ML17229A462

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Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8
ML17229A462
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 08/22/1997
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A461 List:
References
NUDOCS 9709030306
Download: ML17229A462 (49)
v • d • e


Text

St. Lucie Units 1 and 2 Docket No. 50-335 and 50-389 L-97-215 Attachment 3A ATTACHMENT3A PROPOSED LICENSE AMENDMENT-UNIT 1 PROPOSED TECHNICAL SPECIFICATION PAGES 3/4 0-2 3/4 0-3 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-15 3/4 4-2 3/4 4-3 3/4 5-5 3/4 6-15a 3/4 6-19 3/4 6-26 3/4 7-1 3/4 7-9 B 3/4 0-8 B 3/4 4-2 Insert (Page 6-15c) 970903030b 970822 PDR ADOCK 05000335 ) I P PDR

71

) ...APPLICABILITY URYEILLAHCE REOUIRHEHTS 4.Q.l Surveillance Requirements shall bc applicable during the OPERATIONAL

.<<(ODES or other conditions specified for individual Lfeftfng Conditions for Operation unless othcrwist stated in an indivfdu41 Surveillance Rcqufr~nt.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval- with a maximum allowable extension not to exceed 25K of the specified surveillance interval.

~.0.3 Failure to perform a Surveillance Requfiement within'h>> alloxed

~urvefllance interval, defined by Specification 4.0.2, shall constftute noncompliance with the OPERABILITY requirements for a Lfmftfng Condition for Operation. The time limits of the ACTION requirements are applfcablc at the time it fs identiffed that a Surveillance Requfrenent has not (ken 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 survcfllancc when the allowable outage tfsc 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 />. Survefllance Rcqufremcnts do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL NODE or other specfffed applicability condition shall not be made unless thc Surveillance Requirement(s) assocfated xfth the Limiting Condition for Operation have been performed wfthfn the

-tatcd surveillance interval or as otherwise specfffed. This provfsfon

. na11 not prevent passage through or to OPERATIONAL %0ES as required to comply xf th ACTION requirements.

4.0.5 Surveillance Requfrcments for fnservfce inspection and testing of ASIDE Code Class 1, 2 and 3 cowpone shal bemgp fcable is follows:

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a. Inservfce inspection o o e Class 1, 2 a<d 3 components and f-nsem4ceWe~g-ASNE-Gode shall be perforsed fn accordance xfth Sectfon XI of the ASHE Boiler and Pressure Vessel Code and applfcable Addenda as required

~ q~~ll~d-by 10 CFR 50, Sectfon 50.55a(g), except where specific xrftten relief has been granted by the Coamfssfon pursuant to 10 CFR 50, Section 50.55a(g) (6) (f ).

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%%)5()b LUC IE - UNIT 1 3/4 0-2 Amendment Ho. g$ ,$ 8.~~ >>

l APPLICABIL TY SURVEILLANC R UIREHENTS Continued 4.0.5 (Continued)

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-Semiannual-ly-or-ever'y-6-months Yearly-or-annually tl as~nc~er p

At-least-once-per 7-clays east once-pea-3k-days 91-dw.

N4-days At-1 east-once-per-366-days

c. The-pr ovations-of Speci-f ication-4AM-are-appliable-to-the-abeve requ+red-frequ najss for perfoaning inservic~spectio~ndMeating

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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. LUCIE UNIT 1 3/4 0-3 Amendment No. 56, 118

3.1.2.3 At least one charging pump or high pressure safety injection pump in the boron injection fiow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

MODES 5 and 6.

With no charging pump or high pressure safety injection pump OPERABLE, suspend all operations involving CORE ALTERATlONS or positive reactivity changes until at least one of the required pumps is restored to OPERABLE status.

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 ecification-4-.6&

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The flow path from the RWT to the RCS via a single HPSI pump shall be established only if:

(a) the RCS pressure boundary does not exist, or (b) no charging pumps are operable. ln the latter case: 1) all charging pumps shall be disabled; 2) heatup and cooldown rates shall be limited in accordance with Figure 3.1-1b; and 3) at RCS temperatures below 115'F, any two of the following valves in the operable HPSI header shall be verified closed and have their power removed:

HCV-3616 HCV-3617 HCV-3626 HCV-3627 HCV-3636 HCV-3637 HCV-3646 HCV-3647 ST. LUCIE - UNIT 1 3/4 1-12 Amendment No. 66, 8+, 99.

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88 REACTIYITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging C

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 />.

SURYEILLANCE RE UIREMENTS 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE hy verifying that each pump develops flow rate of greater than or equal to 40 gpm when tested pursuant to SpecA-fi~on~9-.5.

gg< +~evY/c~ 7ESgi~+ P~gv>m ST. LUCIE - UNIT 1 3/4 1-13 Amendment No. 90

89 REACTIVITY CONTROL SYSTEMS BORIC ACID PUMPS - SHUTDOMN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one boric acid pump shall be OPERABLE if only the low path through the boric acid pump in Soecification 3.1.2.1a above, is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

Mith no boric acid pump OPERABLE as required to complete the flow path of Specification 3.1.2.la, suspend all operations involving CORE ALTERA-TIONS or positive reactivity changes until at least one boric acid oump 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 Spec~f4cat4on

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ST. LUCIE - UNIT 1 3/4 1-14 Amendment No. 90

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 REOUIREMENTS vacua 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 tested pursuant to 'Spec-i-f H~n-7~zr /eS~+

ST. LUCIE - UNIT 1 3/4 1-15 Amendment No. gO

187 REACTOR COOLANT SYSTEM SAFETY VALVES - SHUTDOMN LIMITING CONDITION FOR OPERATION 3.4.2 lift settingof one pressurizer code safety valve shall A minimum be OPERABLE with a of 2500 PSIA + lX.

APPLICABILITY: MODES 4 and 5.

ACTION:

With no pressurizer code safety valve OPERABLE, itanediately 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 Speci-%~4-.ien-4-.6M.

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ST. LUCIE - UNIT 1 3/4 4-2 Amendment No. 90

' I 188 REACTOR COOLANT SYSTEM SAFETY VALVES - OPERATING LIMITING CONOITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall setting of 2500 PSIA + lX.

be OPERABLE with a lift APPLICABILITY: MOOES 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 SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE VIREMENTS b~ea+f4cat-e'en-4-.B-.G.

4.4.3 No additional Surveillance Requirements other than those required

+%<V('C< /Mori+ jCVAM ST. LUCIE - VNIT 1 3/4 4-3 Amendment No. 9O

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256 ,

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RK MIREMENTS (Continued)

e. 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 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 Speci-fica4-ion-4-.eW: 7fie M~V/C< fMIIQ i <p+
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

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 flow, each spray pujtp develops a discharge pressure of > 200 psig, when tested pursuant to Spem4im&en-4-;0-.5:

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ST. LUC IE - UNIT 1 3/4 6-15a Amendment No. >3>

CONTAINMENT SYST SURVEILLANCE REQUIREMENTS continued 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUEl ING 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 containment isolation valve shall be determined to be within its limits when tested pursuant to Speeifieatiert-4-.0-.5.

ST. LUCIE - UNIT 1 3I4 6-19 Amendment No. QO

288 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.?5 inches Mater 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 hours and in COLD SHUTDOWN within the following 30 hours.

SURVEILLANCE RE UIREMENTS 4.6.5.1 No additional Surveillance Requirements other than those required by Speci-f4c~M40-.$ and at least once per 3 years verify that the vacuum relief valves open fully within 8 seconds at 2.25 + 0.25 inches Mater Gauge differential.

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ST. LUCIE - UNIT 1 3/4 6-26 Amendment No. 90

~ 4 295 I

I 3/4.7 PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall 4

be OPERABLE with lift settings as specified in Table 4.7 APPLICABILITY: MODES 1, Z 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 Sp Jigger (/Ic& 7~+~<+

ST. LUCIE - UNIT 1 3/4 7-1 Amendment No. gO

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3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

~APP I I LITT IAOOIT I I 3 3.

ACTION

'I HOOE I - 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 STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

NOOES 2 - With one or both main steam isolation valve(s) inoperable, and 3 subsequent operation in HOOES 2 or 3 may proceed provided the iso1ation valve(s) is (are) maintained closed. 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 COLO SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE. REQUIREMENTS R R % % W R R R R % R R R Q 0 R R X XW % R Q R R XD Q % Q ÃX % X XR XR X% '+ 0 '+ > > 'R R X R 'R 'R Ã R % X KR R R R 0 R X R R Q 'S R 'S R R 4.7.1.5 Each main steam line isolation valve that i's open shall be demonstrated OPERABLE by verifying full closure within 6.0 seconds when tested pursuant to Spec4fkca44on-4-.4-.S.

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ST. LUCIE - UNIT 1 3/4 7-9 Amendment No. 80,

418 APPLICABILITY BASES Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability s.atement. The purpose of this specification is to ensure that system and component OPEPABILITY requirements or parameter limits are met before entry into a MOOE or condition

'for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MOOES or other specified conditions associated with plant shutdown as well as startuo.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage. d Nhen a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would la placing the facility in a lower MOOE of operation.

4.0.5 This specification ensures that inservice inspection of ASME Class 1, 2 and 3 components aA d-d 3-pumps-and-vaWes we'll be performed in accordance with a periodically updated d~

version of Section XI of the ASh(E Boiler and Pressure Vessel Code and Addenda.

as required by 10 CFR 50.55a. Relief from any of the above requirements has Code been provided in writing by the Commission and is not a part of these Technical

,Specifications.

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I ST. LUG IE - UNIT 1 0 3/4 O-G Amendment No. gB

431 REACTOR COOLANT SYSTEM BASES 3/4.4.2 and 3/4.4.3 SAFETY VALVES (Conti'nued)

During 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 RATED THERMAL POMER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is .aken 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.

Demonstration

~ME-8 3/4.4.4 H

PRESSURIZER

~6 of the safety valves'ift settings will occur only during h

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 pr essurizer 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 Requir ements for inspection of the steam generator tubes ensure that the structural integr ity 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.

ST. LUCIE - UNIT 1 B-3/4 4-2 Amendment No. gS, 87, 5 if~ gO

St. Lucie Units 1 and 2 Docket No. 50-335 and 50-389 L-97-215 Attachment 3A TS Page 6-15c.

INSERT:

6.8.4.i. Inservice Testin Pro ram This program provides controls for inservice testing of ASME Code Class 1,2, and 3 components (pumps and valves). The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code* and applicable addenda as follows:

ASME Boiler and Pressure Vessel Code"'nd applicable Addenda terminology for Required Frequencies for performing inservice testin activities inservice testin activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice testing activities;
c. The provisions of Specification 4.0.3 are applicable to inservice testing activities; and
d. Nothing in the ASME Boiler and Pressure Vessel Code* shall be construed to supersede the requirements of any technical specification.

Where ASME Boiler and Pressure Vessel Code is referenced it also refers to the applicable portions of ASME/ANSI OM-Code, Operation and Maintenance of Nuclear Power Plants, with applicable addenda, to the extent it is referenced in the Code.

l~

St. Lucie Units 1 and 2 Docket No. 50-335 and 50-389 L-97-215 Attachment 3B ATTACHMENT3B PROPOSED LICENSE AMENDMENT-UNIT 2 PROPOSED TECHNICAL SPECIFICATION PAGES 3/4 0-2 3/4 0-3 3/4 1-9 3/4 1-10 3/4 1-11 3/4 1-12 3/4 4-7 3/4 4-8 3/4 4-36 3/4 5-5 3/4 6-15a 3/4 6-17 3/4 6-20 3/4 6-26 3/4 7-1 3/4 7-9 3/4,7-10 B 3/4 0-6 B 3/4 4-2 Insert (Page 6-15c)

APPL I CAB IL ITY SURVEILLANCE REOUIRERENTS 4.0.l Surveillance Requirements shall be applicable during the OPERATIONAL HQOES or other condftfons specified for <ndividual Lfmfting Conditions for Qperatfon unless otherwise stated in an indfvfdual Survefllanca Requirement.

4.0.2 Each SurveHlanca Requfrement shall ba performed within the specified surveillance interval wfth a maxfmum allowable extension not to exceed 25%

of the specfffed surveillance fnterval.

4.0.3 Fai1ure to perform a Surveillance Requfremont within the allowed surv fllance interval, deffned by Specfficatfon 4.0.2, shall constitute noncomplfance with the OPEAA8ILITY requirements for a Lfmftfng Conditfon for Operatfon. The time limits of the ACTION requiranents are app1fcable at the tfme ft fs fdentiffed that a Survefllanca Requfreaant has not been performed. The ACTION requfrements 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 survo~"llance when the allowable outage tfma lfmfts of the ACTION requfrements are lass than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Survefllance Requirements do not have to be performed on inoparable equfpment.

4.0.4 Entry into an OPERATIONAL HOOE or other specfffed condftion shall not be made unless the Survafllance Pequfrement(s) assocfatad with the Limftfng Condftfon for Operatfon have been performed wfthfn'he stated survefllance interval or as otherwfse specified. Thfs provfsfon shall not prevent passage through or to OPERATIONAL NOES as requfred to comply with ACTION requfrements.

4.0.6 Surveillance Requirements fot fnservfca inspection and testing of ASNE Code Class 1, 2 and 3 componen hal a applfcab1e as follows:

G)Z Ns w a.

I ~

Inservfce fnspectfon of t~4 I-AEAE-A ~A+E E o e Class 1, 2 and 3 components and I E I be performed fn accordance with Sectfon XI of the ASIDE Bofler and Pressure Vessel Code and applfcablt Addenda as requfred by 10 CFR 50, I II Sectfon 60.55a(g), except where specific written rolfef has been granted by the Commfssfon pursuant to 10 CFR 60, Sectfon-

'0.55a(g}(6)(f).

b Suave-f-1&ac eel-f4ad ie-See44on-X~~he-ASNE-Bo-Rer

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$o44o~n-4hese-Teehn4eal-Spe@444caMons AEE AEII~

md-Pmssm e-VeeeH-6ode-and-ap@4oabl=e-Addenda-fmMhe-4'.-vie 4esyec'Men-and

  • E~WEA~AI'A ST. LUCIE - UNIT 2 3(4 0-2

APPLICABILITY SURVEILLANCE RE UIRENENTS Continued) 4.0.5 (Continued)

Ve~Gede-and-ap~

ectAen-aa n-and-4es4+ag s

He Ma4annu C. p@-i~bke-~4~>eve requi-red-A equen er4omm~ ~es4~g QRS're.b

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. LUCIE " UNIT 2 3/4 0"3

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - 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 Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no charging pump or high pressure safety injection pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS 4.1.2.3 At least the above required pump 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 develo s a total head of greater than or equal to 2854 ft when tested pursuant to SpeeMh~n-4-.0-.6.

fhe. juservrce tati~ @~<+~

ST. LUCIE - UNIT 2 3/4 1-9

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 at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3000 pcm at 290'F 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 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 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying that each pump develops a flow rate of greater th n equal to 40 gpm when tested pursuant to SpecA44aa><n-4-.0-.5 // 7-77I ~ASH"U/CC ~ /Q Q~

QUERY 4.1.2.4.2 At least once per 18 months verify that each charging pump s automatically on an SIAS test signal.

ST. LUCIE " UNIT 2 3/4 1-10 Amendment No. 8,25

REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one boric acid makeup pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if only the flow path through the boric acid pump in Specification 3.1.2.la. is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

With-no boric acid makeup pump OPERABLE as required to complete the flow path of Specification 3.1.2.la., suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS 4.1.2.5 The above required boric acid makeup pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of greater than or equal to 90 psig when tested pursuant to+Spe~~n~e-.5.

We MuS<rfffC~ r~T~g 7npmm ST. LUCIE " UNIT 2 3/4 1-11

REACTIVITY CONTROL SYSTENS BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 At least the boric acid makeup pump(s) in the boron "infection flow path(s) required OPERABLE pursuant to Specification 3.1.2.2 shall be OPERABLE and capable of being powered fma an OPERABLE. emergency.bus boric. in Specification 3.1.2.2 is if the flow path through the acid pump(s) OPERABLE.

APPLICABILITY: NODES 1, 2, 3 and 4-ACTION:

Nth one boric acid makeup pump required for the boron injection f'1ow path(s) pursuant to Specification 3. 1.2.2 inoperable, restore the boric acid makeup 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 borated to a SHUTDOWN HARGIN equivalent to at least 3000 pea at 200 F; restore the above required boric acid makeup pump(s) status within the next 7 days or be in COLD SHUTDOQi within the next to'PERABLE 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREHENTS

4. 1.2.6 The above required boric acid makeup pump(s) shall be demonstrated OPERABLE by verifying, that on recirculation flow, the puap(s) develop a discharge pressure of greater than or equal to 90 psig when tested pursuant to SpecM ic~n-4-.6-.5.

+4m Earns cree test~ gm~~

ST. LUCIE - UNIT 2 3/4 1-i2 Amendment No. ~ ~ ~V ~ 40

~Q I REACTOR COOLANT SYSTEM 3/4.4;2 SAFETY VALVES-SHUTDOMN LIMITING CONDITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 psia + 1X."

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 Sp~~A 4.4.2.1 No additional Surveillance

'i.

Requirements other than those required by TiQSHVVI~ /~ 7Iwg jP~8~

The at lift setting pressure shall correspond to ambient conditions of the valve nominal operating temperature and pressure. L ST. LUCIE - UNIT 2 3/4 4-7

REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall setting of 2500 psia ~ 1X."

be OPERABLE with a lift APPLICABILITY: MODES 1, 2, and 3.

ACTION:

Mith one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least-HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE RE UIREMENTS Sp~ ~DO.

4.4.2.2 No additional Surveillance Requirements other than those required by 2sserri~e r'mti/~~ ~prrrrI The at lift setting pressure shall correspond to ambient conditions of the valve

. nominal operating temperature and pressure.

ST. LUCIE - UNIT 2 3/4 4-8

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued):

c. In the event either the PORVs, SDCRVs or, the RCS vent(s) are u.,

to mitigate a RCS pressure transient, a Special Report shall be ...

prepared .and submitted to the Commission pursuant to Specification ..

6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, SDCRVs or vent(s) on the transient and any corrective action necessary to prevent recurrence.

I

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.9.3.'. Each PORV shall be demonstrated OPERABLE by;

a. In addition to the requirements of , operating the PORV through one complete cycl of full travel at least once per 18 months.

4e jazern ce 7M7/<$ ~~/'

ST. LUCIE - UNIT 2 3/4 4-36 Amendment No. JS, 31

l' EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

2. A visual inspection of the containment sump and verifying that the subsystem suction inlets ark not restricted by debris and that the sump components (trash racks, screens, etc.).,show no evidence of structural distress or corrosion.
3. Verifying that a'minimum total of 173 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained

. within the TSP storage baskets.

4. Verifying that when a representative sample of 70.5 + 0.5 grams of TSP from a TSP storage basket is submerged, without agitation, in'0. 0 + 0.1 gallons of 120 + 10'F borated water from the RMT, the pH of the mixed solution is raised to greater than or equal to 7 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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

1. Verifying that each automatic valve in the flow path actuates to its correct position on SIAS and/or RAS test signals.
2. Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:
a. ,

High-Pressure Safety Injection pump.

b. Low-Pressure Safety Injection pump.
3. Verifying that on a Sump Recirculation Actuation Test.

Signal, the containment sump isolation valves open and the recirculation valve to the refueling water tank closed.

g. By verifying that each of the following pumps develops the p Sp~ ~9-.5'.

specified total developed head on recirculation flow when tested

~zrvke /zi/~g l~j.cpY~

1. High-Pressure Safety Injection 2854 ft.

pumps: g er an o~ to

2. Low-Pressure Safety Injection pump: greater than or equal to 374 ft.
h. By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
1. 'During valve stroking operation or following maintenance on the valve and prior to declaring the valve OPERABLE when the ECCS subsystems are required to be OPERABLE.

ST. LUCIE - UNIT 2 3/4 5-5

SURVEILLANCE RE UIREMENTS

4. 6. 2.1 Each containment spray system shall be demonstrated OPERABLE:-

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, flow, each pump develops a c

discharge pressure of greater than or equal tested pursuant to Spec+f4~~~.

At least once per 18 months, during shutdown, Q g~<

0 psi when

<<<< /

M cfog iug

)0

~

1. Vet ifying that each automatic valve in the flow path actuates to its correct position on a CSAS test signal.
2. Verifying that upon a Recirculation Actuation Test Signal (RAS),

the containment sump isolation valves open and 'that a recircula-tion mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

Amendment No. "

ST. LUCIE - UNIT 2 3/4 6-15a

~ ~ Zri CONTAINMENT SYSTEMS IODINE REMOVAL SYSTEM (IRS)

LIMITING CONDITION FOR OPERATION 3.6.2.2 The Iodine Removal System shall be OPERABLE with:

a. A hydrazine storage tank containing a minimum volume of 675 gallons of > 25.4X by weight N2H4 (Hydrazine) solution, and
b. Two iodine removal pumps each capable of adding N2H4 solution from the hydrazine storage tank to a containment spray system pump flow.

APPLICABILITY: MODES 1, 2, and 3".

ACTION:

With the Iodine Removal System inoperable restore the system o 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 />; restore the Iodine Removal System 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 4.6.2.2 The Iodine Removal System shall be demonstrated OPERABLE:

ao 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.

b. The above requi red i odi'a ne removal pumps shall be demonstrated OPERABLE by verifying flow rate of between 0.71 gpm and 0.82 gpm when tested pursuant to I /0$ <h~

8 JgSg~y/gQ, GSI IRJ C. At least once per 6 months by:

1. Verifying the contained solution volume in the tank, and
2. Verifying the concentration of the N2H4 solution by chemical analys i s.
d. 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 CSAS test signal.

Applicable only when pressurizer pressure is > 1750 psia.

319 6-1/

CONTAINMENTSYSTE SURVEILLANCE REQUIREMENTS Continued 4.6.3.2 Each automatic containment isolation valve 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 (CIAS) and/or a Safety Injection test signal (SIAS), each isolation valve actuates to its isolation position,
b. Verifying that on a Containment Radiation-High test signal, each containment purge valve actuates to its isolation position.

4.6.3.3. The isolation time of each power-operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to SpeeifieatieR-4:eS.

7~ W~rvree /asHi~+myr~

ST. LUCIE - UNIT 2 3/4 6-20 Amendment No. 88

CONTAINMENT SYSTEMS 3 4.6.5 VACUUM REL EF VALVES LIMITING CONDITION FOR OPERATION 3.6.5 The primary containment vessel to annulus vacuum relief valves shall be OPERABLE with an actuation setpoint of less than or equal to 9.85 0.35 inches water gauge.

i

~AL: MXES1,2,3 44.

ACTION:

Mith one primary 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 SHUTDOW 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 No additional Surveillance Requirements other than those required by Speci-f-ica4-}en~0-.5.

+aservicw 7esV~y ~rg~

.~ c 3/4. 7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY YALVES LINITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE -th 1;ft settings and orifice sizes as shown in Table 3.7-2.

APPLICABILITY: I<ODES 1, 2 and 3.

ACTION:

c

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 NODES l. 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.

SURYEILLANCE'EQUIREHENTS 4.7.1.1 No additional Surveillance Reauirements other than those reauired by

+g +n.~civic~ 7es7i~ 7ropr~

ST. LUCIE - UNIT 2 3/4 7-1 Amendment No~ 68

MA N ST AM N ISO ATION VALV S LIMITING CONDITION FOR OPERATION RRRXR+ma~SRRRX%'R%R~RXRSCSQ> smase~eaaaaamaaa====aaaaaaaaaaasaaa= maa~axa=a===

3.7. 1.5 Each main steam line isolation valve shall be OPERABLE.

A~PP I IIEET: IIDDEE I, I, 3 2 A.

ACTION:

MODE 1 With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; 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 />.

MODES 2, 3- With one or both main steam line isolation valve(s) and 4 inoperable, subsequent operation in MODES 2, 3 or 4 may proceed provided the isolation valve(s) is (are) maintained closed. 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 'R W % 'O 'S R XXR KXR XR XR R XR XR R XR R Q R Ã C R R ~ Ã%

0%%%'RW%'O'SR  % > R > R >> R X4 XQ 0 R R R XR R R XXRA R R XR KR XC C 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 6.75 seconds when tested pursuant to 7/22! +Dd~grII'YCe I Mime ray~

ST. LUCIE - UNIT 2 3/4 7-9 Amendment No- 38, 5~

PLANT SYSTEMS MAIN FEEDWATER ISOLATION UALUES LIMITING CONDITION FOR OPERATION 3.7.1.6 Four main feedwater isolation valves (MFIVs) shall be OPERABLE.

APPLICABILITY:* MODES 1, 2, and,3, except when the MFIV is closed and deactivated,.

ACTION: a. With one MFIV inoperable in one or more main feedwater lines, OPERATION may continue provided each inoperable. valve is restored to OPERABLE status, closed, or isolated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Otherwise, 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With two MFIVs inoperable. in the same flowpath, restore at least one of the inoperable MFIVs to OPERABLE status or close one of the inoperable valves 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 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 HOT SHUTDOWN within,the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREH1.'NTS 4e ~gatv(c< 7~i~ 'P~r 4.7. 1. 6.a Each MFIV shall be demo strated OPERABLE by verifying full closure ithin 5.1S seconds h p The provxszons of Specxfl.cation 4.0.4 are applicable for entry into MODE 3.

no t 4.7. 1. 6.b For each inoperable MFIV, verify or isolated once per 7 days.

that it is closed

  • Each MFIV shall be treated independently.

ST. LUCIE - UNIT 2 3/4 7-10 Amendment No. 8, SS, 8&, 71

BASES 4.0.4 This specification establishes the requirement that all applicable condition surveillances must be met before entry into an OPERATIONAL MODE or otherthis of operation specified in the Applicability statement. The purposerequirements of specification is to ensure that system and component OPERABILITY or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL MOOES or other. specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startuo or following a plant outage.

'When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

4.0.5 This specification ensu'res that inservice inspectio of ASME Code II Class 1, 2 and 3 components an imps-an~+es 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.

74+5-specificat4oo-4nc~d n-o4

'Ne-A*equenc+es-fov-pm4o~mg-tk~~~~spec4+on-and-te~~at-~~~qAme~~ectA on throughout-these-'Fechr6cal Speci-fic~Rs-aRd-4o-remove-any amMgu+t4es.

rMeM~e-to-the-A*equen&-es-fec~m~mmg tthhe-requQ*ed iaserviee inspection ader the-tame-o~h+s-speci4'-'HMAe~e-m e-requ+venents

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,t*e-req~ents-of'peci4~&e~h-4-to-per

-o-entry iso-aR eve~4e-ASME-Bo-i-1-er-and-P-r assure-Vess~de-prov-i-s-mn-which-a04ows-pumps-Co f H Me-Technical-Spec i-fi~%+on-de-H~-tiwn-of-QPGRABLE-does-not grant a-gee

~d-bedim e-a-dev+ee-that i~notcapaM+-oWperfora4og i+s-speci-fiM-Junctions eel~ed-i-nepemM~and-takes-precedence-ove~e-ASME-Bo Her-and-Pressure spaced-4oRc~o-fm up-to-24-hours-before-b~g-de~d-4noperakA e.

ST. LUCIE - UNIT 2 B 3/4 0-6 Amendment No.33

0 'E REACTOR COOLANT SYSTEM BASES.

SAFETY VALVES (Continued)

During 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 system pressure to within its Safety. Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip .setpoint (Pres-surizer 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.

Demonstration of the safety valves'ift settings will occur only during shutdown and will be performed in accordance with the provisions of See&ca-4I ofhe-ASM 3/4.4.3 PRESSURIZER HAe aur yacc'arsi~

An OPERABLE pressurizer provides pressure control for the Reactor Coolant System during operations with both forced reactor coolant flow and with natural circulation flow. The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure control, remain covered with water to prevent failure, which could occur if the heaters were energized uncovered. The maximum water level in the pres-surizer ensures that this parameter is maintained within the envelope of operation assumed in .he safety analysis. The maximum water level'lso ensures that the RCS is not a hydraulically solid system and that a steam bubble will be provided to accommodate pressure surges during operation. The steam bubble also protects the pressurizer code safety valves against water relief. The requirement to verify that on an Engineered Safety Features Actuation test signal concurrent with a loss of offsite power the pressurizer heaters are automatically shed from the emergency power sources is to ensure that the non-Class lE heaters do not reduce the reliability of or, overload the emergency power source. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability to control Reactor Coolant System pressure and establish and maintain natural circulation.

ST. LUCIE " UNIT 2 B 3/4 4"2

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