ML17223A404

Proposed Tech Specs Making Administrative Changes to Achieve Consistency Throughout by Removing Outdated Matl,Making Minor Text Changes,Correcting Errors & Implementing Improvements Recommended by Generic Ltr 89-14

ML17223A404
Person / Time
Site:	Saint Lucie
Issue date:	11/17/1989
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17223A403	List: L-89-407, Application for Amends to Licenses DPR-67 & NPF-16,making Administrative Changes to Tech Specs to Achieve Consistency Throughout by Removing Outdated Matl,Making Minor Text Changes & Implementing Improvements Per Generic Ltr 89-14 ML17223A404
References
GL-89-14, NUDOCS 8911280066
Download: ML17223A404 (45)

Text

ATTACHMENT 1 Marked-up St. Lucie Unit. 1 Technical Specifications Pages:

3/4 0-2 3/4 3-39 3/4 3-40 3/4 4-5 3/4 4-8 B 3/4 0-6 85'11280066 891117 F'DR SDOCV OSOOOSS~

PDC

APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the s

cified interval with~

s pe,%ed s.c.c,//.-c a.

maximum allowable extension not to exceed 251. of the ~:-

interval ~d H;-4e-exceed-3.25t 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 2'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance in'terval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,

2 and 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1,

2 and 3 components and inservice testing ASME Code Class 1,

2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inser vice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ST.

LUCIE - UNIT 1

3/4 0-2 Amendment No. gg,gg,gg, gB

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TABLE 3.3-10 FIRE DETECTION INSTRUMENTATION

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.02.13

.02.14 02.15

.02.20

.02.21

.01.22

.01.01

.01.02

.01.03 ZONE jY.02.01 Q.02.02

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.02.12 MINIMUM DETECTORS OPERABLE THERMAL SMOKE 6

3 12 2

7 9

1 3

3 1

7 1

9 10 2

3 1

6 6

12 LOCATION ZONE-18 REACTOR AUX. BLDG. EL.0.50 I

ZONE-28 REACTOR AUX. BLDG. EL. 0.50 ZONE-38 REACTOR AUX. BLDG. EL.19.50 ZONE-48 REACTOR AUX. BLDG.

EL.43.00'ONE-58 REACTOR AUX. BLDG. EL.19.50 ZONE-68 REACTOR AUX. BLDG. EL.43.00 ZONE-78 REACTOR AUX. BLDG. EL.43.00 ZONE-88 REACTOR AUX. BLDG. EL.62.00 ZONE-98 REACTOR AUX. BLDG. EL.43.00 ZONE-108 REACTOR AUX. BLDG. EL.43.00 ZONE-118 ELECT.

PENET.

REC.

(ANNULUS)

ZONE-128 ELECT.

PENET.

REC.

AUX. BLDG.

I EL.19;60 ZONE-138 REACTOR TUNNEL BELOM EL.18.00 ZONE-148 REACTOR EL.18.00 ZONE-158 REACTOR EL.45.00 ZONE-208 FUEL HANDLING BLDG. EL.19.50 ZONE-218 FUEL HANDLING BLDG. EL.48.00 ZONE-228 DIESEL GEN.

BLDG.

ZONE-1A REACTOR AUX. BLDG. EL.0.50 ZONE-2A REACTOR AUX. BLDG. EL.0.50 ZONE-3A REACTOR AUX. BLDG. EL.19.50

, *Includes pre-action detectors.

ST.

LUCIE - UNIT 1

3/4 3-39 Amendment No. g$,

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TABLE 3.3-10 (Cont'd)

FIRE DETECTION INSTRUMENTATION ZONE I

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MINIMUM DETECTORS OPERABLE THERMAL SMOKE 1

7 9

9 8

6 3

3 1

6 3

10 7

LOCATION ZONE-4A REACTOR AUX. BLDG.. EL.19.50 ZONE-5A REACTOR AUX. BLDG. EL.19.50 ZONE<<6A REACTOR AUX. BLDG. EL.43.00 ZONE-7A REACTOR AUX. BLDG. EL.43.00 ZONE-8A REACTOR AUX. BLDG. EL.62.00 ZONE-9A REACTOR AUX. BLDG. EL.43.00 ZONE-10A REACTOR AUX. BLDG. EL.43.00 ZONE-llA ELECT.

PENET.

REC.

(ANNULUS)

ZONE-12A ELECT.

PENET.

REC. AUX. BLDG.

EL.19.60 ZONE-13A REACTOR TUNNEL BELOW EL.18.00 ZONE-14A REACTOR EL.18.00 ZONE-15A REACTOR EL.45.00 ZONE-20A FUEL HANDLING BLDG. EL.19.50 ZONE-21A FUEL HANDLING BLDG. EL.48.00 ZONE-22A DIESEL GEN.

BLDG.

• Includes pre-action detectors.

ST. LUCIE.- UNIT 1

3/4 3-40 Amendment No. 2$.

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REACTOR COOLAh:

SYSTEM STEAM GENERATORS LIMITING CONOITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable'enerator(s) to OPERABLE status prior to increasing T

above 200'F.

avg SURVEILLANCE REQUIREMENTS 4.4.5.1 Steam Generator Sample Selection.

and Inspection - Each steam generator shall be der rmined OPEP"BLE during shutdown oy selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.5.2 Steam Generato~

Tube Sample Selec" on and Inscection - Tne steam generator zuoe minimum sample size,

nsoection result classy"ication, and the corresponding action required shali "e as soecified in Table 4.4-2.

The inservice inspec ion of steam generator cubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspe ted tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.

4 The tubes selected for each inservice inspection shall include at least 3'f the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except.'

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Nhere experience in similar plants with similar water chemistry indicates critical areas to be.inspected, then at least 50" of the tubes inspected shall be from these critical areas.

b.

The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1.

All nonplugged tubes that previously had detectable wall penetrations

(>ZO")', and 2.

Tubes in those areas where experience has indicated potential problems.

ST.

LUCIE - UNIT 1

3/4 4-5'

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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued b.

5.

Oefect means an imperfection. of such severity that it exceeds the pTugging limit.

A tube containing a defect is defective.

Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.

6.

Plu in Limit means the imperfection depth at or beyond wh>ch the tu e shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40 of the nominal tube wall thickness.

7.

Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a

loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

8.

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.g tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.5.5

~Re orts a e b.

Following each inservice inspection of steam generator

tubes, the number of tubes plugged in each steam generator shall be reported to the Comnission within 15 days.

The complete results of the steam generator tube inservice inspec-tion shall be included in the Annual Operating Report for the period in which this inspection was completed.

This report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

• This 40%

uggi g lim is t ap icab duri g the ycle 7 perati n up to ne 19

. If at an time durin this eriod he uni enter any Mo es o

er t an Mo s

1 d 2, r Mod 3 for great than 4 hou

, the it all plac d in ld s tdow and t tub with dicati ns gre er than OX t ough all p netra ion s ll be remov from ervice rior ex edin 200'F ST.

LUCIE - UNIT 1 3/4 4-8 Amendment No. 73

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APPLICABILITY BASES The specifications of this section establish the general requirements applicable to Surveillance Requirements.

These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility 'operation will be within safety limits, and that the limiting conditions of operation will be met."

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~ ppgft~ r'C 9lioO tlat iS 4.0.1 This specification establishes the requirement that sur veillances must be performed during the OPERATIONAL NODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in 'an individual Surveillance Requirement.

The purpose of this specifi-cation is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a t)ODE or other specified condition for which the associated Limiting Conditions 'for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL NODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test exception is used as an allowable exception to the requirements of a ation.

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4.0.2 This specification establishes the which the specified time interval for Surveillance Requirements may be extended. ~a~

permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that ma not be suitable for conductin the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance ac

>vs ses.

used repeatedly to tend the surveillance interva beyond that specified.

The limit o

S ecification 4.0.2 based on engineering judgment an the recognition that the most probable result of any particular surveillanc eing performed is the verification of conformance with the Surveillance Requi ents.

sufficient to ensure that the reliability ensured ough surveillance activities is not significantly degraded beyond that ob ned from the specified surveillance interval.

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LUCIE - UNIT 1

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ATTACHMENT 2 Marked-up St. Lucie Unit 2 Technical Specifications Pages 3/4 0-2 3/4 3-4 (plus insert) 3/4 4-2 3/4 4-12 3/4 4-12a 3/4 6-1 3/4 9-9 B 3/4 0-4

APPL ICABILITY SUPVEILLAHCE RE UIREMENTS 4.0.1 Surveillance Pequirements shall be applicable during the OPEPATIONAL

.MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the s ecified 5 ggpc I14Ncc. 4+ac int rva1 with~

gpec'gag maximum allowable extension not to exceed 25K of the surveillance interval ~md-(&

4.0.3 Failure to perform a Surveillance Requirement within the allowed surv.illance interval, defined by Specification 4.0.

, shall constitute noncomoliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowaCle outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL !10DE or other specified condition shall not be made unless the Surveillance Pequirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

This provision shall not pre'vent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code "lass 1, 2 and 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1,

2 and 3 components and inservice testing ASHE Code Class 1,

2 and 3 pumps and valves shall be performed in accordance with Section YI of the ASML Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to,l.0 CFR 50, Section 50.55a(g)(6)(1).

b.

Surveillance intervals specified in Section XI Of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ST.

LUCIE - UNIT 2 3/4 0-2 Amendment No. 33

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TABLE 3. 3-1 Continued ACTION STATEMENTS ACTION 2 a.

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5. 1.6m.

The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

b.

With the number of channels OPERABLE one less than the Minimum Channels

OPERABLE, STARTUP and/or POWER OPERATION may continue provided the following conditions are satisfied:

1.

Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.

All functional units affected by the bypassed/tripped channel shall also be placed in the bypassed/tripped condition.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or. tr ip all associated functional units as listed below:

Process Measurement Circuit Functional Unit Bypassed

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Pressurizer Pressure-High 3.

Containment Pressure-High 4.

Steam Generator Pressure-Low 5.

Steam Generator Level Pressurizer Pressure

- High (RPS)

Thermal Margin/Low Pressure (RPS)

Containment Pressure

- High (RPS)

Containment Pressure

- High (ESF)

St'earn Generator Pressure Low (RPS)

Steam Generator hP 1 and 2

(AFAS 1 and 2)

Thermal Margin/Low Pressure (RPS)

Steam Generator Level -

Low (RPS)

Steam Generator DP (AFAS)

ST.

LUCIE - UNIT 2 3/4 3-4

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Insert Page 3/4 3-4 Safety Channel-Nuclear Instrumentation Wide Range Linear Range Rate of Change of Power-High (RPS)

Variable Power Level-High (RPS)

Local Power Density-High (RPS)

Thermal Margin/Low Pressure (RPS)

REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 The Reactor Coolant loops listed below shall be OPERABLE and at least one of these Reactor Coolant loops shall be in operation."

a.

Reactor Coolant Loop 2A and its associated steam generator and at least one associated Reactor Coolant pump.

b.

Reactor Coolant Loop 2B and its associated steam generator and at least one associated Reactor Coolant pump.

APPLICABILITY:

MODE 3g" dele&6 ACTION:

a.

With less than the above required Reactor Coolant loops

OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With no Reactor Coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required Reactor Coolant loop to operation.

SURVEILLANCE RE UIREMENTS 4.4. 1.2. 1 At least the above required Reactor Coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4. 1.2.2 At least one Reactor Coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4. 4. 1.2.3 The required steam generator(s) shall be determined OPERABLE verifying the secondary side water level to be

> 10K indicated narrow range level at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

All Reactor Coolant pumps may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.

ST.

LUCIE - UNIT 2 3/4 4-2

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SUR",EILLAt!CE'E UIREMENTS (Continued l.

All nonplugged tubes that previously had detectab1e wa11 penetrations (greater than 20%),

2.

Tubes in those areas where experience has indicated potential problems.

3.

A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube.

If any selected tube does not permft the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c.

The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice fnspection may be subjected to partial tube inspection provided:

l.

The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes wtih imperfections were previously found.

2.

The inspections fnclude those portions of the tubes where imperfections were prevfously found.

The results of each sample inspection shall be classfffed into one of the following three categories:

~Cats or C-1 C-2 Ins ection Results Less than 5% of the total Cubes inspected are degraded tubes and none of the inspected tubes are defective.,

One of more tubes, but not more than 1% of the total tubes inspected are defective, or between 5X and 10% of Che total tubes inspected are degraded tubes.

ST.

LUCIE - UNIT 2 3/4 4<<12 Amendment No. 24

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REACTOR COOLANT SYSTEM SUR" E ILLANCE RE UIREHENTS Continued

~Cate or C-3 Ins ection Results More than 10K of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note:

{1} In all inspections, previously degraded tubes must exhibit significant (greater than 10%} further wall penetrations to be included in the above percentage calculations.

ST.

LUGIE - UNIT 2 3/4 4-12a Amendment No.

24

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3/4. 6'ONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1", 2", 3, and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations""

not capable of being closed by OPERABLE containment automatic isolation valves and requir ed to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.

b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6. 1.3.

c.

After each closing of each penetration subject to Type B testing, except containment air locks, if opened following a Tyne A or B

'est, by leak rate testing the seal with gas at P

', 41.8 psig and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specifica-tion 4.6. 1.2d. for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L.

a'n MODES 1 and 2, the RCB polar crane shall be rendered inoperable by locking the power supply breaker open.

• A Except valves, blind flanges, and deactivated'utomatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

ST.

LUCIE - UNIT 2 3/4 6-1 Amendment No.

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION

3. 9. 8. 2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operations APPLICABILITY:

MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a.

b.

With less than the required shutdown cooling loops

OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel

flange, as soon as possible.

With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to operation.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.9.8.2 At least one shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ST.

LUCIE - UNIT 2 3/4 9-9

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BASES The specifications of this section establish the general requirements applicable to Surveillance Requirements.

These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3);

"Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."

4.0.1 This specification establishes the requirement that surveillances must be performed during the OPERATIONAL tlODES or other conditions for which the reuqirements of the Limiting Cinditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this speci-fication is to ensure that surveillances are performed to verify the opera-tional status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a

NOOE or other specified condition for which the associated L'ihiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

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4.0.2 This specification establishes the ~ad~iens for which the s ecified time interval for Surveillance Requirements may be extended.

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permits an allowable extension of the normal surveillance interval to facilitate 4LS surveillance scheduling and consideration of plant operating conditions that ma not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or main enance ac ivi ies.

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extend the surveillance interval beyond that specific The limit/of S ecification 4.0 "

based on engineering judgment an e recogni ion that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.

Wese-sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

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LUCIE - UNIT 2 il P grC p~gq c4 p4fi(C /Ig g ~ Q f C4

,Amendment No. 33

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<C ATTACHMENT 3 SAFETY ANALYSIS INTRODUCTION These amendments are submitted to make administrative changes to the St.

Lucie Unit 1

and Unit 2 Technical Specifications and achieve consistency throughout the Technical Specifications by removing outdated material, making minor text changes, correcting errors and implementing the line item improvements recommended by Generic Letter 89-14 "Removal of the 3.25 Limit on Extending Surveillance Intervals."

DISCUSSION The proposed amendments represent an administrative update to the St.

Lucie Units 1

and 2 Technical Specifications.

Each of the proposed changes is discussed below:

St. Lucie Unit 1 1)

Item:

Pages 3/4 0-2 and B 3/4 0-6 Action:

Revise Specification 4.0.2 and the Bases to Specification 4.0.2 to incorporate Generic Letter 89-14 line item improvements.

Discussion:

Specification 4.0.2 of the St.

Lucie Unit 1

Technical Specifications permits surveillance intervals to be extended up to 25 percent of the specified interval.

This extension facilitates the scheduling of surveillance activities and allows surveillances to be postponed when plant conditions are not suitable for conducting a surveillance, for example, under transient conditions or other ongoing surveillance or maintenance activities.

Specification 4.0.2 also limits extending surveillances so that the combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

The intent of the 3.25 limit is to preclude routine use of the provision for extending a surveillance interval by 25 percent.

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Recent review of the 3.25 limit has resulted in issuance by the NRC of Generic Letter (GL) 89-14 "Line-Item Improvements in Technical Specifications Removal of the 3.25 Limit on Extending Surveillance Intervals."

Generic Letter 89-14 provides guidance to licensees for proposing a

license amendment to remove the 3. 25 limit from Specification 4. 0.2.

In GL 89-14, the NRC stated that experience has shown that the 18-month surveillance interval, with the provision to extend it by 25 percent, is usually sufficient to accommodate normal variations in the length of a fuel cycle.

However, in GL 89-14, it was also stated that the NRC Staff has routinely granted requests for one-time exceptions to the 3.25 limit on extending refueling surveillances because the risk to safety is low in contrast to the alternative of a forced shutdown to perform these surveillances.

The Staff concluded in GL 89-14 that the 3.25 limitation on extending surveillances has not been a practical limit on the use of the 25 percent allowance for extending surveillances that are performed on a refueling outage basis.

The use of the allowance to extend surveillance intervals by 25 percent can also result in a significant safety benefit for surveillances that are performed on a routine basis during plant operation.

This safety benefit is incurred when a

surveillance interval is extended at a time that conditions are not suitable for performing the surveillance.

Examples of this include transient plant operating conditions or conditions in which safety systems'are out of service because of ongoing surveillance or maintenance activities.

In such

cases, the safety benefit of allowing the use of the 25 percent allowance to extend a surveillance interval would outweigh any benefit derived by limiting three consecutive surveillance intervals to the 3.25 limit. Also, there is the administrative burden associated with tracking the use of the 25 percent allowance to ensure compliance with the 3.25 limit.

On the basis of these considerations, the Staff concluded that removal of the 3.25 limitwill have on overall positive impact on safety.

2)

Item:

Pages 3/4 3-39 and 3/4 3-40, Table 3.3-10 Action:

Modify "ZONE" location on Table 3.3-10, Fire Detection Instrumentation, to reflect plant fire zone terminology.

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Discussion:

The modified zone number reflects St. Lucie Plant fire zone enumeration for St. Lucie Unit 1.

No change in fire zones is proposed; this change reflects human factors improvements by maintaining system and component labeling consistency to reduce wrong unit/wrong train/wrong component errors.

3)

Item:

Page 3/4 4-5, Surveillance Requirement 4.4.5.2 Steam Generator Tube Sam le Selection and Ins ection Action:

Delete the sentence "Steam generator tubes shall be examined in accordance with Appendix IV of the ASME Boiler and Pressure Vessel Code Section XI "Inservice Inspection of Nuclear Power Plant Components",

1974 Edition and Addenda through Summer 1976."

Discussion:

St.

Lucie Unit 1 License Amendment No.

90, issued March 7, 1988, revised Surveillance Requirement 4.0.5 to require that surveillances be performed in accordance with ASME Section XI as required by 10 CFR 50, Section 50.55a(g).

This required meeting the latest approved revision of the ASME Code in effect at the time of a

new 10 year Inservice Inspection Interval.

Amendment No.

90 revised several other Technical Specifications Surveillance Requirements to address ASME Code Requirements;

however, Surveillance Requirement 4.4.5.2 was not included in this revision.

Technical Specification 4.4.5.2 requires performance of steam generator tube examinations per ASME Section XI, 1974 Edition Summer 1976 Addenda, while Surveillance Requirement 4.0.5 and 10 CFR 50.55a(g) require use of the 1983 Edition, Summer 1983 Addenda.

Accordingly, the sentence should be deleted to be consistent with Surveillance Requirement 4.0.5, the balance of the St.

Lucie Unit 1 Technical Specifications as well as the St. Lucie Unit 2 Technical Specifications.

4)

Item:

Page 3/4 4-8, footnote *.

Action:

Delete footnote "*" at the bottom of the page and "*" after 404 in the last line of Surveillance Requirement 4.4.5.4 a.6.

Discussion:

This footnote was requested by FPL letter L-86-227 dated May 30,

1986, and approved by the NRC in Amendment No.

73 dated May 30, 1986.

This footnote is obsolete since St.

Lucie Unit 1 is now in Cycle 9 and the June 30, 1986 date has passed.

FPL met the conditions of this footnote and subsequent activities by FPL relative to the St. Lucie Unit 1 steam generators have removed the need for this footnote.

St. Lucie Unit, 2 1)

Item:

Pages 3/4 0-2 and B 3/4 0-6 Action:

Revise Specification 4.0.2 and the Bases to Specification 4.0.2 to incorporate Generic Letter 89-14 line item improvements.

Discussion:

Specification 4.0.2 of the St.

Lucie Unit 2

Technical Specifications permits surveillance intervals to be extended up to 25 percent of the specified interval.

This extension facilitates the scheduling of surveillance activities and allows surveillances to be postponed when plant conditions are not suitable for conducting a surveillance, for example, under transient conditions or other ongoing surveillance or maintenance activities.

Specification 4.0.2 also limits extending surveillances so that the combined time interval for any three consecutive surveillance intervals shall not. exceed 3.25 times the specified surveillance interval.

The intent of the 3.25 limit is to preclude routine use of the provision for extending a surveillance interval by 25 percent.

Recent review of the 3.25 limit has resulted in issuance by the NRC of Generic Letter (GL) 89-14 "Line-Item Improvements in Technical Specifications Removal of the 3.25 Limit on Extending Surveillance Intervals."

Generic Letter 89-14 provides guidance to licensees for proposing a

license amendment to remove the 3.25 limit from Specification 4.0.2.

In GL 89-14, the NRC stated that experience has shown that the 18-month surveillance interval, with the provision to extend it by 25 percent, is usually sufficient to accommodate normal variations in the length of a fuel cycle.

However, in GL 89-14, it was also stated that the NRC Staff has routinely

granted requests for one-time exceptions to the 3.25 limit on extending refueling surveillances because the risk to safety is low in contrast to the alternative of a forced shutdown to perform these surveillances.

The Staff concluded in GL 89-14 that the 3.25 limitation on extending surveillances has not been a practical limit on the use of the 25 percent allowance for extending surveillances that are performed on a refueling outage basis.

The use of the allowance to extend surveillance intervals by 25 percent can also result in a significant safety benefit for surveillances that are performed on a routine basis during plant operation.

This safety benefit is incurred when a

surveillance interval is extended at a time that conditions are not suitable for performing the surveillance.

Examples of this include transient plant operating conditions or conditions in which safety systems are out of service because of ongoing surveillance or maintenance activities.

In such

cases, the safety benefit of allowing the use of the 25 percent allowance to extend a surveillance interval would outweigh any benefit derived by limiting three consecutive surveillance intervals to the 3.25 limit. Also, there is the administrative burden associated with tracking the use of the 25 percent allowance to ensure compliance with the 3.25 limit.

On the basis of these considerations, the Staff concluded that removal of the 3.25 limitwill have on overall positive impact on safety.

2)

Item: Page 3/4 3-4, Table 3.3-1, ACTION 2, Process Measurement Circuit 1.

Action:

Differentiate between the Functional Units which use wide range logarithmic power measurement instrumentation and those which use linear range power measurement instrumentation.

Discussion:

Eight safety channels of nuclear instrumentation are provided by the Unit 2 excore instrumentation to monitor neutron flux level.

Four channels monitor reactor power and provide a

wide-range logarithmic indication which spans from 10 '4 to 2004 of full power.

The input to the wide-range logarithmic safety channels is provided by fission chamber detector assemblies.

The channels supply start-up rate signals to the Reactor Protection System (RPS) which are input to the Rate of Change of Power trip circuitry.

Four linear power range safety channels provide linear indication that covers a range of 04 to 2004 of full power.

The inputs to the four linear power range channels are

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provided by dual selection ion chambers.

Linear power range signals provide input to the Variable Power Level-High, Local Power Density-High, and Thermal Margin/Low Pressure reactor trip circuitry in the Unit 2 RPS.

The intent of this change is to clarify which functional units must be bypassed when specific nuclear instrumentation channels are taken out of service.

3)

Item:

Page 3/4 4-2, Limiting Condition for Operation (LCO) 3.4.1.2 and Applicability Footnote **

Action:

Delete "**"in LCO 3.4.1.2 and Applicability Footnote **.

Discussion:

St. Lucie Unit 2 achieved initial criticality on June 2, 1983.

4)

Item: Page 3/4 4-12, Surveillance Requirement 4.4.5.2.*d.

Action:

Delete Surveillance Requirement 4.4.5.2.*d.

Discussion:

This Surveillance Requirement is no longer operative and should be deleted.

St. Lucie Unit 2 is now in Cycle 5.

See Item 5 below for further discussion.

5)

Item:

Page 3/4 4-12a Note:

• (2)

Action:

Delete note: *(2).

Discussion:

This note was added by Amendment 24 dated October 15, 1987 granting a

temporary request for relief.

Following discussions with the NRC subsequent to October 15,

1987, FPL withdrew its request for a permanent change by letter L 376, dated August 29, 1988.

The NRC approved FPL's withdrawal request by letter dated September 23, 1988 (E.G. Tourigny to W.F. Conway).

In the Staff's September 23, 1988 letter, the NRC stated:

you may request to delete

..(the temporary change)

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as an administrative Technical Specification change in the future since the period of time that the temporary change was in effect has now passed.

Accordingly, Note:

"*(2)" is proposed to be deleted.

6)

Item:

Page 3/4 4-12a, footnote Action:

Delete footnote *.

Discussion:

As discussed in Item 5 above, this footnote should be deleted.

St. Lucie Unit 2 is now in Cycle 5.

7)

Item:

Page 3/4 6-1, Surveillance Requirement 4.6.1.1a.

Action:

Change reference to Specification 3.6.4 in Surveillance Requirement 4.6.1.1a to reference Specification 3.6.3.

Discussion:

This Surveillance Requirement states:

.. except as provided in Table 3.6-2 of Specification 3.6.4.

Table 3.6-2 is located in Specification 3.6.3.

Specification "3.6.4~~ shall be changed to <<3.6.3."

8)

Item:

Page 3/4 9-9, LCO 3.9.8.2 and footnote *.

Action:

Delete "*" at the end of the last sentence of LCO 3.9.8.2 and footnote *.

Discussion:

St. Lucie Unit 2 achieved initial criticality on June 2, 1983.

As a result, this footnote is no longer operative.

ATTACHMENT 4 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission s regulations, 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a

new or different kind of accident from any accident previously evaluated or (3) involve a significant reduction in a margin of safety.

Each standard is discussed as follows:

(1)

Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

The NRC Staff has concluded that the deletion of the 3.25 limit is acceptable and previously evaluated the proposed change in Generic Letter 89-14, <<Line-Item Improvements in Technical Specifications Removal of the 3.25 Limit on Extending Surveillance Intervals".

Based on the NRC review, this alternative to the current requirement of Specification 4.0.2 will remove an unnecessary restriction on extending surveillance requirements and will result in a benefit to safety when plant conditions are not conducive to the safe conduct of surveillance requirements.

The removal of the 3.25 limit will provide greater flexibilityin the use of the provision for extending surveillance intervals, reduce the administrative burden associated with its use, and have a positive effect on safety.

Therefore, the proposed amendment will not involve a significant increase in the probability or consequences of the accident previously evaluated.

The administrative changes do not affect assumptions contained in plant safety analyses, nor do they affect Technical Specifications that preserve safety analysis assumptions.

'herefore, the proposed changes do not affect the probability or consequences of accidents previously analyzed.

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(2)

Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.

The NRC has previously evaluated the acceptability of this change on a

generic basis in Generic Letter 89-14 and concluded that it will have a positive effect on safety.

A new or different kind of accident is not created since Technical Specif ication LimitingConditions for Operation (LCO) and ACTION statement requirements remain unchanged.

The administrative changes being proposed by FPL willnot lead to material procedure changes or to physical modifications to St.

Lucie Plant.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident.

(3)

Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

The use of the allowance to extend surveillance intervals by 25 percent can also result in a significant safety benefit for surveillances that are performed on a routine basis during plant operation.

This safety benefit is incurred when a

surveillance interval is extended at a time that conditions are not suitable for performing the surveillance.

The changes being proposed do not relate to or modify the safety margins defined in and maintained by the Technical Specifications.

Therefore, the proposed changes would not involve any reduction in a margin of safety.

Based on the above, we have determined that the amendment request does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the probability of a

new or different kind of accident from any accident previously evaluated, or (3) involve a

significant reduction in a margin of safety; and therefore does not involve a significant hazards consideration.

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