

b. With a maximum of one shutdown bank inserted beyond the insertion limit specified in the CORE OPERATING LIMITS REPORT 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 l

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. 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 , and l

6. the shutdown bank is restored to within the insertion limit specified in the CORE l

OPERATING LIMITS REPORT 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 .

1 See Special Test Exceptions 3.10.2 and 3.10.3.

With Keff greater than or equal to 1.0 1

NORTH ANNA UNIT 2 3/4 1 22 Amendment No.-4M, -440,160 l

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be within the insertion limit specified in the J

CORE OPERATING UMITS REPORT

a. Within 15 minutes prior to initial control rod bank withdrawal 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.

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NORTH ANNA UNIT 2 3/4 122a Amendment No.160 l

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REACTMTY CONTROL SYSTEMS CONTROL ROD INRERTlON UMrTS UMmNG CONDmON FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified in the CORE OPERATING UMITS REPORT.

APPLICABILITY: MODES 1* and 2*#,

ACTION.

a. With the control banks inserted beyond the insertion limits, except for surveillance l

testing pursuant to Specification 4.1.3.1.2, either:

1. Restore the control banks to within the insertion limits within two hours, or l

l

2. Reduce THERMAL POWER within two hours to less than or equal to that fraction of

.l RATED THERMAL POWER which is allowed by the rod group step counter demand position using the insertion limits specified in the CORE OPERATING LIMITS REPORT, or

3. L iin HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i

b. With a maximum of one control bank inserted beyond the insertion limit specified in the CORE OPERATING LIMITS REPORT 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 control 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 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, See Special Test Exceptions 3.10.2 and 3.10.3.

With Keff 21.0.

1. Provision for continued POWER OPERATION does not apply to Control Bank D inserted beyond the insertion limit.

NORTH ANNA UNIT 2 3/4 1 23 Amendment No.424. -440,160 i

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LIMITING CONDITION FOR OPERATION (cont'd.)

5. 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 , and

6. the control bank is restored to within the Insertion limit specified in the CORE OPERATING LIMITS REPORT 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 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 Umit Monitor is inoperable, then verify either the Individual rod positions (indicated positions) or the group step counter demand position of each rod group to be within the insertion limits at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

NORTH ANNA UNIT 2 3/4 123a Amendment No.160 l

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i NORTH ANNA UNIT 2 3/4 1 24 Amendment No.130,

i REACTMTY CONTROL SYSTEMS BASES (Continued)

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 of peaking factors or a restriction in THERMAL POWER: either of these restrictions provides assurance of fu61 rod integrity during continued operation in addition those accident analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation, Continuous monitoring of rod position with respect to insertion limits and rod deviation is provided by the rod insertion limit monitor and rod position deviation monitor, respectively.

OPERABILITY of the rod position deviation monitor is verified by a functional test at least once per 7 days and by comparison of the indicated positions versus the respective demand position indicators at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If the rod position deviation monitor or the rod insertion limit monitor is inoperable, the frequency of manual comparison of indicated rod (or bank) position is increased to an interval of at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , in the event that a malfunction of the Rod Control System renders control rods immovable, provision is made for continued operation provided:

the affected control rods remain trippable, and the individual control rod alignment limits are met, 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:

the affected control rod banks remain trippable, the individual control rod alignment limits are met, a rnaximum of one control or shutdown bank is inserted no more than 18 steps below e

the insertion limit, and the SHUTDOWN MARGIN requirements are verified every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during the period a

the insertion limit is not met.

Control Bank D is excluded from the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provision since insertion of D Bank below the insertion limit is not required for control rod assembly surveillance testing.

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 11 transients ( moderate frequency transients analyzed in Section 15.2 of the UFSAR) or in a violation of the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 during the repair period.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 til or IV) accident or transient condition occurring concurrently with the insertion limit violation.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with Tavo 2 500'F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times 1

experienced during a reactor trip at operating conditions.

NORTH ANNA UNIT 2 B 3/4 14a Amendment NoAM,160 l

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ML20064C218

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