Text

Proposed License Amendments Request for Additional Information Response Control Room Ventilation System and Miscellaneous Minor Changes
	ML052420533
Person / Time
Site:	Saint Lucie
Issue date:	08/25/2005
From:	Jefferson W; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2005-132
	Download: ML052420533 (48)
	v • d • e

Florida Power & Light Company. 6501 S.Ocean Drive, Jensen Beach, FL 34957 FP2L August 25, 2005 L-2005-132 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Request For Additional Information Response Control Room Ventilation System and Miscellaneous Minor ChanQes By Florida Power & Light Company (FPL) letter L-2003-199 dated September 18, 2003 and pursuant to 10 CFR 50.90, FPL requested to amend Facility Operating Licenses DPR-67 and NPF-16 for St. Lucie Units 1 and 2. The proposed amendments revise the Technical Specification (TS) for control room ventilation systems to model the Combustion Engineering Standard Technical Specifications NUREG-1432 (CE STS).

The change includes revising both the Unit 1 and Unit 2 control room ventilation system TS to replace detailed filter testing surveillance requirements with a requirement to test in accordance with the Ventilation Filter Testing Program.

In addition to the above changes, FPL proposed to revise St. Lucie Unit 1 and Unit 2 TS Table 3.3-6, Radiation Monitoring Instrumentation, in order to resolve minor inconsistencies that resulted from changes associated with TS Amendments 184 (Unit

1) and 127 (Unit 2). This change also proposed to correct some minor typographical errors.

Attachment 1 is the FPL response to the NRC request for additional information (RAI) dated June 24, 2004. Attachment 2 provides a revised Determination of No Significant Hazards. Attachments 3 and 4 are complete replacement of the proposed TS page changes for Unit 1 and Unit 2, respectively. These pages incorporate the minor changes requested by the NRC in the subject RAI. Attachments 5 and 6 are replacement smooth retyped TS pages for Unit 1 and 2.

The original Environmental Considerations submitted by FPL letter L-2003-199 remains bounding. In accordance with 10 CFR 50.91 (b)(1), a copy of this supplement is being forwarded to the State Designee for the State of Florida.

C)u an FPL Group company

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Page 2 Please issue the amendment to be effective on the date of issuance and to be implemented within 60 days of receipt by FPL. Please contact George Madden at 772-467-7155 if there are any questions about this submittal.

William Vice Pre ent St. Lucie Plant WJ/GRM Attachments cc: Mr. William A. Passetti, Florida Department of Health

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Page 3 STATE OF FLORIDA )

) ss.

COUNTY OF ST. LUCIE )

William Jefferson, Jr. being first duly sworn, deposes and says:

That he is Vice President, St. Lucie Plant, for the Nuclear Division of Florida Power &

Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licen STATE OF FLORIDA e r COUNTY OF ST LUCIE Sworn to and subscribed before me this _ day of _ 200 by William Jefferson, Jr., who is personally known to me.

Name of Notary lgc - State of Florida

,Leslie J. Whitwell

7 *Co son# DD414813

\ JLSExpires May 12, 2009 M~8.8.719 (Print, type or stamp Commissioned Name of Notary Public)

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 1 Page 1 St. Lucie Unit 1 & 2 Control Room Ventilation Filter Systems Response to NRC Request for Additional Information On September 18, 2003, Florida Power and Light Company submitted a license amendment request for the St. Lucie Unit 1 and Unit 2 Control Room Ventilation Systems (along with other minor miscellaneous system change requests). As a result of the FPL submittals and a teleconference between NRC and FPL staffs on June 23, 2004, the NRC requested additional information to assist in their review of the proposed amendments (NRC letter dated June 24, 2004). FPL hereby provides the response to the requested information.

NRC Question 1: All current surveillance TS requirements for ventilation filter testing are not included in the proposed ventilation filter testing program (VFTP). St. Lucie is committed to Regulatory Guide (RG) 1.52, Rev 2 and as such, the proposed VFTP should be in compliance with the guidance of the RG. Therefore, in order for the proposed VFTP to be acceptable all of the current surveillance requirements should be included.

FPL Response 1: All of the Unit 1 and 2 CR ventilation filter testing TS requirements are included in the proposed Ventilation Filter Testing Program (VFTP). The proposed change is modeled after the NUREG-1432 format in that the filter train operational-type surveillance tests are explicitly stated in the LCO/Surveillance section and direction for the post maintenance or preventative maintenance related surveillance tests are stated to be in accordance with the VFTP (Section 6.0 of St Lucie TS).

The Unit 1 and Unit 2 proposed VFTPs for control room ventilation filter train testing list all required TS surveillance acceptance limits. The frequency requirements are met by describing the VFTP (in Section 6.0 of TS) as a program that tests at the "frequencies specified in Regulatory Guide (RG) 1.52, Revision 2." These testing frequencies specify off-normal as well as normal (i.e., 'scheduled") testing and match up with current TS testing frequencies.

Off-normal testing requirements include HEPA and adsorber bak testing following any filter or cell replacements, re-verification of adsorber efficiency testing following any filter train contact with foreign fumes and specified airflow distribution following train maintenance activities.

The proposal to delete Unit 2 TS 4.7.7.c.1 and 4.7.7.c.2 is an administrative deletion only as these two requirements are delineated in the RG 1.52 ir-place testing requirements which the proposed VFTP and Unit 2 UFSAR is committed to follow.

NRC Question 2: In addition, proposed items k. 1 and k.2 request that in-place testing for emergency safety features show a penetration and bypass of <1% for high efficiency particulate air filters and charcoal adsorbers. This position is not consistent with RG 1.52. In accordance with he staff's position on this issue, as outlined in RG 1.52,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 1 Page 2 systems penetration and bypass for the stated systems and situations should be <.05%,

therefore the proposed VFTP should be revised and made consistent with the RG, or justification should be provided for the higher limit.

FPL Response 2: As confirmed by the November 8, 1974 St. Lucie Unit 1 SER, the proposed control room filtration system design was accepted by the NRC as originally presented with the additional stipulation that charcoal attributes and charcoal/HEPA testing requirements of RG 1.52 (Rev 0) were adopted. The plant complied and the operating license was granted. These requirements dealt with HEPA and charcoal efficiencies as well as the necessary attributes of the activated charcoal. Adoption of the in-place testing criteria of the RG was not cited as being conditional for design acceptance.

Review of past surveillance test results indicates that the Unit 1 design can meet this lower limit. FPL therefore accepts the NRC request to and will abide by the in-place HEPA (DOP) and charcoal (gas) testing criteria of <.05% bypass leakage as recommended by RG 1.52, Rev 2.

The revised marked-up Unit 1 TS page has been included for your review and approval.

The Unit 2 control room filtration system was designed and licensed to all RG 1.52 (Rev

2) requirements and therefore does not require any changes to this particular TS.

NRC Question 3: Surveillance requirements (SR) 4.7.7. 1.a (Unit 1) and 4.7.7.a (Unit 2)

(verification that control room air temperature [<120° F] are being deleted.)

The Licensee is requested to provide a plant-specific technical justification for deletion.

The purpose of a temperature limit is for both equipment operability and human habitability in accordance with GDC 19. The Licensee states, and the staff agrees, that this surveillance does not appear in the Combustion Engineering Standard Technical Specifications. However, since this is currently a requirement in the St. Lucie Technical Specifications (TSs), please provide a plant-specific rationale for the deletion, and indicate how this parameter will be controlled outside of the TS.

FPL Response 3: Upon further review of this specification (including identification of a similar surveillance in the CE STS) S. Lucie Plant withdraws the request to delete Surveillance requirements 4.7.7.1.a (Unit 1) and 4.7.7.a (Unit 2) from St. Lucie Plant TS.

NRC Question 4: SRs 4.7.7. 1.e.3 (Unit 1) and 4.7.7.e.3 (Unit 2) are being revised to allow for conducting control room pressure tests on a staggered basis.

For this request, the Licensee should provide a clearer description of what is requested.

The currently specified test interval (each ventilation system at least once per 18 months) requires testing both trains every 18 months with the interval between the test of each train ranging from one train right after the other, to almost the entire 18 months.

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 1 Page 3 Please describe the current practice for scheduling the affected surveillance, so that the increased interval may be accurately characterized. The proposed change, to test one train every 36 months on a staggered test basis, will result in testing each train on a 36 month interval, with each test occurring every 18 months on the alternate train. Please provide a technical basis for increasing the test interval for a train from 18 months to 36 months. Also, state how you will transition to the new test interval.

FPL Response 4: In light of NRC Generic Letter (GL) 2003-01, Control Room Habitability, and its uncertain future requirements, St. Lucie withdraws for now our request to change the control room pressurization surveillance interval to that as currently required by CE STS.

NRC Question 5: The proposed applicability for the fuel storage pool ventilation system gaseous and particulate monitors is "Whenever recently irradiated fuel is in the spent fuel pool". Why is it not 'During movement of recently irradiated fuel assemblies in the spent fuel pool?" This is more consistent with the Technical Specification Task Force-51 and the STS for an applicability statement for a limiting condition for operation associated with mitigating or monitoring a fuel handling accident.

FPL Response 5: The proposed wording for Unit 1 is consistent with the applicability requirements of the radiation monitors' associated TS ventilation system, Unit 1 TS 3.9.12, Spent Fuel Pool Ventilation System. The proposed wording for Unit 2 has been changed to be consistent with the applicability requirements for the associated TS ventilation system, Unit 2 TS 3.6.6.1, Shield Building Ventilation System. [Note that Unit 2's Shield Building Ventilation System performs both a shield building and a fuel pool area evacuation function.]

Although adequate for Unit 1, the standard TS wording does not sufficiently bound the Unit 2 shield building ventilation system TS applicability because it does not include the condition of crane operations with loads over recently irradiated fuel. The purpose of the administrative change was to align the proposed wording of the radiation monitors' with the previously approved TS applicability requirements of the associated ventilation systems. Although the revised Unit 2 wording differs from the standard TS, it is consistent with the currently approved Unit 2 ventilation system applicability.

NRC Question 6: Unit 2 only:

In Attachment 1, Page 2, the proposed markup for TS 3.7.7.1 (Insert 1) associated with the 2 nd and 3rd bullets is not included. The mark-up designated Insert I on Page 8 is associated with Administrative Controls. Please provide corrected version.

FPL Response 6: The Unit 1 marked-up TS page (TS 3.7.7.1) was inadvertently placed where the Unit 2 marked-up TS page 3/4 7-17(TS 3.7.7) belongs. The Unit 2 marked-up TS page 3/4 7-17 is included with this supplement. The original submittal did include the retyped Unit 2 TS page 3/4 7-17. (Note that the marked-up Unit 2 page is all inclusive and does not reference any associated M inserts.")

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 2 Page 1 Revised No Significant Hazards Determination The Nuclear Regulatory Commission provides standards for determining whether a significant hazards consideration will exist (10 CFR 50.92(c)). A proposed amendment to an operating license for a facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Each standard is discussed below for the proposed amendment.

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

The proposed changes to the St. Lucie Unit 1 & 2 Technical Specifications will adopt the format of the NUREG-1432 Combustion Engineering Standard Technical Specifications for the Unit 1 control room emergency ventilation system and the Unit 2 control room emergency air cleanup system. Additionally, the Ventilation Filter Testing Program of the CE STS is being adopted for the aforementioned ventilation systems. No changes are being made to the methods or scope of any testing. A change involving a more stringent acceptance criteria for in-place HEPA and charcoal adsorber testing for Unit 1 components is a change in a conservative direction.

The proposed changes also correct mode applicability requirements for the containment isolation radiation monitor (both units) and the fuel storage pool gaseous and particulate monitors (both units). These corrections are necessary in order to restore consistency with related technical specification requirements for the containment isolation system and associated fuel pool area ventilation systems.

The equipment and systems involved are associated with accident mitigation.

The surveillance testing of this equipment has no bearing on the initiation of an accident previously evaluated nor on the probability of any accident previously evaluated.

Implementing the proposed changes does not significantly increase the consequences of an accident previously evaluated. With the exception of the Unit 1 in-place HEPA and charcoal adsorber leak testing, the performance requirements and acceptance criteria for the affected ventilation systems are not being changed. The in-place HEPA and charcoal adsorber leak testing acceptance criteria have been changed to more stringent industry-standardized requirements which have no effect on the probability of, and no increase in the

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 2 Page 2 consequences of any previously analyzed accidents. The ability of the affected systems to mitigate the effects of postulated accidents is not diminished by the proposed change.

The changes being proposed do not affect assumptions contained in the plants' safety analyses or the physical design of the plants, nor do they affect other technical specifications that preserve safety analysis assumptions. Therefore, operation of the facility in accordance with the proposed amendments would not involve a significant increase in the probability or consequences of an accident previously analyzed.

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

The proposed amendments do not involve any changes to the operational requirements, present any adverse performance of the affected systems, nor do they involve the addition or modification of any plant equipment. As such, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

(3) Operation of the facility in accordance with the proposed amendments would not involve a significant reduction in a margin of safety.

The margin of safety as defined by 10 CFR Part 100 has not been significantly reduced. There will be no decrease in the ability of the affected systems to perform their intended safety functions as assumed in accident analyses. The proposed changes do not alter the bases for assurance that safety-related activities are performed correctly or the basis for any Technical Specification related to the establishment of or maintenance of a safety margin.

Summary Based on the above discussion, FPL has determined that the proposed amendment request does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety; therefore, the proposed changes do not involve a significant hazards consideration as defined in 10 CFR 50.92.

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 1 Attachment 3 St. Lucie Unit I Planned Marked-up Technical Specification Pages TS Pages 3/4 7-20 314 7-21 314 7-22 314 7-23 3/4 3-22 6-15b 6-15c (For Information Only) 3/4 4-1 d

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 2 PLANT SYSTEMS 314.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM MITNG-CONDITIN FOR OPERATKON 3.7.7.1 The control room emergency ventilation system shall be OPERABLE with:

a. Two booster fans,

b. Two isolation valves in each outside air intake duct,

c. Two isolation valves in the toilet area air exhaust duct,

d. One filter train,

e. At least two air conditioning units, and

f. Two isolation valves in the kitchen area exhaust duct.

APPLICABILITY: MODES 1,2, 3P44, 5- 6' o r ACTION: 1,

a. With one booster fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one isolation valve per air duct inoperable, operation may continue provided the other isolation valve in the same duct is maintained closed; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With the filter train Inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With only one air conditioning unit OPERABLE, restore at least two air conditioning units to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

IIo.D(S &^C-vJ S Ad X _noe.- en ;Z :v a 4xet4/~es; MO DE ST. LUCIE - UN!T I 3/4 7-20 Amendment No. 160

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 3 INSERT 1

a. With one booster fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room emergency ventilation system in the recirculation mode or suspend movement of irradiated fuel assemblies.

b. With one isolation valve in an air duct inoperable, maintain the other isolation valve in the same air duct closed or suspend movement of irradiated fuel assemblies.

c. With the filter train inoperable, suspend movement of irradiated fuel assemblies.

d. With only one air conditioning unit OPERABLE, restore at least two air conditioning units to OPERABLE status within 7 days or suspend movement of irradiated fuel assemblies.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 4 PLANT SYSTEMS SURVEILLANICE REOIREMENTS 4.7.7.1 The control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is < 1200 F.

b. At least once per 31 days by:

1. Initiating flow through the HEPA filter and charcoal adsorber train and verifying that each booster fan operates for at least 15 minutes.

2. Starting (unless already operating) each air conditioning unit and verifying that it operates for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

C. t least once per 18 months or (1) after any structural mai -

te nce on the HEPA filter or charcoal adsorber housin or (2) owing painting, fire or chemical release In any v ti-lation ne communicating with the system by:

Ve g that the charcoal adsorbers remov > 99% of a halogen ed hydrocarbon refrigerant test s when they are test -place in accordance with A SI N510-1975 while operat the ventilation system a flow rate of 2000 cfm + 10

--- Verifying that the H A filter ban remove > 99% of the DOP when they are teted in-p ce in accordance with ANSI N510-1975 while opera g ventilation system at a flow rate of 2000 cfm + 10 r4- Verifying that a laborato an is of a carbon sample from either at least one te nlster o t least two carbon samples removed one of the c arcoal adsorbers demonstrates a removal efficien of> 97.5% for ra oactive methyl iodide when the mple is tested in ac dance with ASTM D3803- 89 (300C, 70% RH). The rbon samples not obtained fro est canisters shall be preparby either

. Em *ng one entire bed from a removed asorber tr mixing the adsorbent thoroughly, and obt ning

,

mples at least two inches in diameter and with ength equal to the thickness of the bed, or A'y pevfo~-1z repulte4 Cogtrol rtOUM MtqeW veVt'ltitiA AySf \

i TetI it me cc3mc wit-4 f1 Vt Amem e 167 ST. LUCIE - UNIT I 314 7-21 Amendment No. 167

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 5 PLANT SYSTEMS SURVEILLANCE REQUIRMENTS (Continued)

\b) Emptying a longitudinal sample from an adsorber/

\ tray, mixing the adsorbent thoroughly, and obtain ,

\samples at least two inches in diameter and wit a

\length equal to the thickness of the bed. /

4.Vring a system flow rate of 2000 cfm + 10%din syste operation when tested in accordance wit ANSI N51 -t5.

d. After every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of system operation by eithe.

1. Verifying th a laboratory analysis of a car on sample obtained fro a test canister demonstrat a removal efficiency of > 7.5% for radioactive me yl iodide when the sample is t ted in accordance wit ASTM D3803-1989 (300C, 70% RH); r

2. Verifying that a lab atory analysis f at least two car-bon samples demon trate a remo efficiency of > 97.5%

for radioactive methyl* ide whe the samples are tested in accordance with AS D380 -1989 (30-C, 70% RH) and the samples are prepar by her.

a) Emptying one entire d from a removed adsorber tray, mixing the adso nt thoroughly, and obtaining samples at least tw in es in diameter and with a length equal to the ick ss of the bed, or b) Emptying a long udinal sa le from an adsorber tray, mixing th dsorbent th roughly, and obtaining samples at le t two inches in iameter and with a length equalo the thickness o he bed.

Subsequent to r installing the adsorbe tray used for obtaining the rbon sample, the syste hall be demonstrat-ed OPERAB by also:

a) Veri g that the charcoal adsorbers remove > 99%

of a alogenated hydrocarbon refrigera test gas wh n they are tested in-place in accorda ce with A SI N510-1975 while operating the venti ton stem at a flow rate of 2000 cfm + 10%, a b) Verifying that the HEPA filter banks remove 9%

of the DOP when they are tested in-place in a rdance with ANSI N510-1975 while operating the ventil on system at a flow rate of 2000 cfm + 10%.

ST. WCIE- UNITI1 3/4 7-22 Amendment No. 167

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 6 PLANT SYSTEMS d,*e At least once per 18 months by 4that the pressure drop across the combn fitters and -charadsLQrjjerban g e Water GaugeW _ ytem at a

_ticOOOcfM + I10%.

A,: Verifying that on a containment isolation signal the system automatically isolates the control room within 35 seconds and switches Into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

2 ..- Verifying that the system maintains the control room at a positive pressure > 1/8 Inch W.G. relative to the outside atmosphere during system operation with < 450 cfm outside air intake. k 47 fter each complete or partial replacement of a HEPA f byby verifying that the HEPA fifter banks removp-!_SiM/ of the hen they are tested in-place in ac nce with ANSI iN51D1 975 e operating the ventilatio sern at a flow rate of 2000 c m 0% /O

-g- After each complete or replacement of a charcoal adsorber bank by ve ng tha e charcoal adsorbers remove

> 99W of a haleated hydroca efrigerant test gas when they are te in-place in accordance ANSI N51 0-1975 while rating the ventilation system at a flo ate of 2000

>;g- 10°h.\

ST. LUCIE - UNIT I 314 7-23 Amendment No. 33.57

r- 0 (D TABLE 3.3-6 o0 r-RADIATION MONITORING INSTRUMENTATION z (

co Co c0 C MINIMUM CHANNELS APPLICARLF ALARM MEASUI REMENT N3 cn =

CD .° -

INSTRUMENT OPERABLE MODES SETPOINT RAINGE ACTION

1. AREA MONITORS

a. Fuel Storage Pool Area 1 < 15 mR/hr 10'-1_ 104 mR/hr 13 0 O

b. Containment (CIS) "'wC; 3 .-G A)JI.W. < 90 mR/hr 1 -10 5 mR/hr 16

c. Containment Area-IHi 1 1, 2, 3, &4 <10 R/hr -107 R/hr 15 -4 CD Range

2. PROCESS MONITORS

a. Containment

i. Gaseous Activity 1 1, 2, 3 & 4 Not Applicable 10-10F6cpm 14 I RCS Leakage Detection ii. Particulate Activity 1 1, 2, 3 & 4 Not Applicable 10-1016cpm 14 RCS Leakage Detection

b. Fuel Storage Pool Area Ventilation System

i. Gaseous Activity I *or7 105AiCl/cc 12 ii. Particulate Activity 1 * *O6 cpm 12

' With uel In the storage pool or building.

Witl'rradiated fuel in the storage pool er-whonoor thoro ic fuel movemont within the pool or orone

The Alarm Setpoints are determined and set in accordance with requirements of the Offsite Dose Calculation Manual.

ST. LUCC iEe.UNT. 2 /4 3 3I:22 Am en-dmer4 ST. LUCIE - UNIT 1 3/4 3-22 Amfendmen it No. 59, 423,134

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 8 ADMINISTRATIVE CONTROLS (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

h. Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. This program is in accordance with the guidelines contained in Regulatory Guide 1.163, 'Performance-Based Containment Leak-Test Program." as modified by the following exception(s):

a) Bechtel Topical Report, BN-TOP-1 or ANS 56.8-1994 (as recommended by R.G. 1.163) will be used for type A testing.

b) The first Type A test performed after the May 1993 Type A test shall be no later than May 2008.

The peak calculated containment internal pressure for the design basis loss of coolant accident Pa, is 39.6 psig. The containment design pressure is 44 psig.

The maximum allowed containment leakage rate, La, at Pa, shall be 0.50% of containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance crit on is< 1.0 La. During the first unit startup following testing in acco ance with this program, the leakage rate acceptance criteria are La for the Type B and C tests,

< 0.75 La for Type A tests, and c 0.27 La for secondary containment bypass leakage paths.

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is < 0.05 La when tested at > Pa.

2) For the personnel air lock door seal, leakage rate is < 0.01 La when pressurized to > 1.0 Pa.

3) For the emergency air lock door seal, leakage rate is < 0.01 La when pressurized to > 10 psig.

ST. LUCIE - UNIT I 6-15b Amnendment No. 6Q.8,E,423.449 187

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 9 ADMINSIRATlVET DfQLS-continued)

The provisions of T.S. 4.0.2 do not apply to test frequencies In the Containment Leak Rate Testing Program.

The provisions of T.S. 4.0.3 are applicable to the Containment Leak Rate Testing Program.

I. Inservice Testing Program 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 Xl of the ASME Boiler and Pressure Vessel Code' and applicable addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies for performing Inservice testing activities Inservice testing 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 164 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.

J. Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

1. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

2. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

a. a change In the TS Incorporated In the license; or

b. a change to the updated UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

3. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

4. Proposed changes that meet the criteria of Specification 6.8.4.J.2.a or 6.8.4.J.2.b, above, shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases Implemented without prior NRC approval shall be provided to the NRC on a frequency J-:iC, ter z7 consistent with 10 CFR 50.71(e).

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

ST. LUCIE - UNIT I 6-15tC Amendment No. 440,453, 176

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 10 INSERT 2

k. Ventilation FilterTesting Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.

1. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1975 at the system flow rate specified below.

ESF Ventilation System Flowrate Control Room Emergency Ventilation 2000 + 200 cfm

2. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1975 at the system flowrate specified below.

ESF Ventilation System Flowrate Control Room Emergency Ventilation 2000 + 200 cfm

3. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30 0 C and the relative humidity specified below.

ESF Ventilation System Penetration RH Control Room Emergency Ventilation 70%

4. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Ventilation System Delta P Flowrate Control Room Emergency Ventilation <4.15" W.G. 2000 + 200 cfm The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 3 Page 11 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMMN39NiIQ EOR OPFRATION 3.4.1.4,t least one shutdown cooling loop shall be OPERABLE and in operao9d either.

a. One additional shutdown cooling loop shall be OPERABLE . or

b. The secondary side water level of at least two steam generators shall be greater than 10% of narrow range Indication.

APPLICABILITY: MODE 5 with reactor coolant loops filled4.

ACTION:

a. With less than the above required loops OPERABLE or with less than the required steam generator level, within one (1) hour Initiate corrective action to return the required loops to OPERABLE status or to restore the required level.

b. With no shutdown cooling loop in operation, suspend operations that would cause introduction intb the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and within one (1)hour initiate corrective action to return the required shutdown loop to operation.

,5URVEI LNCE REQUIREMENTS-4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided 1)no operations are permitted that would cause Introduction Into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and

2) core outlet temperature is maintained at least 10OF below saturation temperature.

One shutdown cooling loop may be Inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

1. A reactor coolant pump shall not be started with two Idle loops unless the secondary water temperature of each steam generator Isless than 30°F above each of the Reactor Coolant System cold leg temperatures.

ST. LUCIE -UNITIt 314 4-td Amendmert No. 66. 94. 4 0rIf-9

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 1 Attachment 4 St. Lucie Unit 2 Proposed Mark-up Technical Specification Pages For Information TS Pages 3/4 7-17 314 7-18 3/4 7-19 3/4 3-25 3/4 3-27 6-15d INDEX iii 3/4 9-9

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 2 PLANT SYSTEMS 314.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM (CREACS)

LMIT F 3.7.7 Two independent control room emergency air cleanup systems shall be OPERABLE with:

a. A filter train and its associated fan per system, and

b. At least one air conditioning unit per system, and

c. Two isolation valves in the kitchen area exhaust duct, and

d. Two isolation valves in the toilet area exhaust duct, and

e. Two isolation valves in each (North and South) air intake duct.

APPLICABILITY: = MODESt.%} z. 3I ' 5ac'S CLQ 0zodto 4 ACTION: of td-ta fz-et ( <e-C.Sr;207 1-P MODES 1, 2,3, and 4:

a. With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With both control room emergency air cleanup systems inoperable, restore at least one system to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With an isolation valve in an air intake duct or air exhaust duct inoperable, operation may continue provided the other isolation valve in the same air intake or air exhaust duct is maintained closed; otherwise be in at least HOT STANDBY in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6 o..we 4 -es-,t-

a. With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room emergency air cleanup system in the jectrculqtion mode- -asCspw-cE Molle t 0f . vix Ie Aa1/r.

4#A 4 /,6/

b. With both control room emergency air cleanup systems inoperable, suspend all rperatonc invohvin CORCALTErosi"

c. With an isolation valve in an air intake duct or air exhaust duct inoperable, maintain the other isolation valve in the same air intake or air exhaust duct closed or suspand ions or X/

pokiie reactivy addifitin npeziief nJ'11a&eJ7 c4 7 /6r~c7A

-Limidplant cooldown or boron dilution is allowed providod the change is a nted for inthe calcu2lated SHUTDOWrN I~GN.

ST. LUCIE - UNIT 2 314 7-17 Amendment No. 122

- - .

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 3 PLANT SYSTEMS SURVEILLANCE RHEQUIREM 4.7.7 Each control room emergency air cleanup system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature Is less than or equal to 1200F.

b. At least once per 31 days by (1)initiating, trom the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes and (2)starting, unless already operating each air conditioning unit and verifying that it operates for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. least once per 18 months or (1)after any structural maintenance on ti/

I A filter or charcoal adsorber housings, or (2)following painting, fir or che release Inany ventilation zone communicating with the s mby

-`- Pe rming a visual examination of CREACS in accordan with ANSi 10-1980.

-2 Pertormin Ir flow distribution to HEPA filers and arcoal adsorbers in accordance th ANSI N-510-1980. The distributfn shall be +/- 20% of the average flow p unit.

-r Verifying that the c rcoal adsorbers remo e > 99.95% of a halogenated hydrocarbon refrigera test gas when t y are tested In accordance with ANSI N-510-1980 while erating the tem at 2000 cfm + 10%.

-4. Verifying that the HEPA flte re e> 99.95% of the DOP when they are tested Inaccordance with IS N-51 0-1 9BO while operating the system at 2000 cfm + 10%.

-S- Verifying a system flow re of 2000 +10%.

.& After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of rcoal adsorber op tion by verifying within 31 days after removal t a 4-Inch laboratory sa le from the Installed sample canisters demonstrats a removal efficiency Of 2 99. 25% for methyl iodide when tested in acc rdance with ASTM D3803-1989 ( 0C,95% RH). I

-e- At least once r18 months by:

-I- Von g that the pressure drop across the combined pre ers, HEPA firs and charcoal adsorber banks Is less than 7.4 Inches ter Gauge ile operating the system at a flow rate of 2000 cfm r 100/0.

$1 Cet f (.M:Are ".Lr(CdA.I-riouI rcGM C/V3CC IV- C(CeAvLf Al ST. WUCIE - UNIT 2 3!4 7-1 8 Amendment No. 1I7

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 4 PLANT SYSTEMS

-2; Verifying that on a containment isolation test signal from Unit 2. the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

. Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 Inch Water Gauge relative to the outside atmosphere during system operation with < 450 cfm outside air intake.

-+3. Verifying that on a containment Isolation test signal from Unit 1 the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

After each complete or place I a charcoal adsorber bank by verifying charcoal adsorbers e greater than or equal to 9 9 a halogenated hydrocarbon re i test gas wh re tested in-place in accordance with ANSI No e operating the system at a flow rate of 2000 cfm +/- 10%.

J. Afi WtSt onct pev 1 MA Iaely.

ST.LMCIE-UNIT2 3(4 7-19

0 rD TABLE 3.3-6 . . 0o RADIATION MONITORING INSTRUMENTATION CAO N(n C:

MINIMUM D)° CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT O Co INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION r co

1. AREA MONITORS CDD)

a. Fuel Storage Pool Area I. Criticality and 4 * < 20 mR/hr 10.1 _104 mR/hr 22 Xu Ventilation System a)

Isolation Monitor *(a C.C

b. Containment Isolation 3 --- < 90 mR/hr 1-10 mR/hr 25 Us

c. Control Room Isolation 1 per ALL MODES < 2x background 10 - 102 CVcc 26 intake

d. Containment Area - Hi 1 1, 2,3 & 4 Not Applicable 1- 107 Rthr 27 Range

2. PROCESS MONITORS

a. Fuel Storage Pool Area Ventilation System

i. Gaseous Activity 1 ** 107 _ 10.2 jCi/cc 24 ii. Particulate Activity 1 1 _106cpm 24

b. Containment Gaseous C. Activity 1 1, 2, 3 & 4 Not Applicable 107 _ 102 jiCi/cc 23 Ii. Particulate Activity 1, 2, 3 & 4 Not Appicable 1 1 6cpm6 23 RCS Leakage Detection

With fuel in the storage pool or building. bu o'er (_ d ,"

- VWth iFredieted Pucl in the sterage pel e henev~rfthere is fuel moverne t4hpeel orxcuranoperations with loads over i e/g2 recked> / Ct Vui/ *S/ . ,~Ase1 -s .Jt sL e ,...Cj/

The Alarm/Trip Setpoints are determined and set In accordance with requirements of the Offsite Dose Calculation Manual. 4

A'UCIE. aC eca..4 1, e./

o

'i-l -:a e J,3 aV3 - .25.61

,,,AA't~ndment No. 25,61

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 6 TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend all operations involving movement of uel within the spent fuel storage pool.

andewieen cPFzrlAt;qnl~ith loadc o.'GthA3 cpent fuziztrzGc8F pOzl.

ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

ACTION 27 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and

2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ST. LUCIE - UNIT 2 314 3-27 Amnendmlent No. 73

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 7 ADMINISTRATIVE CONTROLSlcantinued)

j. Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

1. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

2. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

a. a change in the TS incorporated in the license; or

b. a change to the updated UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

3. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

4. Proposed changes that meet the criteria of Specification 6.8.4j.2.a or 6.8.4.J2.b, above.

shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

[zVSfARf 17 ST. LUCIE - UNIT 2 6-1 5g Amendment No. 117

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 8 INSERT 1

k. Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.

1. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1980 at the system flowrate specified below.

ESF Ventilation SVstem Flowrate Control Room Emergency Air Cleanup 2000 + 200 cfm

2. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1980 at the system flowrate specified below.

ESF Ventilation System Flowrate Control Room Emergency Air Cleanup 2000 + 200 cfm

3. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 300C and the relative humidity specified below.

ESF Ventilation System Penetration RH Control Room Emergency Air Cleanup <0.175% 95%

4. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Ventilation System Delta P Flowrate Control Room Emergency Air Cleanup <7.4" W.G. 2000 + 200 cfm The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 9 INDEX SAFET LIMIS AND LIMITING SAFEW SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE ...................................................................... .................. 2-1 2.1.1.1 DNBR ................... 2-1 E EK............................. ..... _=.....

2.1.2 REACTOR COOLANT SYSTEM PRESSURE .2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SETPOINTS . .2-2 ST. LUCIE - UNIT 2 III Amendment No. 4Or*7

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 4 Page 10 REFUELING OPERATIONS LOW WATER LEVEL I&`"TM19N FOR OPERATION ITlMmN 3.9.8.2 pen~dpedent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling shall be in operation.

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

ACTION:

a. With less than the required shutdown cooling loops OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel flange, as soon as possible.

b. With no shutdown cooling loop in operation, suspend operations that would cause introduction Into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 and within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Initiate corrective action to return the required shutdown cooling loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4 4.9.8.2 At least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:

a. At least one shutdown cooling loop shall be verified to be in operation.

b. The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.'

The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is Implemented: the reactor has been determined to have been subcritical for at least 125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months , the maximum RCS temperature is < 1170F, and the temperature of CCW to the shutdown cooling heat exchanger Is < 87'F.

ST. LUCIE - UNrr 2 3J4 9-9 Amendment No. 48.60.7;.-19 --

- - -

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 1 Attachment 5 St. Lucie Unit 1 Revised Retyped Technical Specification Pages TS Pages 3/4 7-20 3/47-21 3/4 7-22 3/4 7-23 3/4 3-22 6-15b (Also changed by PLA L-2003-224) 6-1 5d 3/4 4-1 d

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 2 PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7.1 The control room emergency ventilation system shall be OPERABLE with:

a. Two booster fans,

b. Two isolation valves in each outside air intake duct,

c. Two isolation valves in the toilet area air exhaust duct,

d. One filter train,

e. At least two air conditioning units, and

f. Two isolation valves in the kitchen area exhaust duct.

APPLICABILITY: MODES 1, 2, 3, 4, 5 and 6 or during movement of irradiated fuel assemblies.

ACTION:

MODES 1, 2,3 and 4:

a. With one booster fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one isolation valve per air duct inoperable, operation may continue provided the other isolation valve in the same duct is maintained closed; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With the filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With only one air conditioning unit OPERABLE, restore at least two air conditioning units to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ST. LUCIE - UNIT I 314 7-20 Amendment No. 460,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 3 PLANT SYSTEMS ACTION: (continued)

MODES 5 and 6 or during movement of irradiated fuel assemblies:

a. With one booster fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room emergency ventilation system in the recirculation mode or suspend movement of irradiated fuel assemblies.

b. With one isolation valve in an air duct inoperable, maintain the other isolation valve in the same air duct closed or suspend movement of irradiated fuel assemblies.

c. With the filter train inoperable, suspend movement of irradiated fuel assemblies.

d. With only one air conditioning unit OPERABLE, restore at least two air conditioning units to OPERABLE status within 7 days or suspend movement of irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS 4.7.7.1 The control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is < 1201F.

b. At least once per 31 days by:

1. Initiating flow through the HEPA filter and charcoal adsorber train and verifying that each booster fan operates for at least 15 minutes.

2. Starting (unless already operating) each air conditioning unit and verifying that it operates for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. By performing required control room emergency ventilation system filter testing in accordance with the Ventilation Filter Testing Program.

ST. LUCIE - UNIT 1 314 7-21 Amendment No. 46;,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 4 PLANT SYSTEMS SURVELNC-ERDEQUIREMENTS (Continued)

DELETED ST. LUCIE - UNIT I 314 7-22 Amendment No. 46,.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 5 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued_

d. At least once per 18 months by:

1. Verifying that on a containment isolation signal the system automatically isolates the control room within 35 seconds and switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

2. Verifying that the system maintains the control room at a positive pressure > 1/8 inch W.G. relative to the outside atmosphere during system operation with < 450 cfm outside air intake.

ST. LUCIE - UNIT I 314 7-23 Amendment No. 33, S7,

M o-00 CD r-TABLE 3.3-6 Z CD RADIATION MONITORING INSTRUMENTATION

-0 C 0\) -°n MINIMUM 0201g.

O CHANNELS APPLICABLE ALARM MEASUREMENT INSTRUMENT RANGE ACTION 0101

=r W X OPERABLE MODES SETPOINT

1. AREA MONITORS Cn-,o, a

a. Fuel Storage Pool Area 1 <15mRihr 10 -104 mR/hr 13 CD WN

'c 90 mRhr 1 105 mRlhr 16 0 O

b. Containment (CIS) 3

c. Containment Area -.Hi 1 1, 2, 3 &4 <10RIhr 1- 107 R/hr 15 Range a)

2. PROCESS MONITORS

a. Containment I. Gaseous Activity 1 1, 2, 3 & 4 Not Applicable 10 - 106 cpm 14 RCS Leakage Detection ii. Particulate Activity 1 1, 2, 3 & 4 Not Applicable 10 -i0 6 cpm 14 RCS Leakage Detection

b. Fuel Storage Pool Area Ventilation System I. Gaseous Activity 1 A.

10-7 _05 PtCIcc 12 ii. Particulate Activity I 1 106 cpm 12

With fuel In the storage pool or building.

With recently Irradiated fuel in the storage pool. I

- - The Alarm Setpoints are determined and set in accordance with requirements of the Offsite Dose Calculation Manual.

'** During movement of recently irradiated fuel assemblies within containment. I ST. LUCIE - UNIT I 3/4 3-22 Amendment No. 59, 423,434,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 7 ADMINISTRA TIVE CONTROLS (2)conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

.2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

h. Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J. Option B, as modified by approved exemptions. This program is in accordance with the guidelines contained in Regulatory Guide 1.163, 'Performance-Based Containment Leak-Test Program," as modified by the following exception(s):

a) Bechtel Topical Report, BN-TOP-1 or ANS 56.8-1994 (as recommended by R.G. 1.163) will be used for type A testing.

b) The first Type A test performed after the May 1993 Type A test shall be no later than May 2008.

The peak calculated containment internal pressure for the design basis loss of coolant accident Pa, is 39.6 psig. The containment design pressure is 44 psig.

The maximum allowed containment leakage rate, La, at Pa, shall be 0.50% of containment air weight per day.

Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests,

< 0.75 La for Type A tests, and < 0.27 La for secondary containment bypass leakage paths.

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is < 0.05 La when tested at > Pa.

2) For the personnel air lock door seal, leakage rate is < 0.01 La when pressurized to > 1.0 Pa.

3) For the emergency air lock door seal, leakage rate is < 0.01 La when pressurized to > 10 psig.

ST. LUCIE - UNIT I 6-15b Amendment No. 69, 86. 423, 449, 4O7,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 8 ADMINISTRATIVE ONTR Inued)

k. Ventilation Filter Testinq Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.

1. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1975 at the system flowrate specified below.

ESF Ventilation System Flowrate Control Room Emergency Ventilation 2000 + 200 cfm

2. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1975 at the system flowrate specified below.

ESF Ventilation System Flowrate Control Room Emergency Ventilation 2000 + 200 cfm

3. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30 0C and the relative humidity specified below.

ESF Ventilation System Penetration RH Control Room Emergency Ventilation < 2.5% 70%

4. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Ventilation System Delta P Flowrate Control Room Emergency Ventilation <4.15"W.G. 2000 + 200 cfm The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment of the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

ST. LUCIE - UNIT I 6-15d Amendment No. 4A6,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 5 Page 9 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation* and eitherI

a. One additional shutdown cooling loop shall be OPERABLE#, or

b. The secondary side water level of at least two steam generators shall be greater than 10% of narrow range Indication.

APPLICABILITY: MODE 5 with reactor coolant loops filled#.

ACTION:

a. With less than the above required loops OPERABLE or with less than the required steam generator level, within one (1) hour initiate corrective action to return the required loops to OPERABLE status or to restore the required level.

b. With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS; coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and within one (1) hour initiate corrective action to return the required shutdown loop to operation.

,SURVEILLANCE-REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided 1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and

2) core outlet temperature is maintained at least I 0OF below saturation temperature.

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

A reactor coolant pump shall not be started with two idle loops unless the secondary water temperature of each steam generator is less than 300 F above each of the Reactor Coolant System cold leg temperatures.

ST. LUCIE - UNIT I 314 41 d Amendment No. C6, 84. 403, 8,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 1 Attachment 6 St. Lucie Unit 2 Revised Retyped Technical Specification Pages TS Pages 314 7-17 314 7-18 314 7-19 314 3-25 314 3-27 6-15d 6-15e INDEX iii 3,4 9-9

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 2 PLANT SYSTEMS 314.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM (CREACS)

LIMITING CONDITION FOR OPERATION 3.7.7 Two independent control room emergency air cleanup systems shall be OPERABLE with:

a. A filter train and its associated fan per system, and

b. At least one air conditioning unit per system, and

c. Two isolation valves in the kitchen area exhaust duct, and

d. Two isolation valves in the toilet area exhaust duct, and

e. Two isolation valves in each (North and South) air intake duct.

APPLICABILITY: MODES 1, 2, 3, 4, 5 and 6 or during movement of irradiated fuel assemblies.

ACTION:

MODES 1, 2, 3, and 4:

a. With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With both control room emergency air cleanup systems inoperable, restore at least one system to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With an isolation valve in an air intake duct or air exhaust duct inoperable, operation may continue provided the other isolation valve in the same air intake or air exhaust duct is maintained closed; otherwise be in at least HOT STANDBY in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6 or during movement of Irradiated fuel assemblies:

a. With one control room emergency air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room emergency air cleanup system in the recirculation mode or suspend movement of irradiated fuel assemblies.

b. With both control room emergency air cleanup systems inoperable, suspend movement of irradiated fuel assemblies.

c. With an isolation valve in an air intake duct or air exhaust duct inoperable, maintain the other isolation valve in the same air intake or air exhaust duct closed or suspend movement of irradiated fuel assemblies.

ST. LUCIE - UNIT 2 314 7-17 Amendment No. 422,

. -

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 3 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.7 Each control room emergency air cleanup system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is

< 1200F.

b. At least once per 31 days by (1) initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes and (2) starting, unless already operating each air conditioning unit and verifying that it operates for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. By performing required control room emergency air cleanup system filter testing in accordance with the Ventilation Filter Testing Program.

ST. LUCIE - UNIT 2 314 7-18 Amendment No. 407,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 4 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. At least once per 18 months by:

1. Verifying that on a containment isolation test signal from Unit 2, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

2. Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch Water Gauge relative to the outside atmosphere during system operation with < 450 cfm outside air intake.

3. Verifying that on a containment isolation test signal from Unit 1 the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

ST. LUCIE - UNIT 2 3/4 7-1 9 Amendment No.

Cn ro O TABLE 3.3-6 °) a I-C)0 Zn C).

RADIATION MONITORING INSTRUMENTATION oC C_

"en MINIMUM CHANNELS APPLICABLE ALARMITRIP MEASUREMENT RANGE ACTION O c; D)

INSTRUMENT OPERABLE MODES SETPOINT

-r CD W °

1. AREA MONITORS E3 (n CL

a. Fuel Storage Pool Area

i. Criticality and 4 c 20 mR/hr 10 1 _104 mR/hr 22 -D D) 0 Ventilation System CD C)

Isolation Monitor C CO

b. Containment Isolation 3 ' 90 mR/hr 1 - 107 mR/hr 25 I CD (

Cn

c. Control Room Isolation 1 per ALL MODES < 2x background 10 7- 1o ptCl/cc 26 intake

d. Containment Area - Hi 1 1, 2, 3 & 4 Not Applicable I - 107R/hr 27 Range

2. PROCESS MONITORS

a. Fuel Storage Pool Area Ventilation System I. Gaseous Activity 1 10 - 10e lccc 24 ii. Particulate Activity 1 1 - 106 cpm 24

b. Containment

i. Gaseous Activity 17 2 3&4 NotApplicable 07-_l2e I/cc 23 RCS Leakage Detection 1 1 RCS Leakage Detection 1 1, 2, 3 & 4 Not Applicable 23 1 - 10 6 cpm

With fuel in the storage pool or building.

During movement of recently irradiated fuel assemblies or during crane operations with loads over recently irradiated fuel assemblies in the spent fuel storage pool.

The Alarm/Trip Setpoints are determined and set in accordance with requirements of the Offsite Dose I

Calculation Manual.

During movement of recently irradiated fuel assemblies within containment.

ST. LUCIE - UNIT 2 3/4 3-25 Amendment No. 25. G1,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 6 TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend all operations involving movement of recently irradiated fuel within the spent fuel I storage pool.

ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

ACTION 27 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and

2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ST. LUCIE - UNIT 2 314 3-27 Amendment No. 73,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 7 ADMINISTRATIVE CQN1RQ1 icont ued)

j. Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

1. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

2. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

a. a change in the TS incorporated in the license; or

b. a change to the updated UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

3. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

4. Proposed changes that meet the criteria of Specification 6.8.4.j.2.a or 6.8.4.J.2.b, above, shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases Implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).

k. Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2.

1. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05% when tested in accordance with ANSI N510-1980 at the system flowrate specified below.

ESF Ventilation System Flowrate Control Room Emergency Air Cleanup 2000 + 200 cfm

2. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested In accordance with ANSI N510-1 980 at the system flowrate specified below.

ESF Ventilation System Flowrate Control Room Emergency Air Cleanup 2000 +/- 200 cfm

3. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2.

shows the methyl iodide penetration less than the value specified below when tested In accordance with ASTM D3803-1989 at a temperature of 300 C and the relative humidity specified below.

ESF Ventilation System Penetration RH Control Room Emergency Air Cleanup < 0.175% 95%

ST. LUCIE - UNIT 2 6-15d Amendment No. 4A.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 8 ADMINI STRATlVE.CO NTROLS~continued)

k. Ventilation Filter Testing Program (VFTP) (continued)

4. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters and charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below.

ESF Ventilation System Delta P Flowrate Control Room Emergency Air Cleanup < 7.4 W.G. 2000 + 200 cfm The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.

ST. WCIE - UNIT 2 6-15e Amendment No.

St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 9 INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SEltINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE .2-1 2.1.1.1 DNBR .2-1 2.1.1.2 DELETE 2.1.2 REACTOR COOLANT SYSTEM PRESSURE .2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SETPOINTS .................... 2-2 ST. LUCIE - UNIT 2 III Amendment No. 405,44-4.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2005-132 Attachment 6 Page 10 REFUELING OPERATIONS LOW WATER LEVEL LIMITNG CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling shall be in operation.

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

ACTION:

a. With less than the required shutdown cooling loops OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel flange, as soon as possible.

b. With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 and within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate corrective action to return the required shutdown cooling loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCEREQ1JIREMENIS 4.9.8.2 At least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:

a. At least one shutdown cooling loop shall be verified to be in operation.

b. The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.*

The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is implemented: the reactor has been determined to have been subcritical for at least 125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months , the maximum RCS temperature is < 117 0F. and the temperature of CCW to the shutdown cooling heat exchanger is < 87'F.

ST. LUCIE - UNIT 2 314 9-9 Amendment No. 48, 60. 76, 422,

L-2005-132, Proposed License Amendments Request for Additional Information Response Control Room Ventilation System and Miscellaneous Minor Changes

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