L-2016-230, License Amendment Request 251, Relocate Select High-Range Noble Gas Effluent Monitors from the Technical Specifications to Licensee-Controlled Documents

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License Amendment Request 251, Relocate Select High-Range Noble Gas Effluent Monitors from the Technical Specifications to Licensee-Controlled Documents
ML17012A085
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/21/2016
From: Summers T
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2016-230
Download: ML17012A085 (23)
v • d • e


Text

DEC 2 1 2016 L-2016-230 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-250 and 50-251 Renewed Facility Operating Licenses DRR-31 and DPR-41 License Amendment Request 251, Relocate Select High-Range Noble Gas Effluent Monitors from the Technical Specifications to Licensee-Controlled Documents Pursuant to 10 CFR Part 50.90, Florida Power& Light Company (FPL) hereby requests an amendment to Renewed Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Nuclear Plant (Turkey Point)

Units 3 and 4, respectively. The proposed license amendment revises Turkey Point Technical Specification (TS) 3.3.3.3, Accident Monitoring Instrumentation, by deleting Instrument 19, High Range Noble Gas Effluent Monitors, from Table 3.3-5, Accident Monitoring Instrumentation, and Table 4.3-4, Accident Monitoring Instrumentation Surveillance Requirements, and relocating the requirements for Instruments .19(a}, Plant Vent Exhaust, 19(b}, Unit 3 Spent Fuel Pit Exhaust, and 19(c), Condenser Air Ejectors, to the Turkey Point Offsi~e Dose Calculation Manual (ODCM).

The Enclosure to this letter provides FPL's evaluation of the proposed change. Attachment 1 to the enclosure provides the existing TS pages marked up to show the proposed changes. Attachment 2 provides the retyped (clean copy) TS pages with revision bars to identify the proposed changes. provides existing TS Bases pages marked up to show the proposed changes. The TS Bases changes are provided for information only and will be incorporated in accordance with the TS Bases Control Program upon implementation of the approved amendment.

FPL has determined that the proposed change does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the change. The Turkey Point Onsite Review Group (ORG) has reviewed the proposed license amendment.

In accordance with 10 CFR 50.91 (b)(1 ), a copy of this letter is being forwarded to the designee of the State of Florida.

There are no new commitments made in this submittal.

FPL requests approval of this amendment request by December 20, 2017 and implementation within 90 days.

Should you have any questions regarding this submittal, please contact Mr. Mitch Guth, Licensing Manager, at 305-246-6698.

Florida Power & Light Company 9760 SW 344 St., Florida City, FL 33035

Turkey Point Nuclear Plant L-2016-230 Docket Nos. 50-250 and 50-251 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on the~ day of December 2016.

Sine:,~

Z-s 1 1 - - - ._ _ _ __

summers Site Vice President Turkey Point Nuclear Plant Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 1 of 21 Enclosure Evaluation of the Proposed Change Turkey Point Units 3 and 4 License Amendment Request (LAR) No. 251 Relocate Various High Range Noble Gas Effluent Monitors from the Technical Specifications to Licensee-Controlled Documents 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration Determination 4.3 Conclusions

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

- Proposed Technical Specification Pages (markup) - Proposed Technical Specification Pages (clean copy) - Proposed Technical Specification Bases Pages (markup), Information Only

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 2 of 21 Enclosure 1.0

SUMMARY

DESCRIPTION Florida Power& Light Company (FPL) hereby requests an amendment to Renewed Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Nuclear Plant (Turkey Point) Units 3 and 4, respectively. The proposed license amendment revises Turkey Point Technical Specification (TS) 3.3.3.3, Accident Monitoring Instrumentation, by deleting Instrument 19, High Range Noble Gas Effluent Monitors, from Table 3.3-5, Accident Monitoring Instrumentation, and Table 4.3-4, Accident Monitoring Instrumentation Surveillance Requirements, and relocating the requirements for Instruments 19(a), Plant Vent Exhaust, 19(b), Unit 3 Spent Fuel Pit Exhaust, and 19(c), Condenser Air Ejectors, to the Turkey Point Offsite Dose Calculation Manual (ODCM).

The proposed chan*ge serves to align the Turkey Point TS more closely with NU REG 1431, Standard Technical Specifications - Westinghouse Plants, Revision 4 (Reference 6.1 ).

2.0 DETAILED DESCRIPTION

  • Table 3.3-5 of TS 3.3.3.3 specifies the INSTRUMENT, TOTAL NUMBER OF CHANNELS, MINIMUM CHANNELS OPERABLE, APPLICABLE MODES and ACTIONS requirements for Accident Monitoring Instrument 19, High Range Noble Gas Effluent Monitors. The proposed change deletes Instrument 19 from Table 3.3-5 by relocating the requirements for Instruments 19(a), Plant Vent Exhaust, 19(b), Unit 3 Spent Fuel Pit Exhaust, and 19(c), Condenser Air Ejectors, to the Turkey Point ODCM. Proposed changes to the relocated requirements will be subject to the provisions of 10 CFR 50.59.

The proposed change to Table 3.3-5 of TS 3.3.3.3 is as follows:

! TABLE 3.3-5  !

i ACCIDENT MONITORING INSTRUMENTATION i

    • -------------**********------------------------------------****************************************r**-*--TOTAL********r******Mi-NiMU_M____ T____APPLi~----T*----------------------** 1

. NO. OF i CHANNELS i CABLE l

******-*-------------------- 1 !'!§.T~.\:!~~!'!I.................................... ~.~~~-~-~~-~---*l ...?.~~~~-~-~-~----l*---~-~~-~-~----L_-~~!~?-~~---j

i. .

! l

19. ! Plii;iFi RaRi:Jl Nsl:Jle Gas ~ffli,ieRt MsRitsrs DELETED  !

f-***---*-*--*-*-*-----------------------------******************************************;-*----------------*-*--*-**-*-*-r***-*****-**********************r*--- .. ------------------.,----------------------------:

j a. PlaRt V@Rt ~JEFiai,ist i 4 i 4 i Aki: i a4 I r----------------------------------------------------------------------------------------1--------------------------------r--------------------------------r------------------------r*-------------------------1

~: '._'_~'.~--~--~-~~-~-~-=~-~~---~-i-~--~~-~~:~-~-~------------------,---------------~---------------l--------------=---------------l--------~--------1---------------------------j 1... ...

i G. C@FIS@FIS@F J\ir ~j@stsrs i 4  ! 4  ! ~ i a4  !

_____________ i ________________________________________________________________________________________ ;________________________________ t________________________________t________________________ j_ __________________________ J

  • Table 4.3-4 of TS 3.3.3.3 specifies the INSTRUMENT, CHANNEL CHECK and CHANNEL CALIBRATION surveillance requirements (SRs) for Accident Monitoring Instrument 19, High Range Noble Gas Effluent Monitors. The proposed change deletes Instrument 19 from Table 4.3-4 by relocating the SRs for Instruments 19(a), Plant Vent Exhaust, 19(b), Unit 3 Spent Fuel Pit Exhaust, and 19(c), Condenser Air Ejectors, to the Turkey Point ODCM. Proposed changes to the relocated requirements will be subject to the provisions of 10 CFR 50.59.

The proposed change to Table 4.3-4 of TS 3.3.3.3 is as follows:

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 3 of 21 r.---------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------1.

TABLE 4.3-4 l----------**-****---~~~-1-~~~-!. ~_?._~_1!?._~~~-~--~~~!.~-~~~~:~~!_?._~--~~-~~~~-~~~~=:A::~~~1*T-~:~~:L----------**-***J

! INSTRUMENT  ! CHECK  ! CALIBRATION  !

~ ----------*-r**-------------------------------------------------------------------------------------------------------------------------------------L--------------------------L*---------------------------------------1

19. i lelisl'l RaRse ~!@!:lie Gas ~ffl1;1eRt M@Rit@rs DELETED i f--------------------------------------------------------------------------------------------------------------------------------------*:*-----------------------*-*:**---------------------------------------i

! a. PlaRt VeRt ~xl'la1;1st  ! ~ ! ~  !

1---------------------------------------------------------------------------------------------------------------------------------------r---------------------------!*----------------------------------------1

! l:i. lJRit J S~eRt i;1;1el Pit ~xl'la1;1st .! ~  ! ~

:  : I
---------------------------------------------------------------------------------------------------------------------------------------r*--------------------------r----------------------------------------~

...._________ l...::___~:_:~:.::.~~-~:'.~-~j:.:t-~~~------ . . . - - - . . . . . . . . .- *- . .*--------**-***-------*-""---""""".l.......~ ..... J. . . . . . .~---. .*- - - *'

3.0 TECHNICAL EVALUATION

3.1 System Description 3.1.1. Plant Vent Exhaust High-Range Noble Gas Effluent Monitor Gaseous radioactive effluents released via the Plant Vent Exhaust are monitored for high-range noble gas via Plant Vent Stack Air Particulate Radiation Monitor, RaD-6304. This Special Particulate, Iodine and Noble Gas (SPING) monitor detects radioactive noble gas isotopes passing through the plant vent exhaust to 7 5 the atmosphere and covers a range from 10- to 10 micro-curies per cubic-centimeter (µCi/cc) for Xenon (Xe) -133. In addition, the Unit 4 Spent Fuel Pit Vent exhaust is routed through the Plant Vent Exhaust pathway and monitored by RaD-6304. The Plant Vent Exhaust SPING monitor also functions to collect halogens and particulates on filter elements for later analysis, and thereby satisfies the NUREG-0737, Item 11.F.1 (Reference 6.2) requirements for noble gas effluent monitoring and for sampling and analysis of plant effluents. The Plant Vent Exhaust SPING monitor transmits a pulse signal to the control console in the computer room where high radiation, intermediate radiation and rate of rise alarms are provided. The alarm setpoints are determined by and set in accordance with the Turkey Point ODCM, as required by the Radioactive Effluent Controls Program.

3.1.2. Condenser Steam Jet Air Ejector High-Range Noble Gas Effluent Monitors Gaseous radioactive effluents released via the Condenser Steam Jet Air Ejectors are monitored for high-range noble gas activity by Condenser Steam Jet Air Ejector Exhaust Radiation Monitor RaD-3-6417 and RaD-4-6417 (RaD-*-6417) for Units 3 and 4 respectively. These SPING monitors detect radioactive noble gas isotopes discharged from the Steam Jet Air ~ector, which draws the gasses from the Condensers, and have a range frofn 10- to 105 µCi/cc for Xe-133. In addition, RaD-*-6417 collect and monitor particulates and halogens from the Condenser Steam Jet Air Ejector outlet flow stream, thereby satisfying NUREG-0737, Item 11.F.1 (Reference 6.2) requirements for noble gas effluent monitoring and for sampling and analysis of plant effluents. The alarm setpoints for these monitors are determined by and set in accordance with the methodology and parameters of the Turkey Point ODCM as required by the Radioactive Effluent Controls Program.

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 4 of 21 3.1.3. Unit 3 Spent Fuel Pit Exhaust High-Range Noble Gas Effluent Monitor Gaseous radioactive effluents released via the Unit 3 Spent Fuel Pit Vent Exhaust are monitored for high-range noble gas via the Unit 3 Spent Fuel Pit Vent Exhaust Radiation monitor, RaD-3-6418. This SPING monitor detects gaseous radiation passing through the Unit 3 Spent Fuel Pool Vent which includes exhausts from the Unit 3 Spent Fuel Pit and the Unit 3 Cask Handling Facility areas. The Unit 3 Spent Fuel Pit Vent Exhaust monitor consists of a 5

beta-gamma sensitive G-M tube detector and covers a range from 10-7 to 10

µCi/cc for Xe-133. The Unit 3 Spent Fuel Pit Vent Exhaust SPING monitor also functions to collect halogens and particulates on filter elements for later analysis, thereby satisfying NUREG-0737, Item 11.F.1 (Reference 6.2) requirements for noble gas effluent monitoring and for sampling and analysis of plant effluents.

The Unit 3 Spent Fuel Pit Vent Exhaust SPING monitor's alarms are provided on a console in the Cable Spreading Room. The alarm setpoints are determined by and set in accordance with the Turkey Point ODCM.

3.2 Proposed Change 3.2.1. Background In July 1996, the NRC issued License Amendments Nos. 188 and 182 for Turkey Point Units 3 and 4 (Reference 6.3), which relocated the Radiological Effluent Technical Specifications (RETS) from the Turkey Point TS to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) and additionally, incorporated new programmatic radioactive effluent and radiological environmental monitoring controls in TS 6.8.1.f, Radioactive Effluents Control Program. The changes were proposed in accordance with NRG Generic Letter (GL) 89-01, Implementation of Programmatic Controls for Radioactive Effluent Technical Specifications (Reference 6.4), and NUREG-1301, Offsite Dose Calculation Manual Guidance, Standard Radiological Controls for Pressurized Water Reactors (Reference 6.5). As part of the license amendment, the requirements for radioactive gas effluent monitoring of the Plant Vent Exhaust, Condenser Air Ejector Vent Exhaust and the Unit 3 Spent Fuel Building Vent Exhaust areas were relocated to the ODCM. However, the radiological effluent monitoring requirements for these locations were retained in part, in other TS sections including TS 3.3.3.3, Accident Monitoring Instrumentation.

The proposed license amendment revises TS 3.3.3.3, by deleting Instrument 19, High-Range Noble Gas Effluent Monitors, from Table 3.3-5, Accident Monitoring Instrumentation, and Table 4.3-4, Accident Monitoring Instrumentation Surveillance Requirements, and relocating the requirements for Instruments 19(a), Plant Vent Exhaust, 19(b), Unit 3 Spent Fuel Pit Exhaust, and 19(c),

Condenser Air Ejectors, to the Turkey Point ODCM.

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 5 of 21 3.2.2. Removal of Item 19, High Range Noble Gas Effluent Monitors, from TS 3.3.3.3 The purpose of the subject post-accident monitoring instrumentation is to detect and measure concentrations of noble gas fission products in gaseous effluents during and following an accident and to provide plant operators and emergency planning agencies with information on plant releases of noble gases. Per NUREG 1431, Volume 2, Bases (Reference 6.6), the post-accident monitoring instrumentation provided in NUREG 1431, Volume 1, Specifications (Reference 6.1) provides the necessary support for Control Room operators to take manual actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for Design Basis Accidents.

A comparison against NU REG 1431, Volume 1 (Reference 6.1) reveals that the proposed change does not involve accident monitoring instrumentation recommended for TS inclusion. More specifically, Table 3.3.3-1 of NUREG 1431 does not list any instrumentation being removed from the Turkey Point TS by the proposed change. Moreover, NUREG 1431, Volume 2 (Reference 6.6) states that the instrument channels required to be OPERABLE includes two classes of parameters identified during Unit specific implementation of Regulatory Guide (RG) 1.97, Revision 3, Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident (Reference 6.7), as Type A and Category 1 variables. The premise is repeated in a "Reviewer's Note" to Table 3.3.3-1 of NUREG 1431, Volume 1 (Reference 6.1 }, which states, "Table 3.3.3-1 shall be amended for each unit as necessary to list:

1. All Regulatory Guide 1.97, Type A instruments and
2. All Regulatory Guide 1.97, Category 1, non-Type A instruments specified in the unit's Regulatory Guide 1.97, Safety Evaluation Report."

Per RG 1.97, Type A applies to variables that provide primary information needed to permit Control Room operating personnel to take the specified manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events. Category 1 applies to instruments necessary to determine whether other systems important to safety are performing their intended function.

The following listing of instrumentation being removed from Turkey Point TS 3.3.3.3 by the proposed change identifies the RG 1.97 specified variable, functional Type and Category, as specified in Section 7.5.4, Regulatory Guide 1.97, Revision 3, of the Turkey Point Units 3 and 4 Updated Final Safety Analysis Report (FSAR).

RG 1.97 Variable Description / Instrument i Type Cat.

--Rx- ~oola_ri~-F>ress.-soun-ciary-Effiuerii- ---- -~~~~-~~~~; ~i;-~j~~;~;-~~~-~~~;-;-' ---------------

-~~-~~:~~;:~~~-~;~~~~~~~~~~~:~~~!- -~~~~~~~_<~~~~~--~~!_7} ___________ j_ ___~---- ---~---

Plant Vent Stack Wide Range : C 2

Monitor (RaD-6304) i containment Effluent Radioactivity Noble -concienserA"ii--E]ector-Exh-ausn----~---- ---~---

Gas from Identified Release Points Monitor (RaD-*-6417) i

-f,-pent-i=Li-e1-F>ooi vent-rvfonitor---:----~- --- ---~ ---

_(13_<!9_-?_-§.'! ~ ~)_ {~_~i! _~ _<?n_ly) _---_J_ -------- -------

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 6 of 21

- -------------------------------------------- -F>lant-Verii-sfacl<-wicie-R"an9_e _--:---- ---:-- ---

~- -~

i Containment Effluent Radioactivity Noble _MC?!:1l!~~-(~'?~:~?~4L __________ j _________ ~-------

i Gas (from Buildings or Areas, etc.) Spent Fuel Pool Vent Monitor : C  :

2

_ _______________________ _____________________ _(13.?!l?:.?_-~4 ~ ?1 {~_f!i! _~ _9_f!ly) _____ J_________ L______ _
. Condenser Air Ejector Exhaust :  :

,: Condenser. Air Removal System Mom"t or (R a -*- )  :, E  :, 2 0 6417

--~~-~-~~~-~~-~t-~-~~~ 1~~~~~~------------- -~~~~~et~!~~~~:;ae-Ran9-e--T---~----r---~---

---------------- ----------- -s-iJeiii-i=ue1_ F>_ool veiii-M"Ciiiitor--:---------:-------

~ ~

All Other Identified Release Points (RaD- _ 3 6418 ) (Unit 3 Only)  : E  : 2

.- -F>lantverii sfacl<-wicie-R"an9_e _-T--- ---:-- ---

~- -~

Particulates & Halogens - All Identified Monitor (RaD-6304)  :  :

Plant Release Points -s-i)eiit-Fue1_F>_oolveiit-M"Ciiiitor--;----~----r---~---

_(13.?!l?_-_?_-~4 ~ ?1 {~_f!i! _~ _9_f!ly) _---_j_ --------~ -------

As can be seen, the proposed change does not affect any instruments that involve RG 1.97 Type A, or Category 1 variables. Moreover, the subject instrumentation are not required for safety systems to accomplish any specified safety function, and are not subject to environmental or seismic qualification, physical or electrical separation, or backup (emergency) power capability. As such, the instruments are not required for TS inclusion as post-accident monitoring instrumentation based upon NUREG 1431, Volume 2 (Reference 6.6)

Additionally, 10 CFR 50.36(c)(2)(ii) establishes criteria for TS inclusion including Limiting Conditions of Operation (LCO). Evaluating the proposed changes against the 10 CFR 50.36(c)(2)(ii) criteria reveals that the proposed changes do not involve instrumentation subject to TS inclusion as an LCO, as indicated below:

(A) Criterion 1: Installed instrumentation that is used to detect, and indicate in the Control Room, a significant abnormal degradation of the reactor coolant pressure boundary.

  • The Plant Vent, Condenser Steam Jet Air Ejector and Unit 3 Spent Fuel Pit high-range noble gas monitoring instrumentation function to measure and display high-range noble gas activity in their respective exhaust vent paths in order to quantify radioactive releases during and following a design basis accident. The subject monitors satisfy RG 1.97 as Type C variables and hence by definition, have the capability to provide information indicative of a potential for being breached or the actual breach of the barriers to fission product release. However, the monitors are neither the only nor the most direct indication used for this diagnosis.

The Plant Vent, Condenser Steam Jet Air Ejector and Unit 3 Spent Fuel Pit high-range noble gas monitors are designated for indicating system operating status and providing diagnostic information to other primary indicators of radioactive releases. Hence, the monitors are not construed as necessary to determine whether other systems important to safety are performing their intended functions, a feature characteristic of a RG 1.97, Category 1 variable required for TS inclusion. The operability of the Plant Vent, Condenser SJAE and Unit 3 Spent Fuel Pit high-range noble gas monitors are not credited in the mitigation of any design basis accident.

As such, the subject monitors are not used as a primary means to detect, and indicate in the Control Room, a significant abnormal degradation of

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 7 of 21 the reactor coolant pressure boundary. These instruments do not satisfy Criterion 1.

(B) Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

The subject monitoring instrumentation are not process variables, design features, or operating restrictions that are an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The Plant Vent, Condenser Steam Jet Air Ejector or Unit 3 Spent Fuel Pit Exhaust high-range noble gas monitoring instrumentation cannot initiate a design basis accident or transient. These instruments do not satisfy Criterion 2.

(C) Criterion 3: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

The subject monitoring instrumentation are not part of the primary success path for accident or transient mitigation. Accident analyses do not credit automatic or manual action of the Plant-Vent, Condenser Steam Jet Air Ejector or Unit 3 Spent Fuel Pit Exhaust high-range noble gas monitoring instrumentation as part of any primary success path for design basis accident mitigation. These instruments do not satisfy Criterion 3.

(D) Criterion 4: A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

The Plant Vent, Condenser Steam Jet Air Ejector or Unit 3 Spent Fuel Pit Exhaust high-range noble gas monitoring instrumentation are not Maintenance Rule risk-significant components, are not credited in either Units' Probabilistic Risk Assessment (PRA) and are not of significant risk to public health and safety. These instruments do not satisfy Criterion 4.

Regarding the relocation of the TS requirements to the ODCM, Federal Register Notice 58 FR 39132 (Reference 6.8) contains the NRC's Final Policy Statement for TS improvements for nuclear power reactors. In reference to the 10 CFR 50.36(c)(2)(ii) criteria for TS inclusion, the Policy Statement states:

If a licensee elects to apply these criteria, the requirements of the removed specifications will be relocated to the FSAR or other licensee-control/ed documents. Licensees are to operate their facilities in conformance with the descriptions of their facilities and procedures in their FSAR. Changes to the facility or to procedures described in the FSAR are to be made in accordance with 10 CFR 50.59.

The proposed change relocates the high-range noble gas monitoring requirements and SRs for the Plant Vent, Condenser Steam Jet Air Ejector and Unit 3 Spent Fuel Pit exhaust pathways to the ODCM and applicable implementing procedures. FSAR references to the current TS requirements will

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 8 of 21 be updated accordingly. However, the accident monitoring functions for these instruments remain and no changes to their respective FSAR descriptions are proposed. The current TS required number of channel(s), applicable MODES and actions for inoperability do not change. In addition, the instrument channel checks and calibrations will continue to be performed in accordance with the Surveillance Frequency Control Program (SFCP). Any changes to the ODCM, FSAR or applicable plant implementing procedures will be controlled in accordance with 10 CFR 50.59.

  • In summary, the Plant Vent, Condenser Steam Jet Air Ejector and Unit 3 Spent Fuel Pit high-range noble gas monitoring instrumentation are not RG 1.97 Type A, or Category 1 variables, are not listed in NUREG 1431(Reference6.1) as post-accident monitoring instrumentation, and do not meet the 10 CFR 50.36(c)(2)(ii) criteria for TS inclusion. Furthermore, the proposed changes are administrative in nature and will not result in changes in the manner or frequency in which the subject instrumentation is maintained. The post-accident monitoring requirements for these instruments will be relocated to the ODCM and applicable plant procedures where future changes will be subject to the requirements of 10 CFR 50.59. As such, deleting Instrument 19, High Range Noble Gas Effluent Monitors, from TS 3.3.3.1, Table 3.3-5 and Table 4.3-4, by relocating the requirements for Instruments 19(a), Plant Vent Exhaust, 19(b), Unit 3 Spent Fuel Pit Exhaust, and 19(c), Condenser Air Ejectors, to the Turkey Point ODCM is reasonable.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria

  • NUREG-0737, Clarification of TMI Action Plan Requirements, identifies the items for which TS are required to provide assurance that facility operation is maintained within acceptable following implementation at each facility. Section 11.F.1 of NUREG-0737 specifies requirements for accident monitoring instrumentation including noble gas monitoring and iodine/particulate sampling.
  • 1967 Proposed General Design Criteria (GDC) 17 requires that means shall be provided for monitoring the containment atmosphere and the facility effluent discharge paths for radioactivity released from normal operations, from anticipated transients, and from accident conditions. An environmental monitoring program shall be maintained to confirm that radioactivity released to the environs of the plant have not been excessive.
  • 1967 Proposed GDC 18 requires that monitoring and alarm instrumentation shall be provided for fuel and waste storage and associated handling areas for conditions that might result in loss of capability to remove decay heat and to detect excessive radiation levels.
  • Generic Letter (GL) 83-37, NUREG-0737 Technical Specifications, requested licensees to provide applications for license amendments for applicable NUREG-0737 items, including noble gas effluent monitors considered helpful to the operator in accessing the plant condition during and following an accident. GL 83-37 further stated that it is desired that these monitors be operable at all times during plant operation, but they are not required for safe shutdown of the plant.

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 9 of21

  • RG 1.97, Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident, Revision 3, establishes the minimum number of variables to be monitored by the Control Room operating personnel during and following an accident. RG 1.97 defines Type C variables as variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product releases; Type E variables as variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases. For design and qualification, RG 1.97 states that Category 2 provides for qualification but does not include seismic, redundancy, continuous display or standby power; Category 3 provides for commercial-grade equipment that requires only offsite power.

The proposed change complies with the requirements of 10 50.36(c)(2)(ii) and does not alter the manner in which plant radiological monitoring functions are operated and maintained, consistent with 1967 Proposed GDC(s) 17 and 18, NUREG-0737, and RG1 .97. All applicable regulatory requirements will continue to be satisfied as a result of this proposed change.

4.2 No Significant Hazards Consideration FPL has evaluated whether o a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, Issuance of amendment, as discussed below.

1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The Plant Vent Exhaust, Condenser Air Ejectors Exhaust and Unit 3 Spent Fuel Pit Exhaust high-range noble gas monitoring instrumentation are not an initiator of any accidents previously evaluated, so the probability of accidents previously evaluated is unaffected by the proposed changes. The proposed changes will not impact any plant systems such that previously analyzed structures, systems, and components (SSCs) would be more likely to fail. The proposed changes do not adversely affect the protective and mitigative capabilities of the plant nor the offsite and control room dose projections associated with any design basis accident described in the FSAR.

Therefore, the proposed changes do not result in a significant increase in the probability or consequences of an accident previously evaluated.

2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change removes the subject instruments from the accident monitoring TS and as such is an administrative change in nature. The Plant Vent Exhaust, Condenser Air Ejectors Exhaust and Unit 3 Spent Fuel Pit Exhaust high-range noble gas monitoring instrumentation will continue to perform their specified function. Removal of the monitors from the TS will not create the possibility of a new or different kind of accident. No new or different interactions

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 10of21 with safety related systems or components are created. The proposed changes will not introduce new failure mechanisms, malfunctions, or accident initiators not already considered in the design and licensing bases. The possibility of a new or different malfunction of safety-related equipment is not created. No new accident scenarios, transient precursors, or limiting single failures are introduced as a result of these changes. There will be no adverse effects or challenges imposed on any safety-related system as a result of the proposed changes.

Therefore, the proposed changes do not create the possibility of a new or different accident from any accident previously evaluated.

3) Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The proposed change relocates the Plant Vent Exhaust, Condenser Air Ejectors Exhaust and Unit 3 Spent Fuel Pit Exhaust high-range noble gas monitoring requirements from TS 3.3.3.3, Accident Monitoring, to the Turkey Point ODCM, and as such is an administrative change in °nature. The changes do not adversely impact plant operating margins or the reliability of equipment credited in the safety analyses. Consequently, there will be no change in the ability to monitor post-accident plant conditions, radionuclide releases, and public doses.

The safety analyses acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation outside of the design basis.

Therefore, operation in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

Based on the above, FPL concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(b), and, accordingly, a finding of "no significant hazards consideration" is justified.

4.3 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

FPL has evaluated the proposed amendment for environmental considerations. The review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set for in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 11 of21 6.0 . REFERENCES 6.1 NUREG-1431, Standard Technical Specifications -Westinghouse Plants, Revision 4.0, Volume 1, Specifications (Accession No. ML12100A222) 6.2 NUREG-0737, Clarification of TMI Action Plan Requirements, dc;1ted November 1980.

(ML051400209) 6.3 NRC Letter from R. Croteau to T. F. Plunkett (FPL}, Turkey Point Units 3 and 4 -Issuance of Amendments Re: Relocation of Radiological Effluent Technical Specifications (TAC Nos. M95077 and M95078) dated July 31, 1996. (ML013390265) 6.4 Generic Letter (GL) 89-01, Implementation of Programmatic Controls for Radioactive Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program 6.5 NUREG-1301, Offsite Dose Calculation Manual Guidance, Standard Radiological Controls for Pressurized .Water Reactors (ML091050061) 6.6 NUREG-1431, Standard Technical Specifications -Westinghouse Plants, Revision 4.0, Volume 2, Bases (Accession No. ML12100A228)

6. 7 Regulatory Guide 1.97, Revision 3, Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident, May 1983. (ML003740282)
  • 6.8 NRC Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors,' dated July 22, 1993 (58 FR 39132)

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page 12 of 21 ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION PAGES (MARKUP)

(2 pages follow)

-I c TABLE 3.3-5 (Continued)

u
A m ACCIDENT MONITORING INSTRUMENTATION

"'1J 0 TOTAL M INIMUM APPLI-z NO.OF CHANNELS CABLE

-I I INSTRUMENT CHANNELS OPERABLE MODES ACTIONS c

z 14. In Core Thermocouples (Core Exit 4/core 2/core 1, 2, 3 31 , 32

=i en Thermocouples) quadrant quadrant V)

Qo 15. Containment High Range Area Radiation 2 1, 2, 3

.::.. 34

16. Reactor Vessel Level Monitoring 2(1) 1( 1) 1, 2, 3 37, 38 System
17. Neutron Flux, Backup NIS (Wide Range) 2 1 1, 2, 3 31, 32
18. DELETED
19. l-li§h Ran§e Noele Gas Effh.10nt Monitors
a. Plant Vent Exhablst 1 1 ALL 24
b. Unit 2 Spent Fuel Pit E><haust 1 1 ALL 34
6. GenElenseF AiF EjeeteFs 1 1, 2, 3 34

~

s:: 20. RWST Water Level 2 1 1, 2, 3 31 , 32 m

z 21. Steam Generator Water Level (Narrow Range) 2/stm. Gen. 1/stm. Gen. 1, 2, 3 31 , 32 0

s::

m z 22. Containment Isolation Valve Position Indication* 1/valve 1/valve 1, 2, 3 39

-I z TABLE NOTATIONS 0

en

1. A channel is eight sensors in a probe. A channel is OPERABLE if a minimum of four sensors are OPERABLE.
2. Inputs to this instrument are from instrument items 3, 4, 5 and 14 of this Table.
  • Applicable for containment isolation valve position indication designated as post-accident monitoring instrumentation (containment isolation valves which receive containment isolation Phase A, Phase B, or containment ventilation isolation signals).

TABLE 4.3-4 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure (Wide Range) SFCP SFCP
2. Containment Pressure (Narrow Range) SFCP SFCP
3. Reactor Coolant Outlet Temperature - T HOT SFCP SFCP (Wide Range)
4. Reactor Coolant Inlet Temperature - T coLo SFCP SFCP (Wide Range)
5. Reactor Coolant Pressure - Wide Range SFCP SFCP
6. Pressurizer Water Level SFCP SFCP
7. Auxiliary Feedwater Flow Rate SFCP SFCP
8. Reactor Coolant System Subcooling Margin Monitor SFCP SFCP
9. PORV Position Indicator (Primary Detector) SFCP SFCP
10. PORV Block Valve Position Indicator SFCP SFCP
11. Safety Valve Position Indicator (Primary Detector) SFCP SFCP
12. Containment Water Level (Narrow Range) SFCP SFCP
13. Containment Water Level (Wide Range) SFCP SFCP
14. In Core Thermocouples (Core Exit Thermocouples) SFCP SFCP
15. Containment - High Range Area Radiation Monitor SFCP SFCP*
16. Reactor Vessel Level Monitoring System SFCP SFCP
17. Neutron Flux, Backup NIS (Wide Range) SFCP SFCP
18. DELETED
19. Higl9 ReAge Noble Gas E#lueAt MeAiters
a. PlaAt VeAt Exl9aust SFGP SFGP
e. UAit 3 S~eAt Fuel Pit Exl9eust SFCP SFCP
c. Condenser Air Ejectors SFCP SFCP
20. RWST Water Level SFCP SFCP 21 . Steam Generator Water Level (Narrow Range) SFCP SFCP
22. Containment Isolation Valve Position Indication SFCP SFCP
  • Acceptable criteria for calibration are provided in Table ll.F.1-3 of NUREG-0737.

TURKEY POINT - UNITS 3 & 4 3/4 3-50 AMENDMENT NOS. -263-AND 2 Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page15of21 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION PAGES (CLEAN COPY)

(2 pages follow)

-I c TABLE 3.3-5 (Continued)

0
i;
:

m ACCIDENT MONITORING INSTRUMENTATION

"'U 0 TOTAL MINIMUM APPLI-z

-I NO.OF CHANNELS CABLE I INSTRUMENT CHANNELS OPERABLE MODES ACTIONS c

z 14. In Core Thermocouples (Core Exit 4/core 2/core 1, 2, 3 31, 32

~ Thermocouples) quadrant quadrant w

~ 15. Containment High Range Area Radiation

~

2 1 1,2,3 34

16. Reactor Vessel Level Monitoring 2(1) 1(1) 1,2,3 37,38 System
17. Neutron Flux, Backup NIS (Wide Range) 2 1 1, 2, 3 31,32
18. DELETED
19. DELETED

)>

s::

m

20. RWST Water Level 2 1 1,2,3 31, 32 z 21. Steam Generator Water Level (Narrow Range) 2/stm. Gen. 1/stm. Gen. 1, 2, 3 31,32 0

s::

m z 22. Containment Isolation Valve Position Indication* 1/valve 1/valve 1,2,3 39

-I z TABLE NOTATIONS 0

~

1. A channel is eight sensors in a probe. A channel is OPERABLE if a minimum of four sensors are OPERABLE.

ffi

)>

z 2. Inputs to this instrument are from instrument items 3, 4, 5 and 14 of this Table.

0

~ *- Applicable for containment isolation valve position indication designated as post-accident monitoring instrumentation (containment isolation valves which receive containment isolation Phase A, Phase B, or containment ventilation isolation signals).

TABLE4.3-4 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure (Wide Range) SFCP SFCP
2. Containment Pressure (Narrow Range) SFCP SfCP
3. Reactor Coolant Outlet Temperature - T Hor SFCP SFCP (Wide Range)~
4. Reactor Coolant Inlet Temperature - T coLo SFCP SFCP (Wide Range)
5. Reactor Coolant Pressure - Wide Range SFCP SFCP
6. Pressurizer Water Level SFCP SFCP
7. Auxiliary Feedwater Flow Rate SFCP SFCP
8. Reactor Coolant System Subcooling Margin Monitor SFCP SFCP
9. PORV Position Indicator (Primary Detector) SFCP SFCP
10. PORV Block Valve Position Indicator SFCP SFCP
11. Safety Valve Position Indicator (Primary Detector) SFCP SFCP
12. Containment Water Level (Narrow Range) SFCP SFCP
13. Containment Water Level (Wide Range) SFCP SFCP
14. In Core Thermocouples (Core Exit Thermocouples) SFCP SFCP
15. Containment - High Range Area Radiation Monitor SFCP SFCP*
16. Reactor Vessel Level Monitoring System SFCP SFCP
17. Neutron Flux, Backup NIS (Wide Range) SFCP SFCP
18. DELETED
19. DELETED
20. RWST Water Level SFCP SFCP
21. Steam Generator Water Level (Narrow Range) SFCP SFCP
22. Containment Isolation Valve Position Indication SFCP SFCP
  • Acceptable criteria for calibration are provided in Table ll.F.1-3 of NUREG-0737.

TURKEY POINT - UNITS 3 & 4 3/4 3-50 AMENDMENT NOS. -266-AND-258--

Turkey Point Nuclear Plant L-2016-230, Enclosure Docket Nos. 50-250 and 50-251 Page18of21 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION BASES PAGES (MARKUP)

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REVISION NO.: PROCEDURE TITLE: PAGE:

16 TECHNICAL SPECIFICATION BASES CONTROL PROGRAM 79 of 210 PROCEDURE NO.:

O-ADM-536 TURKEY POINT PLANT ATTACHMENT 2 Technical Specification Bases (Page 62 of 193) 3/4.3.3.3 (Continued)

Technical Specification Table 3.3-5, Item 14, lncore Thermocouples (Core Exit Thermocouples) , utilizes the term channel. There are NO channels of lncore Thermocouples as stated previously, the term Channel refers to one of the two QSPDS channels. NU REG 0737 ,

Section 11.F.2, Attachment 1, Item (3) describes what is required from instrumentation standpoint: A display should be provided with the capability for selective reading of a minimum of 16 OPERABLE thermocouples, four from each core quadrant. This description is the basis for our Technical Specification , and clarifies the requirement for lncore Thermocouples. If we have fewer than four thermocouples per core quadrant, Action 31 applies. If we have fewer than two thermocouples per quadrant, Action 32 applies. There is NO regulatory requirement that these two or four thermocouples per core quadrant be assigned to or divided between the two channels of QSPDS. The column heading TOTAL NO. OF CHANNELS, is also misleading for the lncore Thermocouples. There are more than four thermocouples in every core quadrant. It takes four thermocouples per core quadrant to satisfy the Technical Specifications and unrestricted operation with fewer than the TOTAL, but at least the MINIMUM is NOT allowed . For example, if there are only three operable thermocouples in a quadrant, in 30 days one must be fixed or a Special Report submitted within the next 14 days.

1Qo Fligh Range Noble Gas Condenser Air E.jeotor TS Table d.d 5, Aooident Monitoring Instrumentation, Item 1Qo, requires one Channel of Fligh Range Noble Gas Effluent Monitoring for Condenser Air E.jeotors to be OPERAQLE in MODES 1, 2, and d. The Steam Jet Air Ejeotor (SJAE) Speoial Partioulate, Iodine, and Noble Gas (SP ING) monitor (RAD 6417) provides this funotion .

REVISION NO. : PROCEDURE TITLE: PAGE:

16 TECHNICAL SPECIFICATION BASES CONTROL PROGRAM 80 of 210 PROCEDURE NO.:

O-ADM-536 TURKEY POINT PLANT ATTACHMENT 2 Technical S~ecification Bases (Page 63 of 193)

+Re SJAe SPING 1:1tilii!:es aR iRteFRal saffi13le 131:1ffi13 ts seRtiR1:1e1:1sly saffi13le aREl ffiSRiteF tRe EliSSR8F§e fFSffi tRe aiF ejesteF e*R81:1St ReaEleF. +Re SJ1A1e SPl~~G iRsl1:1Eles 13i13iR§, ¥al¥es, aREl seRRestieRs ts 13eFffiit R9Fffial 68ffij3liR§ aREl ts alle11\l ffiF SSRRestiR§ 13eFtal3le S8ffij3liR§ e~1:1i13ffieRt SF el3taiRiR§ §F813 Saffi13les. +Re SJAe SPING iRsl1:1Eles ffi1:1lti13le EletestieR sRaRRels tRat 13Fe1.iiEle ffiSRiteFiR§ sf tRe FaR§e sf Rel31e §8Se6 Fe~1:1iFeEl 13y ~e§1:1latei:y G1:1iEle ~ .Q7,

~e¥isieR d (~ .Qe Qe ts ~ . Q~ Q2 1=1Gitss) aREl tRe e*teREleEl FaR§e 13FessFil3eEl iR NY~eG Q:;zd:;z (ts a ffia*iffil:lffi sf ~ .Qe*Qa 1=1Gi1lss).

+Re SJAe SPING is sa13al3le sf 13Fe¥iEliR§ seRtiR1:1e1:1s saffi13liR§ aREl 13eFieElis ffiSRiteFiR§ sf FaElieieEliRes aREl 13aFtis1:1lates 1:16iR§ filteF saFtFiEl§es. +Re SJAe SPING 13Fe1.iiEles tRFee se13aFate EletestieR SR8RAels sf Rel31e §86. +Re F8R§eS iRsl1:1Ele tRe 1:11313eF FaR§e GRaRRel Q (~ .Qe*QQ ts ~ . Q~

  • Qa 1=1Gitss), tRe ffiiEl FaR§e GRaRRel :;z (2 .ae Q2 ts 4.Qe* Q2 1=1Gitss), a Rel tRe lew FaR§e GRaRRel a

(~ .Qe Q:;z ts e.Qe Q2 1=1Gitss). IRe13eFal3ility sf aRy eRe sf tRe tRFee Rel31e §as EletestieR sRaRRels Fe~1:1iFes eRti:y iR AstieR d4 wRisR Fe~1:1iFes iRitiatieR sf a 13Fe13laRReEl alteFRate ffietReEl sf ffiSRiteFiR§ tRe a1313m13Fiate 13arnffietm(s) witRiR 72 RSl:IFS.

Q1:1e te ffil:llti13le EletesteF SR8RRels aREl Saffi13liR§ S9Rfi§l:IFatieR6 13Fe¥iEleEl 13y tRe SJAe SPING, tRe 13Fe13laRReEl alteFRate ffietReEl6 1;1ai:y witR tRe seRElitieR aREl e*teRt sf tRe iRe13eFal3ility. +Re iRe13eFal3ility sf aRy siR§le EletestieR sRaRRel Elees NQ+ FeREleF tRe eRtiFe SJAe SPING iRe13eFal3le as leR§ as saffi13le tle~\1 te tRe FeffiaiRiR§ EletestieR sRaRRels is ffiaiRtaiReEl .

i;:ail1:1Fe sf tRe SJ1~e SPING saffi13le 131:1ffi13 (eF a Ry fail1:1Fe wRisR j3F9¥9Ats tRe Fe~l:liFeEl 6affi13le aiF fFSffi tlewiR§ tRFSl:l§R tRe EletesteFs) Elisal31es all SJAe SPING ffieAiteFiR§ sa13al3ilities aREl Fe~1:1iFes eAti:y iAte AstieA d4 aAEl iffi13leffieAtatieR sf alteFAate 13Fe13laAAeEl ffietReEl6 ffiF easR sf tRe Rel31e §a6 EletestieR sRaRRels .

~AJitR tRe saffi13le :flew 13atR ts tRe SJiA,e SPl~~G still a¥ailal31e, iRstallatieA sf tRe alteFRate saffi13le Fi§ te tRe SJ1~e SPING saffi13le iAlet liAe 13Fei.1iEles tRe sa13al3ility ts el3taiA FaElieieEliRe aREl 13aFtis1:1late saffi13les, ffiSRiteF :flaw, aAEl el3taiR §as §Fal3 saffi13les. Nete tRat iRstallatieA sf tRe alteFRate saffi13liR§ Fi§ 13Fe¥iEles a 13Fe13laRReEl alteFAate ffietRaEl ffiF al3taiAiA§ saffi13les, l31:1t Elees NQ+ FestaFe OPeRABILITY sf tRe SJAe SPING Ri§R FaA§e R913le §8S ffiSRiteFiA§ f1:1RstieR .

REVISION NO.: PROCEDURE TITLE: PAGE :

16 TECHNICAL SPECIFICATION BASES CONTROL PROGRAM 81 of 210 PROCEDURE NO.:

O-ADM-536 TURKEY POINT PLANT ATTACHMENT 2 Technical S~ecification Bases (Page 64 of 193) i;:aih:IFe ef SJAe SPING GRaAAel a FeEll::liFes eAti=;i iAte JA1stieA 34 . An alteFAate FT1etRed ef FTISAiteFiAg tRe Ael31e gas is te 1::1se PFesess RadiatieA MeAiteFiAg SysteFTI ~PRMS~ R 1a ~1 .Qe Qe te 1.Qe Qd 1=1Gitss~ l:IAtil tRe sRaAAel FaAge is e*seeded . ),AJitR tRe SJAe SPING GRaAAel a iAepeFal31e a Ad tRe FaAge ef PRMS R 1a e*seeded ,

eetaiA gml3 saFTlples every 12 Re1::1Fs.

i;:ail1::1Fe ef SJ!l.e SPING GRaAAel +FeEll::liFes eAtr:y iAte AstieA d4 . An alteFAate FT1etRed ef FT1eAiteFiAg tRe Ael31e gas is te 1::1se SJJAie SPING GRaAAel a 9F PRMS R 1a l::IAtil tRe FaAge eHRese SRaAAels is e*seeded . ),AJitR tRe SJAe SPl~JG GRaAAel a aAd PRMS R 1a iAepeFal31e, eF tReiF FaAges e*seeded , FTlaiA steaFTI saA 13e saFTlpled ever:;i 12 Re1::1Fs, eF eetaiA gFal3 saFTlples ever:;i 12 Re1::1Fs 1::1Atil tRe level is witRiA tRe FTISAitmiAg FaAge prnvided 13y detestieA GRaAAel Q.

i;:ail1::1Fe ef SJAe SPING GRaARel g FeE11::1iFes eAtr:y iAte AstieA d4 . AA alteFAate FT1etRed ef FT1eAiteFiAg tRe Ael31e gas is te 1::1se SJAe SPl~JG GRaAAel a 9F PRMS R 1a UAtil tRe FaAge ef tRese SRaAAels is e*seeded . >AlitR tRe SJAe SPING GRaAAel a aAd PRMS R 1a iAepemele eF tReiF mAges e*seeded , eetaiA gml3 saFT1ples every 12 R91::1FS.

3/4.3 .3.4 Deleted 3/4.3.3.5 Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control , as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60 , 63 , and 64 of Appendix A to 10 CFR Part 50.

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