Text

Amends 157 & 161 to Licenses DPR-24 & DPR-27,respectively, Re Changes to TS to Ensure Reactor Safety & Provide for Automatic Initiation of Engineered Safety Features
	ML20077E991
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Site:	Point Beach
Issue date:	12/08/1994
From:	Hansen A; Office of Nuclear Reactor Regulation
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NUCLEAR REGULATORY COMMISSION j..

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-WISCONSIN ELECTRIC POWER COMPANY DOCKET NO 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.157 License No. DPR-24 1.

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

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 10, 1992, as supplemented on March 8, 1994, 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 b 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-24 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.157, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

9412130226 941208 PDR ADOCK 05000266 p

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-This license amendment is effective immediately upon issuance..The Technical Specifications are to be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Allen G. Hansen, Project' Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

-Changes to the Technical Specifications Date of issuance: December 8, 1994 9

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UNITED STATES g,.

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NUCLEAR REGULATORY COMMISSION 3(W1 ).

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WASHINGTON, D.C. 20666-0001 p..o f WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.161 License No. DPR-27 1.

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

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 10, 1992, as supplemented on March 8, 1994, 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; 8.

The facil.ity 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-27 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.161, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

A

,. 3.

This. license amendment is effective immediately upon issuance.

The Technical Specifications are to be implemented within 90 days.from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION-Allen G. Hansen, Project. Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: December 8, 1994 l

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ATTACHMENT TO LICENSE AMENDMENT NOS.157 AND 161 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

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

REMOVE INSERT TS 15.1-5 TS 15.1-5 TS 15.1-6 TS 15.1-6 TS 15.3.5-1 TS 15.3.5-1 Table 15.3.5-2 (2 pages)

Table 15.3.5-2 (3 pages)

Table 15.3.5-3 (2 pages)

Table 15.3.5-4 (1 page)

Table 15.3.5-5 (2 pages)

Table 15.3.5-5 (4 pages)

Table 15.4.1-1 (5 pages)

Table 15.4.1-1 (6 pages)

Table 15.4.1-2 (4 pages)

Table 15.4.1-2 (4 pages) j

'f a

1.

Reactor Critical The reactor is said to be critical when the neutron chain reaction is self-sustaining and k,,, = ].0.

m.

Low Power Operation The reactor is in the low-power operating condition when the reactor is critical and the average neutron flux of the power range instrumentation indicates less than or equal to 2% of rated power.

n.

Fire Suporession Water System A FIRE SUPPRESSION WATER SYSTEM shall consist of: a water source; pump (s);

and distribution piping with associated sectionalizing control or isolation valves.

Such valves shall include yard post indicating valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser.

Unit 1 - Amendment No. J2,32,157 15.1-5 Unit 2 - Amendment No. 76,3E,161

o.

Egig_Eauivalent I-131 l

~

Dose Equivalent I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Fr.ctors for Power and Test Reactor Sites."

l p.

E - Averaae Disintearation Enerav l

E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor couiant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

Unit 1 - Amendment No. 71,157 15.1-6 Unit 2 - Amendment No. 76,161 l

h 15.3.5 INSTRUMENTATION SYSTEM Ooerational Safety Instrumentation Acolicability: Applies to plant instrumentation systems.

Ob.iectives: To provide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are exceeded, and te delineate the conditions of the plant instrumentation and safety circuits 1 necessary to ensure reactor safety.

Specification:

A.

The Engineered Safety Features initiation instrumentation setting limits shall be as stated in Table 15.3.5-1.

B.

For on-line testing or in the event of a sub-system instrumentation channel failure, plant operation at rated power shall be permitted to continue in accordance with Tables 15.3.5-2 through 15.3.5-4.

C.

In the event the number of channels of a particular sub-system in service falls below the limits given in the column entitled Minimum Operable Channels, operation shall be limited according to the requirement shown in Tables 15.3.5-2 through 15.3.5-4, Operator Action when minimum operable channels unavailable.

D.

The post-accident monitoring instrumentation channels in Table 15.3.5-5 shall be operable.

In the event the number of channels in a particular sub-system falls below the minimum number of operable channels given in Column 2, operation and subsequent operator action shall be in accordance with Column 3.

This specification is not applicable in the cold or refueling shutdown conditions.

Basis:

Instrumentation has been provided to sense accident conditions and to initiate operation of the Engineered Safety Features (l).

Unit 1 - Amendment No.33,92,157 15.3.5-1 Unit 2 - Amendment No.60,96,161

TABLE 15.3.5-2 INSTRUMENT CONDITIONS FOR REACTOR TRIP 1

2 3

4 TOTAL NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET 1.

Manual 2

1 1

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.

Nuclear Power Range 3 **

2 of 4 power Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6

a.

low setting 4

2 range channels greater than 10%

full power (low setting only) 3 **

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0

b.

high setting 4

2 3.

Nuclear Flux Intermediate Range 2

1 1

2 of 4 power Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

range channels greater than 10%

full power 4

Nuclear Flux Source 2

1 1

1 of 2 intermediate Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

Range range channels greater than 10" amps.

5.

Overtemperature Delta T 4

2 3**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6.

Overpower Delta T 4

2 3**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 7.

Low Pressurizer Pressure 4

2 3**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8.

Hi Pressurizer Pressure 3

2 2**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Unit 1 - Amendment No.45,JJ2,157 Page 1 of 3 Unit 2 - Amendment No.50,JJ5,161

TABLE 15.3.5-2(continued) 1 2

3 4

TOTAL NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS-N0.

FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET 9.

Hi Pressurizer 3

2 2"

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Water Level i

10. Low Reactor Coolant System Flow a.

Low Flow in One Loop 3/ loop 2/ loop 2/ loop **

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

(>50% full power)

(any loop) b.

Low Flow in Both loops 3/ loop 2/ loop 2/ loop **

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (10-50% full power)

(both loops) 11.

Turbine Trips a.

Turbine Autostop 3

2 2**

Be <50% of rated power Oil Pressure within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months b.

Turbine Stop Valve 2

2 2**

Be <50% of rated power Position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 12.

Steam Flow-Feedwater 2/ loop 1/ loop 1/ loop Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Flow Mismatch 13.

Lo Lo Steam Generator 3/ loop 2/ loop 2/ loop **

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Water Level (input to reactor trip) 14.

4KV Bus (A01 and A02) a.

Undervoltage (input 2/each 1/each 1/each Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to reactor trip) bus bus bus b.

Underfrequency 2/each 1/each-1/each

.Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months bus bus bus Unit 1 - Amendment No.JE,55,JJZ,157.

Page 2 of 3 Unit 2 - Amendment No.50,60,JJ5,161

.6 TABLE 15.3.5-2(continued) 1 2

3 4

TOTAL NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET 15.

Safety Injection See Table 1

See Table Be in hot shutdown.in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months **

15.3.5-3 15.3.5-3 16.

RCP Breaker Open Position a.

(>50% full power) 2 1

2 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months b.

(10 - 50% full power) 2 2

2 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 17.

Reactor Trip Breakers 2

1 2

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months One additional channel may be taken out of service for low power physics testing.

When block condition exists, maintain normal operation.

o If a channel is determined to be inoperable, resulting in one less than the total number of channels being operable, oo power operation may continue if the following conditions are met:

1.

The minimum number of operable channels is still satisfied.

2.

The affected channel is placed in trip within I hour.

If minimum conditions are not met within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching hot shutdown, the unit shall be in cold shutdown within ooo c

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of the event causing the unit shutdown.

When at power, one channel may be bypassed for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months provided that the other channel is operable. When the oooo plant is shutdown and rod withdrawal is possible, restore the inoperable channel to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip Breakers within I hour.

l l

Unit 1 - Amendment No.157 Page 3 of 3 l

Unit 2 - Amendment No.161

o-9 j

TABLE 15.3.5-3 1

ENGINEERED SAFETY FEATURES 1

2 3

4 NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS

[J0 FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET 4

m 1.

SAFETY INJECTION a.

Manual 2

1 1

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b.

Hi Containment Pressure 3

2 2**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c.

Steam Generator low Steam Pressure / Loop 3

2 2

Primary pressure Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *

<1800 psig d.

Low Pressurizer Pressure 3

2 2**

Primary pressure Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *

<1800 psig 2.

CONTAINMENT SPRAY t

a.

Manual"**

2 2

2 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b.

Hi-Hi Containment Pressure (Containment Spray) 2 sets 2 of 3 2 pe,r Be in ho;~ shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

of 3 in each set set 3.

AUXILIARY FEEDWATER i

a.

Start Motor-Driven Pumps i.

Low Low Steam Gen.

Water Level 3/SG 2/either 2/SG**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ' SG ii.

SI signal SI Initiating Conditions as in Item 1 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

l l

Unit 1 - Amendment No. 38, A7,55,JJS,157 Page 1 of 2' Unit 2 - Amendment No. 50,52,60,J22,161

TABLE 15.3.5-3 (continued)

ENGINEERED SAFETY FEATURES 1

2 3

4

- a NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET b.

Start Turbine-Driven Pump i.

Undervoltage on 4KV Buses (A01 & A02) 2/each 1/each 1/each Be in hot shutdown'in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

bus bus bus 11.

Low Low Steam Gen.

Water Level 3/SG 2/each 2/SG**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

SG 4.

SAFETY-RELATED ELECTRICAL LOADS a.

4.16KV Buses (A05, A06) i.

Degraded Voltage 3/ bus 2/ bus 2/ bus **

ii.

Loss of Voltage 2/ bus 1/ bus I/ bus b.

480V Buses (803, 804) i.

Loss of Voltage 3/ bus 2/ bus 2/ bus **

'Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

t If minimum conditions are not met within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching hot shutdown, the unit shall be in cold shutdown within l

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of the. event causing the unit shutdown.

If a channel is determined to be inoperable, resulting in one less than the total number of channels being operable, power operation may continue if the following conditions are met:

1.

The minimum number of operable channels is still. satisfied.

2.

The affected channel is placed in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Declare the associated emergency diesel generator inoperable for the affected bus.

The applicable Limiting Condition for Operation (LCO) shall be entered.

Separate LCOs may be entered for the Degraded Voltage and Loss of Voltage functions.

Both switches must be activated simultaneously.

Unit 1 - Amendment No. 38,47,55,J37,157 Page 2 of 2

-Unit 2 - Amendment No. 50,52,60,JAJ,161 Correction letter of 5-6-93

i TABLE 15.3.5-4 INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS' 1

2 3

4 TOTAL NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTIONS IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET 1.

CONTAINMENT ISOLATION a.

Safety Injection See Items Ib, c, and d of Table 15.3.5-3 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b.

Manual 2

1 1

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.

STEAM LINE ISOLATION a.

Hi Hi Steam Flow with 2/ loop 1/either 1/ loop-Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

loop Safety Injection See Items Ib, c, and d of Table 15.3.5-3 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , b.

Hi Steam Flow and 2/ loop 1/either 1/ loop Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

loop tow Tavg with 4

2 3**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

Safety Injection See Items Ib, c, and d of Table 15.3.5-3 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ' c.

Hi Containment Pressure 3

2 2*

Be.in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d.

Manual 1/ loop 1/ loop 1/ loop Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.

FEEDWATER ISOLATION a.

Hi Steam Generator Water Level 3/SG 2/SG 2/SG**

Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

b.

Safety Injection See Item 1 of Table 15.3.5-3 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

If minimum conditions are not met within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , steps shall be taken on the affected unit to place the unit in cold c

shutdown conditions.

If a channel is determined to be inoperable, resulting in one less than the total number of channels being. operable, i.

power operation may continue if the following conditions are met:

1.

The minimum number of operable channels is still satisfied.

2.

The affected channel is placed in trip within I hour.

l Unit 1 - Amendment No. A5,157 Page 1 of 1 i

Unit 2 - Amendment No. 50,161

TABLE 15.3.5-5 INSTRUMENT OPERATING CONDIT10NS FOR POST ACCIDENT MONITORING VNSTRUMENTATION 1

2 3

TOTAL MINIMUM NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNEL _S CHANNELS OF COLUMN 2 CANNOT BE MET 1.

PORV Position Indicator 1/ Valve 1/ Valve If the operability of the PORV position indicator cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , shut the associated PORV Block Valve.

2.

PORV Block Valve Position Indicator 1/ Valve 1/ Valve If the operability of the PORV Block Valve Position Indicator cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , shut and verify the Block Valve shut by direct observation or declare the Block Valve inoperable.

3.

Safety Valve Position Indicator 2/ Valve 1/ Valve If the operability of at least one of the Safety Valve Position Indicators cannot be restored within seven days, be in at least hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.

Reactor Coolant System Subcooling 2

1 If operability of at least one subcooling monitor cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

5.

AFW Pump Discharge Flowrate 3

If the minimum number of AFW Pump Discharge Flowrate channels required to provide indication of AFW flow to both steam generators cannot be restored to an operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

The minimum number of operable channels for AFW Pump Discharge Flowrate is the number of AFW Pump Discharge Flowrate channels, in conjunction with the aumber of operable AFW to Steam Generator Flowrate channels, required to provide indication of AFW flow to both steam generators.

NOTE:

The channel requirements in this table refer only to that portion of the instrument channel required for post accident monitoring. The applicable channels are listed in FSAR Table 7.7-2.

Unit 1 - Amendment No. 92,JJ2,157 Page 1 of 4

}'

Unit 2 - Amendment No. 96,JJE,161

TABLE 15.3.5-5 (continued) 1 2

3 TOTAL MINIMUM NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNELS CHANNELS OF COLUMN 2 CANNOT BE MET 6.

AFW to Steam Generator Flowrate 2

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

7.

Containment High Range Radiation 3

2 If the operability cannot be restored within seven days after failure, prepare a special report to be submitted within thirty days in accordance with 15.6.9.2.D.

8.

Containment Sump Level (Sump A) 2 1

Operation may continue up to thirty days.

If operability cannot be restored, be in hot shutdown within the next twelve hours.

9.

Containment Sump Level (Sump B) 2 1

If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

10.

Containment Hydrogen Concentration 2,

1 If operability cannot be restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in hot shutdown within the next six hours.

11.

Reactor Vessel Wide Range Level 2

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

12.

Reactor Vessel Narrow Range Level 2

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

With only one hydrogen monitor operable, restore an inoperable monitor with an independent power supply to an OPERABLE status within 30 days or be in hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE:

The channel requirements in this table refer only to that portion of the instrument channel required for post accident monitoring.

The applicable channels are listed in FSAR Table 7.7-2.

Unit 1 - Amendment No.157 Page 2 of 4 Unit 2 - Amendment No.161

]

TABLE 15.3.5-5 (continued) 1-2 3

TOTAL MINIMUM NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS

~ NO.

-FUNCTIONAL UNIT CHANNELS CHANNELS OF COLUMN 2 CANNOT BE MET 13.

In-Core Thermocouples 39 2/ core If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , installed quadrant be in hot shutdown within the next twelve tours.

per core j 14.

Main Steam Line Radiation 1/ steam 1/ steam If operability cannot be_ restored within seven days, prepare line line a special report to be submitted within thirty days in accordance with 15.6.9.2.E.

15.

Refueling Water Storage 2

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot Tank Level shutdown within the next twelve hours.

16.

RCS Wide Range Pressure 3

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

17.

RCS Narrow Range Pressure 4

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

Hot Leg Temperature 2/ loop 1/ loop f

18.

RCS Wide Range If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

19.

RCS Wide Range Cold Leg Temperature 2/ loop 1/ loop If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be-in hot shutdown within the next twelve hours.

20.

Pressurizer Level 4

I If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

NOTE: The channel requirements in this table refer only to that portion of the instrument channel required for post accident monitoring.

The applicable channels are listed in FSAR Table 7.7-2.

i Unit 1 - Amendnent No.157 Page 3 of 4 Unit 2 - Amendment No.161

TABLE 15.3.5-5 (Continued) 1 2

3 TOTAL MINIMUM NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS NO.

FUNCTIONAL UNIT CHANNELS CHANNELS OF COLUMN 2 CANNOT BE MET 21.

Containment Wide Range Pressure 2

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot shutdown within the next twelve hours.

22.

Containment Intermediate 3

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot Range Pressure shutdown within the next twelve hours.

23.

Containment low Range 3

1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot Pressure shutdown within the next twelve hours.

24.

Condensate Storage Tank 2/ tank 1/ tank If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot level shutdown within the next twelve hours.

25.

Steam Generator Wide 2/SG 1/SG If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot Range Level shutdown within the next twelve hours.

26.

Steam Generator Narrow 3/SG 1/SG If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot Range Level shutdown within the next twelve hours.

27.

Steam Generator Pressure 3/SG 1/SG If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in' hot shutdown within the next twelve hours.

28.

Containment Isolation 1

1 If the operability of the shut position indication of a Valve Position Indication containment isolation valve cannot be restored within seven days, close the valve or be in hot shutdown within the next twelve hours.

NOTE:

The channel requirements in this table refer only to that portion of the instrument channel required for post accident monitoring. The applicable channels are listed in FSAR Table 7.7-2.

Unit 1 - Amendment No.157 Page 4 of 4 Unit 2 - Amendment No. 161

TABLE 15.4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS, AND TESTS OF INSTRUMENT CHANNELS PLANT CONDITIONS ~

NO.

CHANNEL DESCRIPTION CHECK CALIBRATE TEST-WHEN REOUIRED 1.

Nuclear Power Range R

ALL

-Heat Balance S(l)

D(1,19)

ALL

-Signal to delta T; bistable Q(1,2)

ALL actions (rod stops, trips)

-Compare results of the incore M(4,5,20)

PWR detector' measurements to NIS axial flux difference

-2.

Nuclear Intermediate Range R

ALL

-when not blocked S(l)

ALL

-logarithmic level; bistable action P

ALL (rod stop, trips) i 3.

Nuclear Source Range R

ALL

-when not blocked S-ALL

-Bistable action (alarm and P

ALL trips) 4.

Reactor Coolant Temperature S

R PWR,H0T S/D, COLD S/D

-0vertemperature delta T Q(1,2)

ALL

-0verpower' delta T Q(1,2)

ALL 5.

Reactor Coolant Flow S(l)

R ALL

-Analog and single loop loss-Q(1,2)

ALL of-flow logic testing

-Logic channel testing for R

ALL reactor trip on loss of reactor coolant flow in both loops 6.

Pressurizer Water Level S(l)-

R Q(1,2)

ALL 7.

Pressurizer Pressure S(l)

R Q(1,2)

ALL l

8.

Steam Generator Level S(l)

R Q(1,17)

ALL Unit 1 Amendment No. A3, A7.86 JJ6,J2J,JfD,157_

Page 1 of 6 Unit 2 - Amendment No.'AB,52,90,JJ9,J24,JAA,161

TABLE 15.4.1-1 (continued)

PLANT CONDITIONS

- NO.

CHANNEL DESCRIPTION CHECK CALIBRATE TEST WHEN REOUIRED-9.

Steam Generator Flow Mismatch S(22)

R Q(1)

ALL 10.

Steam Generator Pressure S(16)

R Q(1)

ALL 11, 4KV Bus Undervoltage (A01 & A02)

-AFW pump actuation R

M(1)

ALL

-Reactor Protection actuation R

M(1,2)

ALL 12.

4KV Bus Underfrequency (A01 & A02)

-to Reactor Coolant Pump trip R

ALL 13.

Safeguards Bus Voltage

-Loss of 4KV -

S R

M(1).

ALL

-Degraded 4KV 5

R M(1)

ALL

-Loss of 480V S

R M(1).

ALL 14.

120 Vac Instrument Buses W(6)

ALL 15.

Reactor Trip Signal From Turbine

-Turbine Autostop M(1)

ALL

-Turbine Stop Valve M(1)

ALL 16.

Reactor Trip Signal From SI M(1)

ALL 17.

Feedwater Isolation on SI

-MFP Trip on Safety Injection R

ALL

-MFRV Shutting on Safety Injection R

ALL-18.

Accumulator Level and Pressure S

R ALL

. 19.

Analog Rod Position S(8,22)

R ALL

-with step counters S(22)

ALL

-Monitoring by On-Line Computer (18)

PWR, HOT S/D t

Unit 1 - Amendment No.J5,80,92,97,JJ6,Jf0,157 Page 2 of 6 Unit 2 - Amendment No.2J,85,96,107,JJ9,JAA,161 4

TABLE 15.4.1-1 (continued)

PLANT CONDITIONS NO.

CHANNEL DESCRIPTION CHECK CALIBRATE TEST WHEN REQUIRED 20.

Auxiliary Feedwater Flowrate (13)

R ALL 21.

Boric Acid Control System R

ALL 22.

Boric Acid Tank Level D

R ALL 23.

Charging Flow R

ALL 24.

Condensate Storage Tank Level S(l)

R ALL 25.

Containment High Range Radiation S(l)

R(14)

M(1)

ALL 26.

Containment Hydrogen Monitor 0

ALL

-Gas Calibration Q(15)

ALL

-Electronic Calibration R

ALL 27.

Containment Pressure S

R Q(1,3,9)

ALL 28.

Containment Water Level M

R ALL 29.

Emergency Plan Radiation Survey Instruments Q

R Q

ALL 30.

Environmental Monier-s M

ALL 31.

In-Core Thermocouples M

R(14)

ALL 32.

Overpressure Mitigating System S(12)

R (IO)

ALL 33.

PORV Block Valve Position Indicator Q

R ALL 34.

PORV Operability R

Q(ll)

ALL 35.

PORV Position Indicator S(21)

R R

ALL Unit 1 - Amendment No. 38,47.35.59.JJ3,JAD,JEE,157 Page 3 of 6 Unit 2 - Amendment No.50,EE.60,6A.JJ6.JAA.JE9,161 i

I

TABLE 15.4.1-1 (continued)

PLANT CONDITIONS NO.

CHANNEL DESCRIPTION CHECK CALIBRATE TEST WHEN REQUIRED 36.

Radiation Monitoring System D(7)

R(7)

M(7)

ALL 37.

Reactor Vessel Fluid Level System M

R ALL 38.

Refueling Water Storage Tank Level R

ALL 39.

Residual Heat Removal Pump Flow R

ALL 40.

Safety Valve Position Indicator M

R ALL 41.

Subcooling Margia Monitor M

R ALL 42.

Turbine Overspeed Trips

-Independent Overspeed Protection System R

M(1)

ALL

-0verspeed Block trip R

M(1)

ALL 43.

Volume Control Tank Level R

ALL 44.

Reactor Protection System and M(1,23)

ALL Emergency Safety Feature Actuation System Logic 45.

Reactor Trip System Interlocks

-Intermediate Range Neutron Flux, P-6 R(24)

R ALL

-Power Range Neutron Flux, P-8 R(24)

R ALL

-Power Range Neutron Flux, P-9 R(24)

R ALL

-Power Range Neutron Flux, P-10 R(24)

R ALL

-1st Stage Turbine Impulse Pressure R(24)

R ALL Unit 1 - Amendment No. 38,47,$5,76,92,JJ3,JAD,JE3,157 Page 4 of 6 Unit 2 - Amendment No. 50,55,60,BD,96,JJ6,JAA.JE9,161 l

NOTATION USED IN IABLE_15.4.1-1 S-Each shift D-Daily W-Weekly Q-Quarterly M-Monthly P-Prior to reactor criticality if not performed during the previous week.

R-Each refueling interval (but not to exceed 18 months)

PWR-Power and Low Power Operation, as defined in Specifications 15.1.h. and 15.1.n.

HOT S/D-Hot Shutdown, as defined in Specification 15.1.g.l.

COLD S/D-Cold Shutdown, as defined in Specification 15.1.g.2.

REF S/D-Refueling Shutdown, as defined in Specification 15.1.g.3.

ALL-All conditions of operation, as defined in Specifications 15.1.g, h and n.

NOTES USED IN TABLE 15.4.1-1 (1)

Not required during periods of refueling shutdown, but must be performed prior to reactor criticality if it has not been performed during the previous surveillance period.

(2)

Tests of the low power trip bistable setpoints which cannet be done during power operations shall be conducted prior to reactor criticality if not done in the previous surveillance interval.

(3)

Perform test of the isolation valve signal.

(4)

Perform by means of the moveable incore detector system.

(5)

Recalibrate if the absolute difference is >3 percent.

(6)

Verification of proper breaker alignment and that the 120 Vac instrument buses are energized.

(7)

Radioactive Effluent Monitoring Instrumentation Surveillance Requirements are specified in Section 15.7.4.

(8)

Verify that the associated rod insertion limit is not being violated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months whenever the rod insertion limit alarm for a control bank is inoperable.

(9)

Test of Narrow Range Pressure, 3.0 psig, -3.0 psig excluded.

1 Unit 1 - Amendment No. If0,157 Page 5 of 6 Unit 2 - Amendment No. Jff,161

NOTES USED IN TABLE 15.4.1-1 (continued)

(10) When used for the Overpressure Hitigating System, each PORV shall be demonstrated operable by:

Performance of a channel functional test on the PORV actuation channel, but excluding valve operation, within 31 a.

days prior to entering a condition in which the PORV is required operable and at least once per 31 days thereafter when the PORV is required operable.

(11)

Performance of a channel functional test is required, excluding valve operation.

(12)

Shiftly check is required when the reactor coolant system is not open to the atmosphere and the reactor coolant system temperature is less than the minimum temperature for the in-service pressure test as specified in TS Figure 15.3.1-1.

(13) An AFW ' low path to each steam generator shall be demonstrated operable, following each cold shutdown of greater than 30 days, prior to entering power operation by verifying AFW flow to each steam generator.

(14) Calibration is to be a verification of response to a source.

(15)

Sample gas for calibration at 2% and 6%.

(16) A check of one pressure channel per steam generator is required whenever the steam generator could be pressurized.

(17)

Includes test of logic for reactor trip on low-low level, automatic actuation logic for auxiliary feedwater pumps, and test of logic for feedwater isolation on high steam generator level.

(18)

Rod positions must be logged at least once per hour, after a load change >10% or after >30 inches of control rod motion if the on-line computer is inoperable.

(19) The daily heat balance is a gain adjustment performed to match Nuclear Instrumentation System indicated power level with reactor thermal output.

(20)

To confirm that hot channel factor limits are being satisfied, the requirements of TS 15.3.10.B must be met.

(21)

Check required only when the overpressure mitigation system is in operation.

(22) Not required during period of cold and refueling shutdowns, but must be performed prior to reactor criticality if it has not been performed during the previous surveillance period.

(23)

Each train tested at least every 62 days on a staggered basis.

(24) Neutron detectors excluded from calibration.

Unit 1 - Amendment No.157 Page 6 of 6 Unit 2 - Amendment No.161

TABLE 15.4.1-2 MINIMUM FRE0VENCIES FOR E0VIPMENT AND SAMPLING TESTS Jn1 Freauency _

i 1.

Reactor Coolant Samples Gross Beta-gamma 5/ week (7) activity.

(excluding tritium)

Tritium activity.

Monthly Radiochemical E semiannually (2"

)

Determination Isotopic Analysis for Every two weeks (1)

Dose Equivalent I-131 Concentration i'

Isotopic Analysis for a.) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l

Iodine including I-131, whenever the specific I-133, and 1-135 activity exceeds 1.0yCi/

gram Dose Equivalent I-131 or 100/E pCi/ gram.'6) b.) One sample between l

2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a thermal power change exceeding 15% of rated power in a one-hour period.

Chloride Concentration 5/ week'8)

Diss. Oxygen Conc.

5/ week (6)

Fluoride Conc.

Weekly 2.

Reactor Coolant Boron Boron Concentration Twice/ week 3.

Refueling Water Storage Boron Concentration Weekly'6)

Tank Water Sample 4.

Boric Acid Tanks Boron Concentration Twice/ week 5.

Spray-Additive Tank Na0H Concentration Monthly 6.

Accumulator Boron Concentration Monthly 7.

Spent Fuel Pit a) Boron Concentration Monthly b) Water Level Weekly Verification Page 1 of 4 Unit 1 - Amendment No. 45,77,J06,123,157 Unit 2 - Amendment No. 33./p,709,777,161

TABLE 15.4.1-2 (Continued)

Ifit Frecuency 8.-

Secondary Coolant Gross Beta-gamma Weekly (')

Activity or gamma isotopic analysis Iodine concentration Weekly when~ gross Beta-gamma activity equals or-exceeds 1.2 #Ci/cc (6) 9.

Control Rods a) Rod drop times of all Each refueling or l

full length rods (3) after maintenance that could affect proper functioning.(')

b) Rodworth measurement Following each refueling shutdown prior to commencing power operation

10. Control Rod Partial movement of Every 2 weeks (ta)

(

all rods

11. Pressurizer Safety Valves Set point Every five years (")

12. Main steam Safety Valves Set Point Every five years (")

13. Containment Isolation Trip Functioning Each refueling shutdown

14. Refueling System Interlocks functioning Each refueling shutdown

15. Service Water System functioning Each refueling shutdown

16. Primary System Leakage Evaluate Monthly (6)

17. Diesel fuel Supply fuel inventory Daily

18. Turbine Stop and Governor Functioning Annually ")

Valves 19.

Low Pressure Turbi e Visual and magnetic Every five years RotorInspection(g) particle or liquid penetrant

20. Boric Acid System Storage Tank Daily Temperature

21. Boric Acid System Visual observation Daily of piping temperatures (all > 145 F) i Page 2 of 4 Unit 1 - Amendment No. 6A,65,71,83,J00.106,129,155,157 Unit 2 - Amendment No. pp,79,7%,87,Jp3,Jp9,J33,JE9,161

i TABLE 15.4.1-2 (Continued)

Int Frecuency 22.

Boric Acid Piping Heat Electrical circuit' Monthly Tracing operability 23.

PORV Block Valves

a. Complete Valve Cycle Quarterly "3)

b. Open position check Every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ""

24.

Integrity of Post Accident Evaluate Each refueling Recovery Systems Outside cycle Containment

+

25.

Containment Purge Supply Verify valves are Monthly ")

and Exhaust Isolation Valves locked closed 26.

Reactor Trip Breakers

a. Verify independent Monthly ")

operability of automatic shunt and undervoltage trip functions.

b. Verify independent Each refueling 4

operability of man-shutdown ual trip to shunt and undervoltage trip functions.

27.

Reactor Trip Bypass Breakers

a. Verify operability Prior to of the undervoltage breaker use trip function.

b. Verify operability Each refueling of the shunt trip shutdown functions.

c. Verify operability Each refueling of the manual trip shutdown l

l to undervoltage trip functions.

28.

120 VAC Vital Instr.

Verify Energized"2)

Shiftly Bus Power i

29.

Power Operated Relief Valves Operate ')

Each shutdown"5)

U (PORVs),

PORV Solenoid Air Control Valves, and Air System Check

30. Atmospheric Steam Dumps Complete valve cycle Quarterly 31.

Crossover Steam Dump System Verify operability of Quarterly each steam dump valve.

Pa e 3 of 4 Unit 1-AmendmentNo.6/,65,77,83,J00,f96,J29,J/B,J55,157 Unit 2 - Amendment No.69,70,76,B/,J03,109,J33,132,JE9,161 l

. -,, =.

O TABLE 15.4.1-2 (Continued) 32.

Pressurizer Heaters Verify that 100KW of Quarterly heaters are available.

33.

CVCS Charging Pumps Verify grability of Quarterly pumps.

34.

Potential Dilution in Verify operability of Prior to placing plant Progress Alarm alarm.

in cold shutdown.

(1) Required only during periods of power operation.

(2)

E determination will be started when the gross activity analysis of a filtered sample indicates 21GyCi/cc and will be redetermined if the primary coolant gross radioactivity of a filtered sample increases by more than 10yCi/cc.

(3) Drop test shall be conducted at rated reactor coolant flow.

Rods shall be dropped under both cold and hot condition, but cold drop tests need not be timed.

(4) Drop tests will be conducted in the hot condition for rods on which i

maintenance was performed.

(5) As accessible without disassembly of rotor.

(6) Not required during periods of refueling shutdown.

(7) At least once per week during periods of refueling shutdown.

(8) At least three times per week (with maximum time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months between samples) during periods of refueling shutdown.

(9) Not required during periods of cold or refueling shutdown, but must be performed prior to exceeding 200*F if it has not been performed during the previous surveillance period.

(10) Sample to be taken after a minimum of 2 EFPD and 20 days power operation since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

(11) An approximately equal numbc of valves shall be tested each refueling outage such that all valves will be tested within a five year period.

If any valve fails its tests, an additional number of valves equal to the number originally tested shall be tested.

If any of the additional tested valves fail, all remaining valves shall be tested.

(12) The specified buses shall be determined energized in the required manner at least once per shift by verifying correct static transfer switch alignment and indicated voltage on the buses.

(13) Not required if the block valve is shut to isolate a PORV that is inoperable for reasons other than excessive seat leakage.

(14) Only applicable when the overpressure mitigation system is in service.

(15) Required to be performed only if conditions will be established, as defined in Specification 15.3.15, where the PORVs are used for low temperature overpressure protection.

The test must be performed prior to establishing these conditions.

(16) Test valve operation in accordance with the inservice test requirements of the ASME Boiler and Pressure Vessel Code,Section XI.

(17) Operability of charging pumps is verified by ensuring that the pumps develop the required flowrate, as specified by the In-Service Test program.

(18) Not required to be performed if the reactor is subcritical.

Page 4 of 4 Unit 1 - Amendment No.10E.729,JfS,JEF,157 Unit 2 - Amendment No.JO9,133,JE2,JE9,161

ML20077E991

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