ML17221A671
| ML17221A671 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/07/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17221A672 | List: |
| References | |
| NUDOCS 8803180158 | |
| Download: ML17221A671 (81) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POMER 5 LIGHT COMPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NO.
AMENDMENT TO FACILITY APFPATING LICFNSF.
Amendment Nn. 90 License No.
DPI'.-67 1.
The Nuclear Regulatory Commiss'.On (the Commission) has found that:
A.
The applications for amendment hy Florida Power II Light Companv, (the licensee) dated August 17, 1987 and November 16,
- 1987, as supplemented December 30,
- 1987, comply with the standards and requirements of the Atomic Fr ergy 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 con.ormity 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 hy 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 nf 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.
88031801 8
PDR ADDCK.'05000335 P
J
Accordingly, Facility Operating License No.
DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2~
to read as follows:
'(2)
Technical S ecifications The Technical Specifications contained in Appendices A
and 8, as revised through Amendment No.
90, are hereby incorporated in the license.
The.licersee shall operate the facilitv in accordance with the Technical Specifications.
3.
This licer se amendment is effective as o~ the date of its issuance.
~OP, THF. NUCLEAP, REAl!LATOPY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, 1988
~e bert N. Rerkow, Director Proiect Directorate II-2 Division of Peartor Projects-I/II Of~ice of nuclear Reactor Regulation
ATTACHMENT TO LICENSF. AMENDMENT NO.
90 TO FACILITY OPEPATING LICENSF.
NO.
DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number at d contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document com-pleteness.
Remove Pa es 3/4 0-2 3/4 1-8 3/4 1-10 through 3/< 4-2 3/4 4-3 3/4 4-".6 through 3/4 5-4 3/4 5
5 3/4 5-6 3/4 6-15 3/4 6-16 3/4 6-18 3/4 6-19 3/4 6-~6 3/4 7-1 3/4 7-4 3/4 7-5 3/4 7-9 3/4 7-1<
3/4 7-15 3/4 7-16 3/4 7-17 83/4 4-2 83/4 4-1"..
83/4 4-13 3/4 1-15 3/4 ~-55 Insert Paqes 3/4 0-2 3/4 0-3 3/4 1-8 3/< 1-10 through 3/4 4-2 3/4 4-3 3/4 4-".6 through 3/4 5-<
3/4 5-5 3/4 5-6 3/4 6-15 3/4 6-16 3/4 6-18 3/4 6-19 3/4 6-26 3/4 7-1 3/4 7-4 3/4 7-5 3/4 7-q 3/4 7-14 3/4 7-15 3/4 7-]6 3/4 7-17 83/4 0-3 83/4 4-2 83/4 4-12 83/4 4-13 3/4 1-15 3/4 4-55
APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25Ã of the test
- interval, and b.
A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condi-tion shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
The provisions of Specification 4.0.4 are not applicable to the performance of surveillance activities associated with fire protection technical specifica-tions 4.3.3.7.1, 4.3.3.7.2, 4.7.11.1, 4.7.11.2'and 4.7.12 until the completion of the initial surveillance interval associated with each specification.
4.').5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,
2 and 3 components shall be applicable as follows:
a.
Inser vice inspection of ASHE 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 CFP, 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 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 1
3/4 0-2 Amendment No. g5, PP, 90
APPL ICABILITY SURVEILLANCE RE UIREMENTS (Continued) 4.0.5 (Continued)
ASHE Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice inspection and testin activities Required frequencies for performing inservice inspection and testing activities Weekly Monthly quartet ly or every 3 months Semiannually or every 6 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
ST.
LUGIE - UNIT 1
3/4 0-3 Amendment No.
90
REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.5 The Reactor Coolant System lowest operating loop temperature (T ) shall be
> 515'F when the reactor is critical.
APPLICABILITY:
MODES 1 and 2k'.
ACTION:
With a Reactor Coolant System operating loop temperature (Tav
)
<515'F, restore T
to within its limit within 15 minutes or be in HIT STANDBY within thPkext 15 minutes.
SURVEILLANCE RE UIREMENTS 4.1.1.5 The Reactor Coolant System temperature
{T
) shall be determined to be
> 515'F.
a.
Within 15 minutes prior to achieving reactor criticality, and b.
At least once per 30 minutes when the reactor is critical and the Reactor Coolant System temperature (T
) is
< 525'F.
W)th K
> 1.0.
ST.
LUCIE - UNIT 1
3/4 1-7 Amendment No.
4
REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATHS -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths and one associated heat tracing circuit shall be OPERABLE:
a.
A flow path from the boric acid makeup tank via either a
boric acid pump or a gravity feed connection and charging pump to the Reactor Coolant System if only the boric acid makeup tank in Specification 3.1.2.7a is OPERABLE, or b.
The flow path from the refueling water tank via either a
charging pump or a high pressure safety injection pump*
to the Reactor Coolant System if only the refueling water tank in Specification 3.1.2.7b is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to OPERABLE status.
SURVEILLANCE RE UIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path is above the temperature limit line shown on Figure 3.1-1 when a flow path from the boric acid makeup tanks is used.
Amendment No. g 9, ~>>
9O 3/4 1-8
(a) the RCS pressure boundary does not exist, or (b) no charging pumps are operable.
In this case all charging pumps shall be disabled, and heatup and cooldown rates shall be limited in accordance with Fig. 3.l-lh.
ST.
LUCIE - UNIT 1
REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION fOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths and one associated heat tracing circuit shall be OPERABLE:
a.
Two flow paths from the boric acid makeup tanks via either a
boric acid pump or a gravity feed connection, and a charging pump to the Reactor Coolant System, and b.
The flow path from the refueling water tank via a charging pump to the Reactor Coolant System.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System 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 make the reactor subcritical within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and borate to a SHUTDOWN MARGIN equivalent to 5t least 2000 pcm at 200'F; restore at least two flow paths to OPERABLE status within the next 7
days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:
a.
At least once per 7 days by ver'ifying that the temperature of the heat traced portion of the flow path from the boric acid makeup tanks is above the temperature limit line shown on Figure 3.1-1.
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
ST.
LUCIE - UNIT 1
3/4 1-10 Amendment No.g 9 8p, g0
REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREHENTS (Continued C.
At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation signal.
ST.
LUCIE - UNIT '1 3/4 1-11 Amendment No. 9 0
REACTIVITY CONTROL SYSTEMS CHARGING PUMP -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or one high pressure safety injection pump* in the boron injection flow path required OPERABLE pursuant to Specifi-cation 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no charging pump or high pressure safety injection pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one of the required pumps is restored to OPERABLE status.
SURVEILLANCE RE UIREMENTS 4.1.2.3 At least one of the above required pumps shall be demonstrated OPERABLE by verifying the charging pump develops a flow rate of greater than or equal to 40 gpm or the high pressure safety injection pump develops a total head of greater than or equal to 2571 ft. when tested pursuant to Specification 4.0.5.
(a) the RCS pressure boundary does not exist, or (b) no charging pumps are operable.
In this case, all char ging pumps shall be disabled and heatup and cooldown rates shall be limited in accordance with Fig. 3.l-lb.
ST.
LUCIE - UNIT 1
3/4 1-12 Amendment No.5 ONE 9O
REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one charging pump OPERABLE, restore at least two charging pumps 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be 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 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE hy verifying that each pump develops a flow rate of greater than or equal to 40 gpm when tested pursuant to Specification 4.0.5.
ST.
LUCIE - UNIT 1
3/4 1-13 Amendment No. 90
REACTIVITY CONTROL SYSTEMS BORIC ACID PUMPS -
SHUTDOWN LIMITING CONDITION fOR OPERATION 3.1.2.5 At least one boric acid pump shall be OPERABLE if only the flow path through the boric acid pump in Specification 3.1.2.la above, is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no boric acid pump OPERABLE as required to complete the flow path of Specification 3.1.2.1a, suspend all operations involving CORE ALTERA-TIONS or positive reactivity changes until at least one boric acid pump is restored to OPERABLE status.
SURVEILLANCE RE UIREMENTS 4.1.2.5 The above required boric acid pump shall he demonstrated OPERABLE by verifying that on recirculation flow, the pump develops a
discharge pressure of > 75 psig when tested pursuant to Specification 4.0.5.
ST.
LUCIE - UNIT 1 3/4 1-14 Amendment No. 90
REACTIVITY CONTROL SYSTEMS BORIC ACID PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 At least the boric acid pump(s) in the boron injection flow path(s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE if the flow path through the boric acid pump in Specification 3.1.2.2a is OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one boric acid pump required for the boron injection flow path(s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid pump 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 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 4.1.2.6 The above required boric acid pumpts) shall be demonstrated OPERABLE by verifying that on recirculation flow, the pump develops a
discharge pressure of > 75 psig when'ested pursuant to Specification 4.0.5.
ST.
LUCIE - UNIT 1
3/4 1-15 Amendment No.
90
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
One boric acid makeup tank and one associated heat tracing circuit with a minimum contained volume of 1660 gallons of 8 weight percent boron.
b.
The refueling water tank with:
l.
A minimum contained volume of 125,000 gallons, 2.
A minimum boron concentration of 1720
- ppm, and 3.
A minimum solution temperature of 40'F.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no borated water sources OPERABLE, suspend all operations involving positive reactivity changes until at least one borated water source
=-is restored to OPERABLE status.
SURVEILLANCE RE UIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
l.
Verifying the boron concentration of the water, 2.
Verifying the water level of the tank, and 3.
Verifying the boric acid makeup tank solution temperature when it is the source of borated water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWT temperature when it is the source of borated water and the site ambient air temperature is ( 40'F.
ST.
LUGIE - UNIT 1
3/4 1-16 Amendment No. 27
I
~
I I ~
REACTOR COOLANT SYSTEM SAFETY VALVES -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE with a liftsetting of 2500 PSIA + 1%.
APPLICABILITY:
MODES 4 and 5.
ACTION:
With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.
SURVEILLANCE RE UIREMENTS 4.4.'2 No additional Surveillance Requirements other than those required by Specification 4.0.5.
ST.
LUCIE - UNIT 1
3/4 4-2 Amendment No.
90
REACTOR COOLANT SYSTEM SAFETY VALVES - OPERATING
, LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 PSIA +
1%.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.4.3 No additional Surveillance Requirements other than those required by Specifj'cation 4.0.5.
ST.
LUCIE - UNIT 1
3/4 4-3 Amendment No.
90
REACTOR COOLANT SYSTEM PRESSURIZER.
LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:
a.
A maximum heatup of 100'F in any one hour period, b.
A maximum cooldown of 200'F in any one hour period, and c.
A maximum Reactor Coolant System spray water temperature differential of 350'F.
APPLICABILITY: At all times.
ACTION'ith the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an analysis to determine the effects of the out-of-limit con-dition on the fracture toughness properties of the pressurizer; deter-mine that the pressurizer remains acceptable for continued operation 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 reduce the pressurizer pressure to less than 500 psia 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 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.
The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation.
ST.
LUCIE - UNIT 1
3/4 4-25
REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL'NTEGRITY ASME CODE CLASS 1, 2, AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1,
2 and 3 components (except steam generator tubes) shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY: Al 1 MODES.
ACTION:
a ~
b.
c, With the structural integrity of any ASME Code Class 1
component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
With the structural integrity of any ASME Code Class 2
component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.
With the structural integrity of any ASME Code Class 3
component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.10.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
ST.
LUGIE - UNIT 1
3/4 4-26 Amendment No. gP, 90
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued OELETEO ST.
LUCIE - UNIT 1
3/4 4-27 Amendment No.
90
TABLE 4.4-6 INSERVICE INSPECTION PROGRAM - SAFETY CLASS 1
COMPONENTS SECTION 1.
REACTOR VESSEL AND CLOSURE HEAD DELETED
TABLE 4.4-6 Cont'd)
SECTION 1.
REACTOR VESSEL AND CLOSURE HEAD DELETED
TABLE 4.4-6 (Cont'd)
SECTION 1.
REACTOR VESSEL AND CLOSURE HEAD DELETED
TABLE 4.4-6 Cont'd SECTION 2.
PRESSURIZER DELETED
TABLE 4.4-6 (Cont'd)
SECTION 2.
PRESSURIZER DELETED
TABLE 4.4-6 (Cont'd)
SECTION 3.
STEAM GENERATORS DELETED
TABLE 4.4-6 (Cont'd)
SECTION 4.
PIPING PRESSURE BOUNDARY DELETED
TABLE 4.4-6 (Cont'd)
SECTION 5.
PUMP PRESSURE BOUNDARY AND PUMP FLYL(HEELS DELETED
TABLE 4.4-6 (Cont'd)
SECTION 6.
VALVE PRESSURE BOUNDARY DELETED
REACTOR COOLANT SYSTEM SAFETY CLASS 2
COMPONENTS r
LIMITING CONDITION FOR OPERATION DELETED ST.
LUCRE - UNIT 1 3/4 4-37 Amendment No. g9, 90
REACTOR COOLANT SYSTEt'I SURVEIL~LANCE RE UIREHENTS Continued OELETED ST.
LUGIE - UNIT 1
3/4 4-38 Amendment No.
90
TABLE 4.4-7 INSERVICE INSPECTION PROGRAM - SAFETY CLASS 2
COMPONENTS SECTION C1.
PRESSURE VESSELS DELETED
TABLE 4.4-7 (Cont'd)
SECTION C1.
PRESSURE VESSELS DELETED
TABLE 4.4-7 (Cont'd)
SECTION C1.
PRESSURE VESSELS DELETED
TABLE 4.4-7 Cont'd SECTION C2.
PIPING DELETED
TABLE 4.4-7 (Cont'd}
SECTION C2.
PIPING DELETED
TABLE 4.4-7 (Cont'd SECTION C2.
PIPING DELETED
TABLE 4.4-7 (Cont'd)
SECTION C2.
PIPING DELETED
TABLE 4.4-7 (Cont'd)
SECTION C2.
PIPING DELETED
TABLE 4.4-7 (Cont'd)
SECTION C2 PIPING DELETED
TABLE 4.4-7 (Cont'd)
SECTION C3.
PUMPS DELETED
TABLE 4.4-7 (Cont'd)
SECTION C3.
PUMPS DELETED
TABLE 4.4'-7 Cont'd SECTION C4.
VALVES IVl CD DELETED fD fD C+,
O
TABLE 4.4-7 (Cont'd)
SECTION C4.
VALVES DELETED
TABLE 4.4-7 (Cont'd)
SECTION C4.
VALVES DELETED
REACTOR COOLANT SYSTEM SAFETY CL'ASS 3
COMPONENTS LIMITINCi CONDITION FOR OPERATION DElETED ST.
LUCIE - UNIT 1 3/4 4-53 Ppnendment No. Q,,
9O
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued)
DELETED ST.
LUCIE -. UNIT 1 3/4 4-.54 Amendment No.
90
TABLE 4.4-8 INSERVICE INSPECTION PROGRAH - SAFETY CLASS 3
COMPONENTS DELETED
REACTOR COOLANT SYSTEM 3.4.11 DELETED ST.
LUGIE - UNIT 1 3/4 4-56 AMENDMENT NO. 80
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T
> 325'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each sub-system comprised of:
a.
One OPERABLE high-pressure safety injection (HPSI) pump (one ECCS subsystem shall include HPSI pump A and the second ECCS subsystem shall include either HPSI pump B or C),
b.
One OPERABLE low-pressure safety injection pump, and c.
An independent, OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
APPLICABILITY:
MODES 1, 2'and 3".
ACTION:
a
~
With one ECCS subsystem inoperable, restore the inoperable subsystem 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 />.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90, days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
- Wit pressurizer pressure 1750 psia.
ST.
LUGIE - UNIT 1 3/4 5-3 Amendment No.
28
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number 1.
V-3659 2.
V-3660 Val.ve Function 1.
Mini-flow isolation 2.
Mini-flow isolation Valve Position l.
Open 2.
Open b.
At least once per 31 days by:
1.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
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 LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when the Reactor
~ Coolant System pressure is above 300 psig.
2.
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.
ST.
LUGIE - UNIT 1 3/4 5<<4 Amendment No.
90
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RK UIREMENTS Continued e.
At least once per 18 months, dur ing shutdown, by:
l.
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation Signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Signal; a.
High-Pressure Safety Injection pump.
b.
Low-Pressure Safety Injection pump.
3.
Verifying on a
Sump Recirculation Actuation Test
- Signal, the containment sump isolation valves.open and the recirculation valve to the refueling water tank closed.
f.
By verifying that each of the following pumps develops the specified total developed head on recirculation flow when tested pursuant to Specification 4.0.5:
1.
High-Pressure Safety Injection pumps:
greater than or equal to 2571 ft.
2.
Low-Pressure Safety Injection pumps:
greater than or equal to 350 ft.
ST.
LUCIE -.. UNIT 1
3/4 5-5 Amendment No. 25, 90
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued)
THIS PAGE INTENTIONALLYLEFT BLANK ST.
LUCIE - UNIT 1
3/4 5-6 Amendment No.
'90.
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a
Containment Spray Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.
APPLICABILITY:
MODES 1, 2 and 3*.
ACTION'
~
b.
With one containment spray system inoperable and all four containment fan coolers OPERABLE, restore the inoperable spray system to OPERABLE status within 30 days 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 one containment spray system inoperable and one containment fan cooler inoperable, restore either the inoperable spray system or the inoperable fan cooler 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 />.
SURVEILLANCE RE UIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is positioned to take suction from the RWT on a Containment Pressure -- High High test signal.
b.
By verifying that on recirculation'low, each spray pump develops a discharge pressure of > 200 psig, when tested pursuant to Specification 4.0.'5.
Applicable when pressurizer pressure is o
1750 psia.
ST.
LUCIE - UNIT 1
3/4 6-15 Amendment No. 90
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued c.
At least once per 18 months, during shutdown, by:
l.
Verifying that each automatic valve in the flow path actuates to its correct position on a
CSAS test signal.
2.
Verifying that each spray pump starts automatically on a
CSAS test signal.
3.
Verifying that upon a recirculation actuation signal, the containment sump isolation valves open and that a
recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.
d.
At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
ST, LUCIE - UNIT 1
3/4 6-16 Amendment No.
90
CONTAINMEN SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 Four containment fan coolers shall be OPERABLE.
PPLICABILITY:
MODES 1, 2 and 3.
CTION:
a.
With one containment fan cooler inoperable and both containment spray systems OPERABLE, restore the inoperable fan cooler to OPERABLE status within 30 days 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 />.
b.
With one containment fan cooler inoperable and one containment spray system inoperable, restore either the inoperable fan cooler or the inoperable spray system 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 />.
SURVEILLANCE RE UIREMENTS 4.6.2.3 Each containment fan cooler shall be demonstrated OPERABLE at least once per 31 days on a STAGGERED TEST BASIS by:
a.
Starting each unit from the control room, b.
Verifying that each unit operates for at least 15 minutes, and c.
Verifying a cooling water flow rate of > 1200 gpm to each cooling unit.
ST.
LUGIE - UNIT 1
3/4 6-17 Amendment No.
26
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve(s) specified in Table 3.6-2 inoperable, either:
a.
Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
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 4.6.3.1.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated
- actuator, control or power circuit by..performance of the cycling test, and verification of isolation ti'me.
ST.
LUCIE - UNIT 1
3/4 6-18 wiiendment No.
9O
CONTAINMENT SYSTEMS SURVEILLANCE PE UIREMENTS (Continued
,gVt
~
4.6.3.1.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on a Containment Isolation test signal, and/or SIAS test signal, each isolation valve actuates to its isolation position.
4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-2 shall be determined to be within its limits when tested pursuant to Specification 4.0.5.
ST.
LUCIE - UNIT 1
3/4 6-19 Amendment No.
90
TABLE 3.6-2 CONTAINMENT ISOLATION VALVES ln m
Ch I
C)
Valve Ta Number)
A.
CONTAINMENT ISOLATION 1.
I-FCV-25-4,5 I
2.
I-FCV-25-2,3 3.
I-MV-15-1 4.
I-MV-18-1 5.
V-6741 6.
I-HCV-14-1 5 7 7.
I-HCV-14-6 5 2 8.
V-2515,251 6 9.
V-520055203 10.
V-5201,5204 11.
V-5202,5205 12.
V-6554,6555 13.
I-LCV-07-11A,118 Penetration Number 10 ll 7
9 14 23 26 28 29 29 31 42 Function Containment purge air exhaust, CIS Containment purge supply, CIS Primary makeup water, CIS Instrument air supply, CIS Nitrogen supply to safety injection
- tanks, CIS Reactor coolant pump cooling water
- supply, SIAS Reactor coolant pump cooling water
- return, SIAS Letdown line, CIS, SIAS Reactor coolant sample, CIS Pressurizer surge line sample, CIS Pressurizer steam space
- sample, CIS Containment vent header, CIS Reactor cavity sump pump discharge, CIS Testable During Plant 0 eration No Yes No Yes No No No Yes Yes Yes Yes Yes Isolation Time Sec 5
5 19 28 5
5 5
5 5
5 10 14.
V-6301,6302 15.
V-2505 16.
I-SE-Ol -1 43 44 44 Reactor drain tank pump suction, CIS Reactor coolant pump controlled
- bleedoff, CIS Reactor coolant pump controlled
- bleedoff, CIS Yes No No
CONTAINMBlT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 3.
Verifying during a recombiner system functional test that the heater sheath temperature increases to
> 1200'F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and is maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.
Verifying the 'integrity of the heater electrical circuits by performing a continuity and resistance to ground test immediately following the above required functional test.
The resistance to ground for any heater phase shall be
> 10,000 ohms.
ST.
LUGIE - UNIT 1
3/4 6-25
CONTAINMENT SYSTEMS 3/4.6.5 VACUUM RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.6.5.1 The containment vessel to annulus vacuum relief valves shall be OPERABLE with an actuation setpoint of,less than or equal to 2.25
+ 0.25 inches Water Gauge differential.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one containment vessel to annulus vacuum relief valve inoperable, restore the valve to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 4.6.5.1 No additional Surveillance Requirements other than those required by Specification 4.0.5 and at least once per 3 years verify that the vacuum relief valves open fully within 8 seconds at 2.25
+ 0.25 inches-Water Gauge differential.
ST.
LUCIE - UNIT 1
3/4 6-26 Amendment No.
9O
e 3/4.7 PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE SAFETY VAL'VES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as specified in Table 4.7-1.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
a.
With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise,,
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 />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
ST.
LUGIE - UNIT 1 3/4 7-1 Amendment No.
90
TABLE 3.7-1 MAXIMUMALLOWABLE POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE ST LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS Maximum Number of Inoperable Safety Valves on An 0 eratin Steam Generator Maximum Allowable Power Level-High Trip Setpoint Percent of RATED THERMAL POWER 93.2 79.8 66.5
TABLE 4.7-1 STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER Header A
Header B
LIFT SETTING 4 lX ORIFICE SIZ a.
8201 b.
8202 c.
8203 d.
8204 e.
8209 8210 g.
8211 h.
8212 8205 8206 8207 8208 8213 8214 8215 8216 1000 psia 1000 psia 1000 psia 1000 psia 1040 psia 1040 psia 1040 psia 1040 psia 16 in. 2 16 in. 2 16 in. 2 16 in.
~
2 16 in.
16 in. 2 16 in.
16 in. 2
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two motor driven feedwater
- pumps, and b.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven pumps and one capable of being powered by an OPERABLE steam supply system) 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 />.
SURVEILLANCE RE UIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a 0 At least once per 31 days by:
l.
Verifying that each motor driven pump-develops a
discharge pressure of ) 1342 psig on recirculation flow.
2.
Verifying that the steam turbine driven pump develops a discharge pressure of ) 1342 psig on recirculation flow.*
"lfhen not in MODES 1, 2 or 3, this surveillance shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering MODE 3 and prior to entering MODE 2.
ST.
LUCIE - UNIT 1
3/4 7-4 Amendment No.
8$,
90
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 3.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown by:
l.
Verifying that each automatic valve in the flowpath actuates to its correct position upon receipt of the Auto Start actuation test signal.
2.
Verifying that each auxiliary feedwater pump starts automatically as designed upon receipt of the Auto Start actuation test signal.
ST.
LUC IE - UNIT 1
3/4 7-5 Amendment No. g7, 90
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank shall be OPERABLE with a minimum contained volume of 116,000 gallons.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With the condensate storage tank inoperable, restore the condensate storage tank to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 I 4.7.1.3 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the water level.
ST.
LUCIE - UNIT 1
3/4 7-6
PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
MODE 1
MODES 2
and 3
With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, 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 one main steam line isolation valve inoperable, sub-sequent operation in MODES 1, 2 or 3 may proceed after the inoperable valve is restored to OPERABLE status or the isolation valve is maintained closed; otherwise, 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 />.
SURVEILLANCE RE UIREMENTS 4.7.1.5 "Each main steam line isolation valve that is open shall be demonstrated OPERABLE by verifying full closure within 6.0 seconds when tested pursuant to Specification 4.0.5.
ST.
LUCIE - UNIT 1
3/4 7-9 Amendment No.
90
TKIS PAGE LEFT INTENTIONALLY BLANK ST.
L'UCIE - UNIT 1 3/4 7-10 Amendment No. 86
PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2.1 The temperatures of both the primary and secondary coolants in the steam generators shall be
> 70'F when the pressure of either cool-ant in the steam generator is
> 200 psig.
APPLICABILITY:
ALL MODES.
ACTION:
With the requirements of the above specification not satisfied:
a.
Reduce the steam generator pressure of the applicable side to
< 200 psig within 30 minutes, and b.
Perform an analysis to determine the effect of the overpres-surization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200'F.
SURVEILLANCE RE UIREMENTS 4.7.2.1 The pressure in each side of the steam generators shall be determined to be ( 200 psig at least once per hour when the temperature of ei ther the primary or secondary coolant in the steam generators is
< 700F.
ST.
LUCIE - UNIT 1
3/4 7-13
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR'PERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one component cooling water loop OPERABLE, restore at least two 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 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 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection Actuation Signal.
ST.
LUCIE - UNIT 1
3/4 7-14 Amendment No.
gO
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued THIS PAGE INTENTIONALLY LEFT BLANK ST.
LUGIE - UNIT 1
3/4 7-15 Amendment No.
90
PLANT SYSTEMS 3/4.7.4 INTAKE COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.'t least two independent intake cooling water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one intake cooling water loop OPERABLE, restore at least two 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 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 4.7.4.1 At least two intake cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown by:verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection Actuation signal.
ST.
LUCIE - UNIT 1
3/4 7-16 Amendment No.
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued THIS PAGE INTENTIONALLY LEFT BLANK ST.
LUCIE - UNIT 1
3/4 7-17 Amendment No.
90
PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5.1 The ultimate heat sink shall be OPEPABLE with:
a.
Cooling water from the Atlantic Ocean providing a water level above
-10.5 feet elevation, Mean Low Water, at the plant intake structure, and b,
Two OPERABLE valves in the barrier dam between Big Mud Creek and the intake structure.
APPLICABILITY: At al 1 times.
ACTION:
a.
With the water level requirement of the above Specification not satisfied, be in at least HOT STANDBY within six hours and provide cooling water from Big Mud Creek within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With one isolation valve in the barrier dam between Big Mud CreeM and the intake structure inoperable, restore the inoperable valve 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, within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, install a temporary flow barrier and open the barrier dam isola-tion valve.
The availability of the onsite equipment capable of removing the barrier shall be verified at least once per seven days thereafter.
c.
With both of the isolation valves in the barrier dam between the in-take structure and Big Mud Creek inoperable, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either:
1)
Install both 'temporary flow barriers and manually open both barrier dam isolation valves.
The availability of the onsite equipment capable of removing the barriers shall be verified at least once per seven days thereafter, or 2)
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 />.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE VIREMENTS 4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water level to be within limits.
4.7.5.1.2 The isolation valves in the barrier dam between the intake structure and Big Mud Creek shall be demonstrated OPERABLE at least once per six months by cycling each valve through at least one complete cycle of full travel.
ST.
LUCIE - UNIT 1
3/4 7-18 Amendment No.
54
APPLICABILITY Y lt8 BASES (Continued 4.0.5 This specification ensures that inservice inspection of ASME Code Class 1,
2 and 3 components and inservice testing of ASME Code Class 1,
2 and 3
pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda.
as required by 10 CFR 50.55a.
Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any, ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.
For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested
.up to one week after return to normal operation.
And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable.of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
ST.
LUCIE - UNIT 1
B 3/4"0'-'3 Amendment No.
90
3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above the DNBR limit duri ng all normal operations and anticipated transients.
In MODES 1
and 2 with one reactor coolant loop not in operation, this specifica-tion requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.
In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reac-tor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either shutdown cooling or RCS) be OPERABLE.
In MODE 5 with r eactor coolant loops not filled, a single shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failur e considerations and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling loops be OPERABLE.
The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.
The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.
The restrictions on starting a Reactor Coolant Pump are provided to prevent RCS pressure transients, caused by energy additions from the secondary
- system, which could exceed the limits of Appendix G to 10 CFR 50.
The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the Reactor Coolant Pumps to when the secondary water temperature of each steam generator is less than 30'F above each of the Reactor Coolant System cold leg temperatures.
3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressur'izer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.
Each safety valve is designed to relieve 2 'x 10 lbs per hour of saturated steam at the valve setpoint.
The relief capacity of a single safety valve is adequate to relieve any. over-pressure condition which could occur during shutdown.
In the event that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS. provides overpr essure relief capability and will.prevent RCS overpressuriza-tion.
ST.
LUCIE - UNIT 1
B 3/4 4-1 Amendment No. Q, g'.
N'81
REACTOR COOLANT SYSTEM BASES 3/4.4.2 and 3/4.4.3 SAFETY VALVES (Continued)
Ouring operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.
The combined relief capacity of these valves is sufficient to limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATEO THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e.,
no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.
Oemonstration of the safety valves'ift setti ngs will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
3/4.4.4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydrauli-cally solid system and is capable of accommodating pressure surges during opera-tion.
The steam bubble also protects the pressurizer code safety valves and power operated relief valve against water relief.
The power operated relief valve and steam bubble function to relieve RCS pressure during all design transients.
Operation of the power operated relief valve in conjunction with a reactor trip on a Pressurizer-Pressure-High signal minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.
The required pressurizer heater capacity is capable of maintaining natural circulation sub-cooling.
Operability of the heaters, which are powered by a diesel generator
- bus, ensures ability to maintain pressure control even with loss of offsite power.
3 4.4.5 STEAM GENERATORS One OPERABLE steam generator provides sufficient heat removal capability to remove decay heat after a reactor shutdown.
The requirement for two steam generators capable of removing decay heat, combined with the requirements of Specifications 3.7.1.1, 3.7.1.2 and 3.7.1.3 ensures adequate decay heat removal capabilities for RCS temperatures greater than 325'F if one steam generator becomes inoperable due to single failure considerations.
Below 325'F, decay heat is removed by the shutdown cooling system.
The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision l.
Inservice inspec-tion of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical demage or progressive degradation due to design, manufacturing errors, or in-service conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
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LUCIE - UNIT 1
8-3/4 4-2 Amendment No. gg, g7, 5 g>
gO
DELETED ST.
LUCIE - UNIT 1 B 3/4 4-11 Amendment No. 81
REACTOR COOLANT SYSTEM BASES for piping, pumps and valves.
Below this temperature, the system pressure must be limited to a maximum of 20% of the system's hydrostatic test pressure of 3125 psia.
The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4-5 to assure compliance with the requirements of Appendix H
to 10 CFR Part 50.
The limiations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fati-gue analysis performed in accordance with the ASME Code requirements.
3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection program for ASME Code Class 1,
2 and 3
components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.
This program is in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).
Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1971 Edition and Addenda through Winter 1972.
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LUGIE - UNIT 1
B.,3(4 4~12 Amendment No.
90
REACTOR COOLANT SYSTEM BASES DELETED ST.
LUCRE UNIT 1
8 3/4. 4-13 Amendment No gg.
90
REACTOR COOLANT SYSTEM BASES 3/4.4.12 PORV BLOCK VALVES The opening of the Power Operated Relief Valves fulfills no safety related function.
The electronic controls of the PORVs must be maintained OPERABLE to ensure satisfaction of Specifications 4.5.l.d.l and 4.5.2.d.l.
Since it is impractical and undesirable to actually open the PORVs to demonstrate reclosing, it becomes necessary to verify operability of the PORV Block Valves to ensure the capability to isolate a malfunctioning PORV.
ST LUCIE - UNIT 1
B 3/4 4-14 Amendment No. 37