Text

Amends 206 & 187 to Licenses NPF-4 & NPF-7,respectively, Addressing Only Proposed Changes to Intermediate Range Trip Setpoints & Allowable Values
	ML20149L176
Person / Time
Site:	North Anna
Issue date:	07/30/1997
From:	Edison G; NRC (Affiliation Not Assigned)
To:	;
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ML20149L179	List: ML20149L176; ML20149L184;
References
	NUDOCS 9707310173
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pS Ctg 1

UNITED STATES f

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2056H001

\\ *****/

VIRGINIA ELECTRIC AND POWER COMPANY DOCKEi NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 206 License No. NPF-4 4

1.

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

A.

The application for amendment by Virginia Electric and Power Company, (the licensee) dated November 9,1987, as supplemented by letters dated March 31, 1988, June 8, 1992, and February 4, 1997, 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; i

l B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and l

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.

9707310173 970730 PDR ADOCK 05000338 P

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, 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 206, 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 and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Gordon E. Edison, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 30,1997 i

. _ - ~. _ -.. --

c.

i ATTACHMENT TO LICENSE AMENDMENT N0. 206 TO FACILITY OPERATING LICENSE N0. NPF-4 DOCKET NO.50-33E 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. lines indicating the area of change.

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

Remove Paaes Insert Paaes-a 2-6 2-6 B 2-4 8 2-4 3/4 3-2 3/4 3-2 j

3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-12 3/4 3-12 3/4 3-14 3/4 3-14 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 4

Z

~

O

~

y TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS k

z FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES l.

Manual Reactor Trip Not Applicable Not Applicable C

2.

Power Range, Neutron Flux Low Setpoint -s 25% of RATED Low Setpoint - s 26% of RATED THERMAL POWER THERMAL POWER High Setpoint - 5109%" of RATED High Setpoint - s 110%*** of RATED THERMAL POWER THERMAL POWER i

3.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER s5.5% of RATEDTHERMALPOWER High Positive Rate with a time constant 2 2 seconds with a time constant 2 2 seconds i

4.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER s5.5% of RATEDTHERMALPOWER 3

High Negative Rate with a tirre constant 2 2 seconds with a time constant 2 2 seconds 5.

Intermediate Range, Neutron 5 35% of RATED THERMAL POWER s 40% of RATED THERMAL POWER l

y Flux 5

5 6.

Source Range, Neutron Flux s 10 counts per second s 1.3 x 10 counts per second 7.

Overtemperature AT See Note I See Note 3 8.

Overpower AT See Note 2 See Note 3 9.

Pressurizer Pressure-Low 21870 psig 21860 psig I

f 10.

Pressurizer Pressure-High s 2360 psig s 2370 psig E.

I 1.

Pressurizer Water Level-High s 92% ofinstrument span s 93% ofinstrument span p,

12.

Loss of Flow 2 90% of design flow per loop

2 89% of design flow per loop

o 0}

Design flow per loop is one-third of the minimum allowable Reactor Coolant System Total Flow Rate as specified in Table 3.2-1.

k The high trip setpoint for Power Range, Neutron Flux, shall be s 103% RATED THERM 4L POWER for the period of operation

{

until steam generator replacement.

- - The allowable value for the high trip setpoint for Power Range, Neutron Flux, is required to be s 104% RATED THERMAL POWER for the period of operation until steam generator replacement.

2.2 LIMITING SAFETY SYSTEM SETTINGS BASES i

2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the values at which the Reactor Trips are set for each parameter. The Trip Setpoints have been selected to ensure that the reactor core and reactor coolant system are prevented from exceeding their safety limits. Opera-tion with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that each Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

,e Manual Reactor Trip The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and provides manual reactor trip i

capability.

Power Range, Neutron ' lux F

The Power Range Neutron Flux channel high setpoint provides reactor core protection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry. The low set point provides redundant protection in the power range for a power excursion beginning from low power. The trip associated with the low setpoint may be manually bypassed when P-10 is active (two of the four power range channels indicate a power level of above approximately 10 percentofRATEDTHERMALPOWER).

PowerRange,NcqtronFlux,HighRates The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of rod ejection events from any power level. Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from partial power.

e I

NORTH ANNA-UNIT 1

.B 2-3

..~....._

b

LIMITING SAFETY SYSTEM SETTINGS BASES The Power Range Negative Rate Trip provides protection for control rod drop accidents.

At high power, a rod drop accident could cause local flux peaking which could cause an unconservative local DNBR to exist. The Power Range Negative Rate Trip will prevent this from occurring by tripping the reactor. No credit is taken for operation of the Power Range Negative Rate Trip for those control rod drop accidents for which the DN' BR's will be greater than the applicable design limit DNBR value for each fuel type.

htermediate and Source Ranne. Nuclear Flux The Source Range Nuclear Flux trip provides reactor core protection during shutdown

[

(Modes 3,4 and 5) when the reactor trip system breakers are in the closed position. The Source and Intermediate Range trips in addition to the Power Range trips provide core protection during reactor stanup (Mode 2). Reactor startup is prohibited unless the Source, Intermediate and Power Range trips are operable in accordance with Specification 3.3.1.1. The Source Range Channels will initiate a reactor trip at about 10d counts per second unless manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unless manually

[

blocked when P-10 becomes active. In the accident analyses, bounding transient results are based on reactivity excursions from an initially critical condition, where the source range trip is assumed to be blocked. Accidents initiated from a suberitical condition would produce less severe results since the source range trip would provide core protection at a lower power level. No credit was taken for operation of the trip associated with the Intermediate Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemocrature AT The Ovenemperature AT trip provides core protection to prevent DNB for all combinations i

of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transient delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat c,apacity of water with temperature and dynamic compensation for piping delays from the core to the loop temperature detectors. With normal axid power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

i i

NORTH ANNA - UNIT 1 B 2-4 Amendment No. 84, 206 j

_ _ ~. - _ _

. z:O

-I TABLE 3.3-1 bz REACTOR TRIP SYSTEM INSTRUMENTATION z

Y MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE q

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACrlON

1. Manual Reactor Trip 2

1 2

1,2 and

12

2. Power Range, Neutron Flux 4

2 3

1, 2 2'

i

3. Power Range, Neutron Flux 4

2 3

1, 2 2'

High Positive Rate

4. Power Range, Neutron Flux, 4

2 3

1, 2 2'

y High Negative Rate

5. Intermediate Range, Neutron Flux 2

1 2

l , 2 3

l

6. Source Range, Neutron Flux A. Startup 2

1 2

2"'

4 B. Shutdown 2

1 2

3*,4* and 5*

15 C. Shutdown 2

0 1

3,4 and 5 5

7. Overtemperature AT E

Three Loop Operation 3

2 2

1, 2 7'

R

[

Two Loop Operation 3

.1 *

2 1, 2 9

?3

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a cn

._.._.m_

_____m

TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive systern capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

With tL9 Reactor Trip Breaker open for surveillance teisting in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

High voltage to detector may be de-energized above the P-6.

Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

l ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is operable.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within I hour.

I

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the redundant channel (s) per Specification 4.3.1.1.1.

c. Either, THERMAL POWER is restricted to s 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the moveable incore detectors to i

confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

NORTH ANNA - UNIT 1 3/43-5 Amendment No. 81, 206

j, TABLE 3.3 1 (ContinEd)

J 4

)

Below P-6, restore the inoperable channel to OPERABLE status pnor to j

4 a.

j increasing THERMAL POWER above the P-6 Setpoint.

l

b. Above P-6 but below the P-10 setpoint, restore the inoperable channel to f

OPERABLE status prior to increasing THERMAL POWER above the P-10

{

setpoint.

j

c. Above the P-10 setpoint, POWER OPERATION may continued.

ACTION 4 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

j

a. Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above P-6, operation may continue.

ACTION 5 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the i

SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

l ACTION 6 -

Not applicable.

ACTION 7 -

With the number of OPERABLE channels one less than the Total Number of i

j Charmels, STARTUP and POWER OPERATION may proceed until j

performance of the next required CHANNEL FUNCTIONAL TEST provided j

the inoperable channel is placed in the tripped condition within I hour. '

j ACTION 8 -

Not applicable.-

i i

4 j

J I

l NORTH ANNA - UNIT 1 3/43-6 Amendment No. 206 2

2-O M

TABLE 4.3-1 g

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS b2 CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE c:

FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED Z

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1. Manual ReactorTrip N.A.

N.A.

fi R)

I,2 and *

2. Power Range, Neutron Flux S

D(2), M(3)

M I, 2 and Q(6) l

3. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 High Positive Rate y

4. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 High Negative Rate

5. Intermediate Range, Neutron Flux a.

S R(6.12)

M, S/U(I) 1***,2 b.

Mil 1)

N.A.

3*,4*,5*

6. Source Range, Neutron Flux N.A.

R(6)

M, S/U(I) 2,'3,4 and 5 l

7. Overtemperature AT S

R(6)

M 1, 2

[

8. Overpower AT S

R(6)

M 1, 2

9. Pressurizer Pressure-Low S

R M

1, 2 L

m e-

10. Pressurizer Pressure-High S

R M

I, 2 R

a z

11. Pressurizer Water Level-High S

R M

1, 2 I

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12. Loss of Flow -Single Loop S

R M

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TABLE 4.3-1 (Continued)

NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

l (1)-

If not performed in previous 7 days.

(2)-

Heat balance only, above 15% of RATED THERMAL POWER.

(3)-

Compare incore to excore axial offset above 15% of RATED THERMAL POWER.

Adjust channel if absolute difference 2 3 pe.ent.

(4)-

Manual ESF functional input check every 18 months.

(5)-

Each train or logic channel shall be testcd at least every 62 days on a STAGGERED TEST B ASIS.

(6) -

Neutron detectors may be excluded som CHANNEL CALIBRATION.

(7)-

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the manual reactor trip function. The test shall also verify the operability of the Bypass Breaker Trip circuit (s).

(8) -

Local manual shunt trip prior to placing the bypass breaker into service.

(9)-

Automatic undervoltage trip.

(10)-

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(11)-

Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that l

Permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(12)-

Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 1 3/4 3-14.

Amendment No. 81, 206

~

SPECIAL TEST EXCE' PTIONS l

PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.4,3.1.3.1,3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

The THERMAL POWER does not exceed 5%'of RATED THERMAL POWER, a.

b.

The reactor trip setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERMAL POWER, and The reactor trip setpoints on the OPERABLE Power Range Channels are set at less c.

than or equal to 25% of RATED THERMAL POWER.

APPLICABILITY:

MODE 2.

ACTION:

With the THERMAL POWER > 5% of RATED THERMAL POWER, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be 5 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNE'L FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PHYSICS TESTS.

NORTH ANNA - UNIT 1 3/4 10-3 Amendment No. M, 206

SPECIAL TEST EXCEPTIONS l

REACTOR COOLANT LOOPS I

LIMITING CONDITION FOR OPERATION t

l 3.10.4 The limitations of Specification 3.4.1.1 may be suspended dt ring the performance of startup and PHYSICS TESTS provided:

The THERMAL POWER does not exceed the P-7 Interlock Setpoint, 1

a.

b.

The Reactor Trip Setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERMAL POWER, and The Reactor Trip Setpoints on the OPERABLE Power Range Channels are set at c.

less than or caual to 25% of RATED THERMAL POWER.

APPLICABILITY:

During operation below tb: P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactoi *. rip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a i

CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating startup or PHYSICS TESTS.

NORTH ANNA - UNIT 1 3/4 10-4 Amendment No. 206

, ' f*

g t

UNITED STATES g

j NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D.C. 2066M201 o

- - - - s VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-339 1

l l

NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT T0 FACILITY OPERATING LICENSE j

Amendment No.187 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, (the licensee) dated November 9, 1987, as supplemented by letters dated March 31, 1988, June 8, 1992, and February 4, 1997, 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; j

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.

, 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 187, 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 and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Gordon E. Edison, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 30,1997 l

l l

ATTACHMENT TO LICENSE AMENDMENT N0.187 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET N0. 50-339 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 lines indicating the area of change.

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

Remove Paaes Insert Paaes 2-6 2-6 B 2-4 8 2-4 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-12 3/4 3-12 3/4 3-14 3/4 3-14 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 l

.y O

ac TABLE 2.2-I REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FLINCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 1.

Manual ReactorTrip Fot Applicable Not Applicable acZ' 2.

Power Range, Neutron Flux Low Setpoint -s 25% of RATED Low Setpoint -s 26% of RATED h

THERMAL POWER THERMAL POWER High Setpoint -s 109% of RATED High Setpoint -5110% of RATED THERMAL POWER THERMAL POWER 3.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER s5.5% of RATEDTHERMAL POWER High Positive Rate with a time constant 2 2 seconds with a time constant 2 2 seconds 4.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER s5.5% of RATEDTHERMAL POWER High Negative Rate with a time constant 2 2 seconds with a time constant 2 2 seconds 5.

Intermediate Range, Neutron s 35% of RATED THERMAL POWER s 40% of RATED THERMAL POWER l

y 6

Flux 5

5 6.

Source Range, Neutron Flux s 10 counts per second s 1.3 x 10 counts per second 7.

Overtemperature AT See Note i See Note 3 8.

Overpower AT See Note 2 See Note 3 9.

Pressurizer Pressure-Low 21870 psig 21860 psig 10.

Pressurizer Pressure-High s 2360 psig s 2370 psig i 1.

Pressurizer Water Level-High s 92% ofinstrument span s 93% ofinstrument span k

12.

Loss of Flow 2 90% of design flow per loop

2 89% of design flow per loop

o R

y Design flow per loop is one-third of the minimum allowable Reactor Coolant System Total Flow Rate as specified in Table 3.2-1.

I h

)

2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the values at which the Reactor Trips are set for each parameter. The Trip Setpoints j

have been selected to ensure that the reactor core and reactor coolant system are prevented from exceeding their safety limits. Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Yalue is acceptable on the basis that the difference between Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

l Manual Reactor Trip i

The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and provides manual reactor trip capability.

Power Range, Neutron Flux The Power Range, Neutron Flux channel high retpoint provides reactor core tprotection.againstreactivityexcursionswhicharetoorapidtobeprotected by temperature and pressure protective circuitry. The low setpoint provides j

redundant protection in the power range for a power excursion beginning from j

low power. The trip associated with the low setpoint may be manually bypassed

.when P-10 is active (two of the four power range channels indicate a power level of above approximately 10 percent of RATED THERMAL POWER).

Power Range, Neutron Flux, High Rates The Power Range Positive Rate trip provides protection against rapid flux l

increases which are characteristic of rod ejection events from any power I

level. Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from partial power,

The Power Range Negative Rate Trip provides protection for control rod drop accidents. At high power, a rod drop accident could cause local flux peaking which could cause an unconservative local DNBR to exist. The Power Range Negative Rate Trip will prevent this from occurring by tripping the reactor. No credit is taken for operation of the Power Range Negative Rate Trip for those control rod drop accidents for which the DNBR's will be greater than the applicable design limit DNBR value for each fuel type.

NORTH ANNA - UNIT 2 B 2-3 Amendment No.71

LIMITING SAFETY SYSTEM SETTINGS BASES Intermediate and Source Ranne. Nuclear Flux i

The Source Range Nuclear Flux trip provides reactor core protection during shutdown

]

(Modes 3,4, and 5) when the reactor trip system breakers are in the closed position. The Source and Intermediate Range trips in addition to the Power Range trips provide core protection during reactor stanup (Mode 2). Reactor stanup is prohibited unless the Source, Intermediate and Power Range trips are operable in accordance with Specification 3.3.1.1. The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unless manually

[

blocked when P-10 becomes active. In the accident analyses, bounding transient results are based on reactivity excursions from an initially critical condition, where the source range trip is assumed to be blocked. Accidents initiated from a subcritical condition would produce less severe results since the source range trip would provide core protection at a lower power level. No credit was taken for operation of the trip associated with the Intermediate Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the. overall reliability of the Reactor Protection System.

Overtemocrature Delta T The Overtemperature Delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transient delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic compensation for piping delays from the core to the loop temperature detectors. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial p:aks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

Operation with a reactor coolant loop out of service below the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint and associated trip will prevent DNB during 2 loop operation exclusive of the Overtemperature Delta T setpoint. Two loop operation above the 3 loop P-8 setpoint is permissible after resetting the K, K and K inputs i

2 3

to the Overtemperature Delta T channels and raising the P-8 setpoint to its 2 loop value. In this mode of operation, the P-8 interlock and trip functions as a High Neutron Flux trip at the reduced powerlevel.

NORTH ANNA - UNIT 2 B 2-4 Amendment No. M,187 i

K O

h

z:

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION D

MINIMUM C

TOTAL NO.

CHANNELS CHANNELS APPLICABLE h

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual ReactorTUp 2

1 2

1,2 and

12

2. Power Range, Neutron Flux 4

2 3

1, 2 2"

3. Power Range, Neutron Flux High 4

2 3

1, 2 2'

Positive Rate

4. Power Range, Neutron Flux, High 4

2 3

1, 2 2'

y Negative Rate

5. Intermediate Range, Neutron Flux 2

1 2

I "'", 2 3

l

6. Source Range, Neutron Flux A. Startup 2

1 2

2

4 B. Shutdown 2

1 2

3*,4* and 5*

15 C. Shutdown 2

0 1

3,4 and 5 5

3. Overtemperature AT y

B

{

Three Loop Operation 3

2 7

1, 2 7'

B E

Two Loop Operation 3

1**

2 1, 2 9

TABLE 3.3-HCONTINUED)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the out of service i

Reactor Coolant Loop shall be placed in the tripped condition.

I With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

High voltage to detector may be de-energized above the P-6, (Block of Source Range Reactor Trip), setpoint.

Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

[

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirements, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within I hour.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the redundant channel (s) per Specification 4.3.1.1.1.

c. Either, THERMAL POWER is restricted to 5 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to s 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map,is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NORTH ANNA - UNIT 2 3/43-5 Amendment No. 69,187

TABLE 3.3-1 (CONTINUEDT ACTION 3 - -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6, (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below the P-10 setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-10 setpoint.

c. Above the P-10 setpoint, POWER OPERATION may continued.

ACTION 4 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below P-6, (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above P-6, (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN rc,,uirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6-Not applicable.

ACTION 7-With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 8 -

Not applicable.

NORTH ANNA - UNIT 2 3/43-6 Amendment No.187

.2 O

c TABLE 4.31 N

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE c:

FUNCTIONAL UNIT CliFzCK CALIBRATION TEST REOUIRED z}

1. Manual ReactorTrip N.A.

N.A.

R(8)

I,2 and *

2. Power Range, Neutron Flux S

D(2) M(3)

M 1, 2 and Q(6)

3. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 High Positive Rate

4. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 w

[

High Negative Rate 2.

5. Intermediate Range, Neutron Flux a.

S R(6,13)

M, S/U(3)

I***,2 b.

M(12)

N.A.

3*,4*,5*

6. Source Range, Neutron Flux S(7)

R(6)

M, S/U(I) 2, 3',4, 5 and *

7. Overtemperature AT S

R(6)

M 1, 2

8. Overpower AT S

R(6)

M 1, 2

9. Pressurizer Pressure -Low S

R M

I, 2 N

h 10 PressurizerPressure-High S

R M

1, 2 E

Q l 1. Pressurizer Water Level-High S

R M

1, 2

.o

.f

12. Loss of Flow -Single Loop S

R M

i e:

..n--

TABLE 4.3-1 (Continued) i

~

g REACTOR TRIP SYSTEM INSTRUMENTATION SUREVEILLANCE REQUIREMENTS 5

CHANNEL MODES IN WHICH R

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE R

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1

13. Loss of Flow - Two Loops S

R NA 1

14. Steam Generator Water Level -

S R

M 1, 2 Low-Low

15. Steam /Feedwater Flow Mismatch S

R M

1, 2 l

and Low Steam Generator Water Level

16. Undervoltage - Reactor Coolant NA R

M 1 *'

Pump Busses

17. Underfrequency - Reactor Coolant NA R

M 1

+

Pump Busses w

i

18. Turbine Trip A. Low Auto Stop Oil Pressure NA NA S/U(1)

NA w

g B. Turbine Stop Valve Closure NA NA S/U(1)

NA t

19. Safety injection Input from ESF NA NA M(4)" & (5) 1, 2

20. Reactor Coolant Pump Breaker NA NA R

1 Position Trip i

21. A. Reactor Trip Breaker NA NA M(5), (9), & (11) 1, 2, &

B. Reactor Trip Bypass Breaker NA NA M(5), (9), & R(10) 1, 2, & *

22. Automatic Trip Logic NA NA M(5) 1, 2, &

3 "o

==J

TABLE 43-1(CONTINUED) l NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

Surveillance requirements for the manual ESF functional test of the safety injection input to the reactor trip breakers is suspended for the duration of Cycle 9 operation.

~

Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

l (1)-

If not performed in previous 7 days.

(2)-

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference >2 percent.

(3)-

Compare incore to excore axial offset above 15% of RATED THERMAL POWER.

Recalibrate if absolute difference 2 3 percent.

(4)-

Manual ESF functional input check every 18 months.

(5)-

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6)-

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)-

Below the P-6, (Block of Source Range Reactor Trip) Setpoint.

- (8) -

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(9)-

Local manual shunt trip prior to placing the bypass breaker into service.

(10)-

Auto' atic undervoltage trip.

m (11)-

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12)-

Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(13)-

Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not npplicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 2 3/4 3-14 Amendment No. 4-50,187

,. J,'

SPECIAL TEST EXCEPTIONS PHYSICS TESTS 5

LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.4,3.1.1.5,3.1.3.1,3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

The THERMAL POWER does not exceed 5% of. RATED THERMAL POWER, a.

l b.

The reactor trip setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERMAL POWER, 1

The reactor trip setpoints on the OPERABLE Power Range Channels are set at less c.

j than or equal to 25% of RATED THERMAL POWER, and d.

The Reactor Coolant System lowest operating loop temperature (Tavg) is greater than j

or equal to 531 F.

APPLICABILITY: MODE 2.

ACTION:

With the THERMAL POWER greater than 5% of RATED THERMAL POWER, a.

immediately open the reactor trip breakers.

b.

With a Reactor Coolant System operating loop temperature (Tavs)less than 531 F, restore T,yg to within its limit within 15 minutes or be in at least HOT STANDBY

. within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.10.3.1 The. THERMAL POWER shall be determined to be less than or equal to 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS, 4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PHYSICS TESTS.

4.10.3.3 The Reactor Coolant System temperature (Tava) shall be determined to be greater than or equal to 531 F at least once per 30 minutes during PHYSICS TESTS.

NORTH ANNA - UNIT 2 3/4 10-3 Amendment No.187

Y

./.'

SPECIAL TEST EXCENIONS REACTOR COOLANT LOOPS

\\

LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of startup and PHYSICS TESTS provided:

The THERMAL POWER does not exceed the P-7 Interlock Setpoint, a.

b.

The reactor trip setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERMAL POWER, and The reactor trip setpoints on the OPERABLE Power Range Channels are set at less c.

than or equal to 25% of RATED THERMAL POWER.

APPLICABILITY: During operation below the P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating startup or PHYSICS TESTS.

NORTH ANNA - UNIT 2 3/4 10-4 Amendment No.187

-

ML20149L176

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