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Amend 222 to License DPR-70,allowing 1 Time Extension of TS Surveillance Interval to End of Fuel Cycle 13 for Certain Srs.Amend Extends Surveillance Intervals in SR 4.3.2.1.3 for Instrumentation Response Time & Sequence Testing of ESFAS
	ML20206H256
Person / Time
Site:	Salem
Issue date:	05/04/1999
From:	Clifford J; NRC (Affiliation Not Assigned)
To:	;
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ML20206H259	List: ML20206H256; ML20206H263;
References
	NUDOCS 9905110119
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UNITED STATES p

g NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. SpeeHoot l

PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY j

DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY Ft FCTRIC COMPANY DOCKET NO,50274 SALEM NUCLEAR GENERATING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 222 License No. DPR-70 1.

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

A.

The application for amendment filed by the Public Service Electric & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Elect ic Company (the licensees) dated January 15,1999, as supplemented on i

March 31,1999, complies with the standards and requirem6nts of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR ChapterI; 8.

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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicatsle 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 2.C,(2) of Facility Operating License No. DPR 70 is hereby amended to read as follows:

~

9905110119 990504 PDR ADOCK 05000272 P

PDR

.g - l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 222, are hereby incorporated in the license. The licensee shall operate the fadlity in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION J mes W. Clifford, Chief, Section 2 Project Directorate 1 l

Division of Licensing Project Management l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: May 4,1999 I

t

1 I

ATTACHMENT TO LICENSE AMENDMENT NO.m FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Panes Insert Paaes 3/4 1-9 3/4 1-9 l

3/4 3-11 3/4 3-11 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14.

3/4 3-31a 3/4 3-31a 3/4 3-57 3/4357 3/4 3-57a 3/4 3-57a i

3/4 5-2 3/4 5-2 3/4 5-5 3/4 5-5 3/4 7-20 3/4 7-20 3/4 7-34 3/4734 3/4 & 5 3/4 & 5

. 3/4 8-5a 3/4 8-5a 3/4 8 9a 3/4 8-9a 3/4 8-12 3/4 8-12 3/4 8-14 3/4 8-14 i

4

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l REACTIVITY CONTROL SYSTEMS SURVEIIIANCE REQUIREMENTS (Continued)

c.

At least once per 18 months during shutdown by verifying that l

l each automatic valve in the flow path actuates to its correct l

position on a safety injection test signal.

d.

At least once per 18 months by verifying that the flow path required by specification 3.1.2.2.a delivers at least 33 gym to the Reactor Coolant System.

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A one time extension to this surveillance requirement which is l

satisfied by performance of the Manual SI test is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

SAI.EW - UNIT 1 3/4 1-9 Amendment No.222

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e TABLE 4. 3-1 (Continued)

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

(1)

If not performed in previous 31 days.

(2)

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

(3)

Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference a 3 percent.

l (4)

Manual, SSPS functional ittput 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.

j (7) -

Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8)

' Deleted j

(9) -

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Undervoltage acid Shunt Trip sechanism for the Manual Reactor Trip Function.

The Test shall also verify OPERABILITY of the Bypass Breaker Trip circuits.

(10)

DELETED (11)

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip mechanisms.

(12)

DELETED

- A one time extension to this surveillance' requirement which is satisfied by performance of the Manual SI test is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

SALEM - UNIT 1 3/4 3-13 Amendment No. 222

7 l

INSTRUMENTATIQN 3/4.3.2 EiMI=h dD SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 1,IMITING CONDITION NCR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

. b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CNECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation hgic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3*

The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall l

be demonstrated to be within the limit at least onoe per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per functiors such that all channels are tested at least onoe per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

The provisions of Specification 4.0.4 are not applicable to MSIV closure time testing. The provisions of Specification 4.0.4 are not applicable to the turbine

. driven auxiliary feedwater pump provided the surveillanoe is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the secondary steam generator pressure is greater than 680 psig.

A one time extension to this eurveillance requirement for performance of relay time response and sequence testing of the safeguard equipment control (SEC) system, which partially satisfies the surveillance requirement, is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the IR13 outage, prior to the unit returning to Mode 4 upon outage completion.

SALEM - UNIT 1 3/4 3-14 Amendment No.222 l,

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7-O EMERGENCY CORE COOI,ING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

-b,

.At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of a 1% of tank volume by verifying the boron concentration of the accumulator solution.

c.

At least once per 31 days when the RCS pressure is greater than 1000 psig by verifying that the power lockout switch is in lockout.

d.* ' At least once per 18 months by verifying that each acc.taulator l

isolation valve opens automatically upon receipt of a saf3ty injoction test signal.

1 i

A one time extension to this surveillance requirement which is satisfied by performance of the Manual SI test is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion, i

SALEM - UNIT-1 3/4 5-2 Amendment No. 222

A EMERGENCY CORE COOLING SYSTEMS SURVEILIANCE REQUIREMENTS (Continued) c.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to.the containment sump and cause restriction of the pump suctions during IDCA conditions. This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

At least once daily (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months consecutive period) the areas affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

d.

At least once per 18 months by:

1.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.)- show no evidence of structural distress or corrosion, e.

At least once per 18 months, during shutdown, by:

1*

Verifying that each automatic valve in the flow path actuates l

to its correct position on a safety injection test signal.

2.

Verifying that each of the following pumps start automatically upon receipt of a safety injection' test signal:

a)

Centrifugal charging pump b)

Safety injection pump c)

Residual heat removal pump

A one time extension to this surveillance requirement which is satisfied by performance of the Manual SI test is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

l i

i SALEM - UNIT 1 3/4 5-5 Amendment No. 222 i

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PLANT SYSTEMS

. SURVEILLANCE REQUIREMENTS 4.7.6.1 Each control room emergency air :ouditioning system filtration train shall be demonstrated OPERABLE:

a.

At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train (s) and verifying that the train (s) operates with each fan operating for at least 15 minutes.

b.

At least once per 18 months or prior to return to service (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1.

Verifying that the charcoal adsorbers remove 299% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place while operating the ventilation system at a flow rate of 8000 cfm

10%.

2.

Verifying that the HEPA filter banks remove 299% of the DOP when they are tested in-place while operating tne ventilation system at a flow rate of 8000 cfm

10%.

l 3.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample from one of the charcoal adsorbers demonstrates a removal efficiency of 299% for radioactive methyl iodide when the sample is tested at 30 C,95%

relative humidity, c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of 2 99% for radioactive methyliodide when the sample is tested at 30 C,95% relative humidity.

j d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filter and charcoal adsorber bank is s 3.5 inches water gauge while operating the ventilation system at a flow rate of 8000 cfm

10%.

2.*

Verifying that on a safety injection test signal or control room intake high I

radiation test signal, the system automatically actuates in the pressurization mode by opening the outside air supply and diverting air flow through the HEPA filter and charcoal adsorber bank.

3.

Verifying that the system can maintain the control room at a positive pressure 2 1/8" water gauge relative to the adjacent areas during system operation with makeup air being supplied through the HEPA filters and charcoal adsorbers at the design makeup flow rate of s 2200 cim.

A one time extension to this surveillance requirement which is satisfied by performance of the Manual SI test is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (IR13). The surveillance testing is to be completed at the appropriate time during the IR13 outage, prior to the unit returning to Mode 4 upon outage completion.

SALEM - UNIT 1 3/4 7-20 Amendment No. 222 t

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION: MODES 5 and 6 or during movement ofirradiated fud assemblies.

a.

With one chillerinopersble:

1.

Remove the appropriate non-essential heat loads from the chilled water i

system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and; 2.

Restore the chiller to OPERABLE status within 14 days or; l

3.

Suspend CORE ALTERATIONS and movement ofirradiated fuel assemblies.

b.

With two chillers inoperable:

1.

Remove the appropriate non-essential heat loads from the chilled water system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and; 2.

Align the control room emergency air conditioning system (CREACs) for single filtration operation using the Salem Unit 2 train within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and; 3.

Restore at least one chiller to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or; l

4.

Suspend CORE ALTERATIONS and movement ofirradiated fuel assemblies.

With one chilled water pump inoperable, restore the chilled water pump to c.

OPERABLE status within 7 days or suspend CORE ALTERATIONS and l

4 movement ofirradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS l

4.7.10 The chilled water loop which services the safety-related loads in the Auxiliary Building shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each manual valve in the chilled water system flow path servicing safety related components that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. ** At least once per 18 months, by verifying that each automatic valve actuates to its l correct position on a Safeguards Initiation signal.

c.

At least once per 92 days by verifying that each chiller starts and runs.

During Mohs 5 and 6 and during movement ofirradiated fuel assemblies, chilled water components are not considered to be inoperable solely on the basis that the backup emergency power source, diesel generator, is inoperable.

- A one time extension to this surveillance requirement for performance of relay time response and sequence testing of the safeguard equipment control (SEC)

. system, which partially satisfies the surveillance requirement,is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (IR13).' The surveillance testing is to be completed at the appropriate time during the IR13 outage, prior to the unit returning to Mode 4 upon outage completion.

SALEM - UNIT 1 3/4 7-34 Amendment No. 222

i ELECTRICAI, POWER SYSTEMS SURVEILIANCE REQUIRDS,NTS (Continued) c)

Verifying that all nonessential. automatic diesel generator trips (i.e., other than engine overspeed, lube oil pressure low, 4 KV bus differential and generator differential), are automatically bypassed upon loss of voltage on the vital bus concurrent with a safety injection actuation signal.

7.*** Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *.

)

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to 2760-2860 kw.**

During the remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel generator shall be loaded to 2500-2600 kw**.

The steady state voltage and frequency shall be maintained at 2 3910 and 5 4580 volts and 60 i 1.2 Hs during this test.

8.

Verifying that the auto-connected loads to each diesel generator do not exceed the two hour rating of 2860 kw.

9.

Verifying that with.the diesel generator operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by (1) returning the diesel generator to l

. standby operation and (2) automatically energising the emergency loads with offsite power.

e.

' At least once per ten years or after any modifications which could affect diesel generator interdependence by starting all diesel generators simultaneously *, during shutdown, and verifying that all diesel generators accelerate to at least 58.8 Hs in less than or aquel to 13 seconds.

f.

At least once per 18 months, the following test shall be performed within 5 minutes of diesel shutdown after the diesel has operated for at least two hours at 2500-2600 kw**:

l Verifying the diesel generator starts and achieves 2 3910 volts and i

2 58.8 Hs in $ 13 seconds, and subsequently achieves steady state voltage j

of 2 3910 and $ 4400 volts and frequency of 60 i 1.2 Hz.

4.8.1.1.3 The diesel fuel oil storage and transfer system shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

l '. -

Verifying the level in each of the above required fuel storage tanks.

2.

Verifying that both fuel transfer pumps can be started and 1-transfer fuel from the fuel storage tanks to the day tanks.

SALEM - UNIT 1 3/4 0-5 Amendment No. g l

t i

lm

.-.--.,.-..-.--.--------.-----m.-...+

e

\\

IIECTRICAL POWER SYSTEMS SURVEILIANCE REQUIREISNTS (Continued) b.

At least once per 92 days by verifying that a sample of diesel fuel from each of the above required fuel storage tanks is within the acceptable limits specified in Table 1 of ASTM D975-77 when checked for viscosity, water and sediment.

4. 0.1'.1. 4 ReDorts - NOT USED' Surveillance testing may be conducted in accordance with the manufacturer's recommendations regarding engine prelube, warm-up and loading (unless loading times are specified in the individual Surveillance Requirements).

This band is meant as guidance to preclude routine exceedances of the diesel generator manufacturer's design ratings. Loads in excess of this band for special testing or momentary variations due to changing bus loads shall not invalidate the test.

A one-time extension to this surveillance requirement is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance is to be completed at the appropriate time during the 1R13 outage, prior to the

. unit returning to Mode 4 upon outage ocapletion.

SALEM - UNIT 1 3/4 8-5a Amendment No.P22

1 4

EI.ECTRICAL POWER SYSTEMS SURVEILIANCE REQUIREMENTS (Continued)

)

3.

The connection resistance is:

s 150 micro ohms for inter-tell connections, t 350 micro ohns for inter-rack connections, s 350 micro ohns for inter-tier connections, j

s 70 micro ohms for field cable terminal connections, and s 2500 micro ohms for the total battery connection resistance which includes all inter-cell connections (including bus bars), all inter-rack connections (including cable resistance), all inter-tier connections (including cable resistance), and all field terminal connections at the battery.

e.

At least once per 18 months by verifying that the battery charger will supply at least 170 amperes at 125 volts for at least 4

hours, f.* At least once per 18 months, during shutdown, by verifying that l

the battery capacity is adequate to supply and maintain in OPERABLE status all of the. actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test.

g.

At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.

Satisfactory completion of this performance discharge test shall also satisfy the requirements of Specification 4.8.2.3.2.f if the performance discharge test is conducted during a shutdown where that test and the battery service test would both be required.

h.

At least once per 12 months, during shutdown, if the battery shows signs of degradation 98 has reached 85% of the service life with a capacity less than 100% of manufacturers rating, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Degradation'is indicated when the battery capacity dropa more than 10% of rated capacity from its capacity on the previous performance test, or is below 90% of the manufacturer's rating, i.

At least once per 24 months, during shutdown, if the battery has reached 85% of the service life with capacity greater than or equal'to 100% of manufacturers rating, by verifying that the j

battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.

l

-A one-time extension to this surveillance requirement is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance is to be completed'at the appropriate time during the IR13 outage, prior to the unit' returning to M>de 4 upon outage completion.

SALEM - UNIT 1 3/4 8-9a Amendment No. 222

h o.

'}

EIECTRICAL POWER SYSTEMS i'

SURVEILLANCE REQUIREM NTS (Continued) 2.

The pilot cell specific gravity, corrected t.o 77*F, and full electrolyte level, is greater than or equal to 1.200.

3.

The pilot cell voltage is greater than or equal to 2.08 volts.

l l

4.

The overall battery voltage is greater than or equal to 27 volts.

b.~

At least' once per 92 days by verifying that 1.

'The voltage of each connected cell is greater than or equal to l

2.13 volts under float charge and has not decreased more than 0.27 volts from the value observed during the original acceptance test.

2.

The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.02 from the value observed during the previous test.

3.

The electrolyte level of each connected cell is between the minimum std =mw4=um level indication marks.

c.

At least once per 18 months by verifying-that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.

j

2.

The cell-to-cell and terminal connections are clean, tight, and l

coated with anti-corrosion material.

3.

. The battery charger will supply at least 150 amperes at 28 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d.*

At least once per 18 months, during shutdown, by verifying that the l

l battery capacity is adequate to supply and maintain in OPERABIZ status l

all of the actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test, e.

At least once per 60 months, Auring shutdown, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Satisfactory completion of l

this performance discharge test shall also satisfy the requirements of j

Specification 4.8.2.5.2.d'if the performance discharge test is conducted during a shutdown where that test and the battery service test would both be required.

l l

A one-time extension to this surveillance requirement is granted

[

during fuel cycle thirteen allowing Unit 1 oparations to continue to l

the thirteenth refueling outage (1R13). The surveillance is to be

-completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

SAIEN - 12 TIT 1 3/4'8-12 Amendment No.222 l

1 l

l.

i

1 a

'e ELECTRICAL PONER Si* STEMS

~3/4 8.3 ELECTRICAL EOUIPMENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION' 3.3.3.1 All containment penetration conductor overcurrent protective devices required to provide thermal protection of penetrations shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the required containment penetration conductor overcurrent protective device (s) inoperable:

a.

Restore the protective device (s) to OPERABLE status or de-energise the circuit (s) by tripping either the primary or backup protective devios, or racking out or removing the primary or backup device within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable, and verify the primary or backup protective device to be tripped, or the primary or backup devios racked out or removed at least once per 7 days thereafter; or b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDONN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.0.3.1 All required containment penetration conductor overcurrent protective devices l

shall be demonstrated OPERABLE:

)

i m.

At least once per 18 months:

1.*,** For at least one 4.16 KV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least onoe per I

72 months, by performance of:

(a) A CHANNEL CALIBRATION of the associated protective relays, and (b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and

. associated circuit breakers and control circuits function as designed.

A one time extrinaion to this surveillanoe requirement for inspection calibration and seggaring of the IF 4KV Bus overload relays, which partially satisfies this surveillance requirement, is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

- A one time extension to this surveillance requirement for inspection calibration and maggaring of the 1A, 1B, and 1C 460 transformer relays and CT's, which partially satisfy this surveillance requirement, is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

SALEM - UNIT 1 3/4 8-14 Amendment No.222

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