L-2014-266, Response to NRC Technical Specifications Branch Request for Additional Information Regarding License Amendment Request No. LAR-229

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Response to NRC Technical Specifications Branch Request for Additional Information Regarding License Amendment Request No. LAR-229
ML14252A228
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 08/29/2014
From: Kiley M
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2014-266
Download: ML14252A228 (18)
v • d • e


Text

0 FPL.

L-2014-266 10 CFR 50.90 August 29, 2014 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 DPR-31 and DPR-41 Response to NRC Technical Specifications Branch Request for Additional Information regarding License Amendment Request No. LAR-229, "Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program"

References:

1) M. Kiley (FPL) letter (L-2014-033) to NRC Document Control Desk, "License Amendment Request No. LAR-229 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program," dated April 9, 2014 (ADAMS Accession No. ML14105A042).
2) A. Klett (NRC) letter to M. Nazar (FPL), "Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information on license amendment request to revise technical specifications to implement TSTF-425, Revision 3, 'Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specifications Task Force (RITSTF) Initiative 5B' (TAC Nos. MF3931 and MF3932),"

dated August 7, 2014 (ADAMS Accession No. ML14212A713).

By letter dated April 9, 2014 (Reference 1), Florida Power & Light Company (FPL) submitted a license amendment request (LAR) to Renewed Facility Operating License Nos. DPR-31 and DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4. The proposed amendments would revise the Technical Specifications (TS) to implement Technical Specifications Task Force (TSTF)

Traveler 425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control-Risk Informed Technical Specifications Task Force (RITSTF) Initiative 5B."

By letter dated August 7, 2014 (Reference 2), the NRC Technical Specifications Branch submitted a request for additional information (RAI) related to the proposed LAR. The responses to the four questions in the RAI are provided in Attachment 1. Attachment 2 contains revised TS marked up pages that support the responses to the RAI (LAR Attachment 3). Attachment 3 contains revised pages to LAR Attachment 6, "Cross-Reference Between TSTF-425 and Turkey Point Technical Specifications."

Florida Power &Light Company o 19 9760 SW 344t' Street, Florida City, Florida 33035 Fl..

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Page 2 of 2 This submittal does not alter the no significant hazards consideration or environmental assessment previously submitted by FPL in Reference 1.

This submittal contains no new commitments or revisions to existing commitments.

The Turkey Point Nuclear Safety Committee has reviewed and approved this response to the license amendment application. In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.

Should you have any questions regarding this submittal, please contact Mr. Robert J. Tomonto, Licensing Manager, at (305) 246-7327.

I declare under penalty of perjury that the foregoing is true and accurate.

Executed on the 29 day of 45'4

  • 2014.

Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachments (3) 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 Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 1 Page 1 of 6 Attachment I Turkey Point Nuclear Plant Unit Nos. 3 and 4 License Amendment Request No. LAR-229 Response to Request for Additional Information

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 1 Page 2 of 6 Response to Request for Additional Information The following information is provided by Florida Power & Light Company (FPL) in response to the U.S. Nuclear Regulatory Commission's (NRC) Request for Additional Information. The information was requested to support the review of License Amendment Request (LAR)-229, "Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program." LAR-229 was submitted to the NRC by FPL letter L-2014-033 dated April 9, 2014 (ADAMS Accession No. ML14105A042).

By letter from NRC (A. Klett) to FPL (M. Nazar), dated August 7,2014 (ADAMS Accession No. ML14212A713), the NRC Technical Specifications Branch provided a request for additional information (RAI). The RAI consisted of four questions. The responses to the questions are provided below. Revised marked-up Technical Specifications pages are provided in Attachment 2.

Revised pages for LAR Attachment 6, "Cross-Reference Between TSTF-425 and Turkey Point Technical Specifications" are provided in Attachment 3.

STSB RAI-1 The licensee proposed to replace specific surveillance frequencies in Technical Specifications (TSs) Tables 4.1-1, 4.3-1, 4.3-2, 4.3-4, 4.3-6, and 4.4-3 with "SFCP." However, Florida Power &

Light did not incorporate what the acronym "SFCP" stands for in the proposed TSs.

Please provide a proposed change to TSs Tables 4.1-1, 4.3-1, 4.3-2, 4.3-4, 4.3-6, and 4.4-3 that is consistent with Technical Specification Task Force (TSTF)-425 and clearly states that SFCP stands for the surveillance frequency control program in the Turkey Point TSs.

For examples, review NRC-approved license amendment requests for Surry Power Station Units 1 and 2, Hope Creek Generating Station Unit 1, and Salem Nuclear Generating Station Units 1 and 2 (Agencywide Documents Access and Management System Accession Nos. ML110740033, ML103410243, and ML110410691, respectively).

FPL Response FPL reviewed the license amendment requests identified above, and also reviewed the recently approved Seabrook license amendment, dated July 24, 2014 (ADAMS Accession No. ML13212A069). This proposed change is consistent the Seabrook license amendment.

FPL revised TS Table 1.1, "Frequency Notation" to include the definition for SFCP. SFCP is defined as "In accordance with the Surveillance Frequency Control Program." With SFCP defined in Table 1.1, Tables 4.1-1, 4.3-1, 4.3-2, 4.3-4, 4.3-6 and 4.4-3 are unchanged. A marked-up TS page for Table 1.1 is provided in Attachment 2.

STSB RAI-2 Surveillance Requirement (SR) 4.2.1.1.b requires monitoring and logging the indicated Axial Flux Difference (AFD) for each operable excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 1 Page 3 of 6 at least once per 30 minutes thereafter, when the alarm used to monitor the AFD is inoperable.

The licensee proposes to delete, "at least once per" from SR 4.2.1.1.b. After the deletion, SR 4.2.1.1.b requires monitoring and logging the indicated AFD for each operable excore channel hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the alarm used to monitor the AFD is inoperable. The phrasing of the proposed SR is incoherent.

Please provide a proposed change to Turkey Point SR 4.2.1.1 .b that is coherent and consistent with TSTF-425.

FPL Response FPL did not intend to change TS surveillance requirement 4.2.1.1.b. The deletion was an editorial error and unintended. SR 4.2.1.1.b is unchanged by this license amendment request.

A revised marked-up TS page without the deletion and an unchanged SR 4.2.1 .1 .b is provided in .

STSB RAI-3 Surveillance requirement 4.2.4.1 currently states:

The quadrant power tilt ratio shall be determined to be within the limit above 50%

of rated thermal power by:

a. Calculating the ratio at least once per 7 days when the power range upper detector high flux deviation and power range lower detector high flux deviation alarms are operable, and
b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state operation when either alarm is inoperable.

The licensee proposes to change SR 4.2.4.1 to (added wording is in italic font):

The quadrant power tilt ratio shall be determined to be within the limit above 50%

of rated thermal power:

a. In accordance with the Surveillance Frequency ControlProgram by calculating the ratio when the power range upper detector high flux deviation and power range lower detector high flux deviation alarms are operable in accordance with the Surveillance Frequency Control Program,and
b. By calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state operation when either alarm is inoperable.

The proposed surveillance requirement 4.2.4.1 has added duplicate wording.

Explain the need for the duplicate wording, or provide a change to SR 4.2.4.1 that does not have duplicate wording.

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 1 Page 4 of 6 FPL Response FPL amended this SR 4.2.4.1 in its final version for clarity. The surveillance frequency was relocated to the beginning of the sentence. An editorial error resulted in the second required change "Insert 1" being left in the markup. The second change "Insert 1" is deleted.

A revised marked-up TS page without the second insertion for surveillance requirement 4.2.4.1 is provided in Attachment 2. Note that the revised marked-up page incorporates TS Amendment 260/255 which revised the page number from 3/4 2-15 to 3/4 2-13.

SR 4.2.4.1.a now states

a. In accordance with the Surveillance Frequency Control Program by calculating the ratio when the Power Range Upper Detector High Flux Deviation and Power Range Lower Detector High Flux Deviation Alarms are OPERABLE, and STSB RAI-4 Surveillance requirement 4.5.2.b currently states:

Each ECCS component and flow path shall be demonstrated operable:

b. At least once per 31 days by:

.3) Verifying that each RHR Pump develops the indicated differential pressure applicable to the operating conditions in accordance with Figure 3.5-1 when tested pursuant to Specification 4.0.5.

Surveillance requirement 4.8.1.1.2.1.2 currently states:

At least once per 10 years by:

.2) For Unit 4 only, performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The licensee proposes to change SR 4.5.2.b to (new wording is in italic font):

Each ECCS component and flow path shall be demonstrated operable:

b. In accordance with the Surveillance Frequency Control Program by:

.3) Verifying that each RHR Pump develops the indicated differential pressure applicable to the operating conditions in accordance with Figure 3.5-1 when tested pursuant to Specification 4.0.5.

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 1 Page 5 of 6 The licensee proposes to change SR 4.8.1.1.2.1.2 to (new wording is in italic font):

In accordance with the Surveillance Frequency Control Program by:

.2) For Unit 4 only, performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

Turkey Point TS 4.0.5 addresses SRs for inservice inspection and testing of ASME Code Class 1, 2, and 3 components.

The NRC staff model safety evaluation for TSTF-425 states that all surveillance frequencies can be relocated except for frequencies that reference other approved programs for the specific interval (such as the Inservice Testing Program or the Primary Containment Leakage Rate Testing Program).

The licensee's proposed change to SRs 4.5.2.b and 4.8.1.1.2.1.2 applies the surveillance frequency control program to inservice inspection and testing of American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components; this is not allowed.

Please explain the proposed change, remove the proposed change to SRs 4.5.2.b and 4.8.1.1.2.1.2, or provide a change to SRs 4.5.2.b and 4.8.1.1.2.1.2 that does not apply the surveillance frequency control program to inservice inspection and testing of ASME Code Class 1, 2, and 3 components.

FPL Response Surveillance requirements 4.5.2.b and 4.8.1.1.2.1 contained multiple surveillance requirements.

When revising surveillance requirements 4.5.2.b and 4.8.1.1.2.1, FPL inadvertently included surveillance requirements 4.5.2.b.3) and 4.8.1.1.2.1.2 into the surveillance frequency control program. FPL has revised the changes such that 4.5.2.b.3) and 4.8.1.1.2.1.2 are tested at the currently required frequency in accordance with Specification 4.0.5 and are not included in the Surveillance Frequency Control Program.

SR 4.5.2.b.3) now states:

.3) At least once per 31 days by verifying that each RHR Pump develops the indicated differential pressure applicable to the operating conditions in accordance with Figure 3.5-1 when tested pursuant to Specification 4.0.5.

SR 4.8.1.1.2.1.2 now states:

.2) At least once per 10 years, for Unit 4 only, performing a pressure test of those portions of the diesel fuel oil system designed to Section Il1, subsection ND of the ASME Code in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 1 Page 6 of 6 Revised marked-up TS pages for these surveillance requirements are provided in Attachment 2.

Note that the revised marked-up page for SR 4.8.1.1.2.1.2 incorporates TS Amendment 260/255 which revised the page number from 3/4 8-9 to 3/4 8-10.

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 2 Attachment 2 Turkey Point Nuclear Plant Unit Nos. 3 and 4 License Amendment Request No. LAR-229 Marked-Up Technical Specifications Pages (This coversheet plus 6 pages)

Insert 1 Note that Insert I capitalization and punctuation is varied based on the use in each specific surveillance requirement.

In accordance with the Surveillance Frequency Control Program

TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

P Completed prior to each release.

In accordance with the Surveillance Frequency Control Program I TURKEY POINT - UNITS 3 & 4 1-7 AMENDMENT NOS. "ST"AND 132-

POWER DISTRIBUTION LIMITS SURVEILL ANCEF REQUIREMENTS 4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 50% o RATED THERMAL POWER by: "1"

a. Monitoring the indicated AFD for each OPERABLE excore channel:
1) 'k =8t G..= POF 7 days when the alarm used to monitor the AFD is OPERABLE, and
2) At least once per hour for the first 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after restoring the alarm used to monitor the

,,t a I AFD to OPERABLE status.*

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the alarm used to monitor the AFD is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2.1. The target flux difference of each OPERABLE excore channel shall be determined by measurement at-ia*L e ,ast 92 Effect

, Full. ,w. B;,y. The provisions of Specification 4.0.4 are not applicable.

4.2.1.3 target flux difference shall be updated at le;at ..m,. pr. 31, Eff.,' Full ,..w.r Boy; by either determi g the target flux difference pursuant to Specification 4.2.1.2 above or by linear interpolation between ><

the mo recently measured value and the predicted value at the end of the cycle life. The provisions of Speci ation 4.0.4 are not applicable.

In accordance with the Surveillance Frequency Control Program, the

  • Performance of a functional test to demonstrate OPERABILITY of the alarm used to monitor the AFD may be substituted for this requirement.

TURKEY POINT - UNITS 3 & 4 3/4 2-2 AMENDMENT NOS. 1-6 and +50

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and
3. Identify and correct the cause of the out-of -limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.
d. The provisions of Specifications 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER "y:

a. Galekle"e the ratio at least e,,e per 7 days when the Power Range Upper Detector High Flux ZDeviation a. C',ut:.*the ',eas=t onepr1 ratio atRange and Power ordrn Lower Detector taysat High Flux Deviation prto are OPERABLE, Alarms hnihraami and Cs',cthe ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state operation when either alarm is

~~~~~i~noperae.Bcacltn 4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained either from two sets of four symmetric thimble locations or full-core flux map, or by incore thermocouple map is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.2.4.3 If the QUADRANT POWER TILT RATIO is not within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the POWER DISTRIBUTION LIMITS of 3.2.2 and 3.2.3 are within their limits, a Special Report in accordance with 6.9.2 shall be submitted within 30 days including an evaluation of the cause of the discrepancy.

In accordance with the Surveillance Frequency Control Program by calculating TURKEY POINT - UNITS 3 & 4 3/4 2-13 AMENDMENT NOS. 260-AND 266

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS component and flow path shall be demonstrated OPERABLE:

a. .A4t l6c-.t n-o-e pcr 12 h*;;. by verifying by control room indication that the following valves are in the indiced positions with power to the valve operators removed:

Valve Nu ber Valve Function Valve Position 864A a B Supply from RWST to ECCS Open 862A nd B RWST Supply to RHR pumps Open 863 and B RHR Recirculation Closed 8A and B H.H.S.I. to Hot Legs Closed CV-758* RHR HX Outlet Open To permit temporary operation of these valves for surveillance or maintenance purposes, power may be restored to these valves for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. At least ene per 31, days by:

r 1)',Verifying that the ECCS piping is full of water by venting the ECCS pump casings and

-accessibledischarge piping, Insert 1

2) erifying that each valve (manual, power-operated, or automatic) in the flow path that is not It least once locked, sealed, or otherwise secured in position, is in its correct position, and er 31 days, 3)I that each RHR Pump develops the indicated differential pressure applicable to the y verifying operating conditions in accordance with Figure 3.5-1 when tested pursuant to Specification 4.0.5.
c. Atd leat p days by:

EInsert 1 I 1) Verifying that each SI pump develops the indicated differential pressure applicable to the I I operating conditions when tested pursuant to Specification 4.0.5.

SI pump Ž_1083 psid at a metered flowrate > 300 gpm (normal alignment or Unit 4 SI pumps aligned to Unit 3 RWST), or

Ž_1113 psid at a metered flowrate 2!280 gpm (Unit 3 SI pumps aligned to Unit 4 RWST).

  • Air Supply to HCV-758 shall be verified shut off and sealed closed once per 31 days.

TURKEY POINT - UNITS 3 & 4 3/4 5-5 AMENDMENT NOS. AND 1"85-

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Cohtnuedl-h.r after any modifications which could affect diesel generator

° interdependence by starting all required diesel generators simultaneously and verifying

/ that all required diesel generators provide 60 + 0.6 Hz frequency and 3950-4350 volts in less than or equal to 15 seconds: and At leat eme pe 10 yars by-.

  • )* *raining each fuel oil storage tank, removing the accumulated sediment and I1nsert 1 cleaning the tank.*
2) _-y-Unit 4 only, performing a pressure test of those portions of the diesel fuel oil At ls system designed to Section III, subsection ND of the ASME Code in accordance At least once per with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable I10 years, for lAddenda.

4.8.1.1.3 ReDorts - (Not Used)

  • A temporary Class III fuel storage system containing a minimum volume of 38,000 gallons of fuel oil may be used for up to 10 days during the performance of Surveillance Requirement 4.8.1.1.2i.1 for the Unit 3 storage tank while Unit 3 is in Modes 5, 6, or defueled. If the diesel fuel oil storage tank is not returned to service within 10 days, Technical Specification 3.8.1.1 Action b and 3.8.1.2 Action apply to Unit 4 and Unit 3 respectively.

TURKEY POINT - UNITS 3 &4 3/48-10 AMENDMENT NOS. 26e AND *205A

Turkey Point Units 3 and 4 L-2014-266 Docket Nos. 50-250 and 50-251 Attachment 3 Attachment 3 Turkey Point Nuclear Plant Unit Nos. 3 and 4 License Amendment Request No. LAR-229 Cross-Reference Between TSTF-425 and Turkey Point Technical Specifications (This coversheet plus 2 pages)

Turkey Point Units 3 and 4 L-2014-033 Docket Nos. 50-250 and 50-251 Attachment 6 I TSTF-425 Turkey Point Surveillance Requirements Surveillance Surveillance Requirement Requirement 3.4.15, RCS Leakage Detection Instrumentation Perform Channel Check - containment atmosphere SR 3.4.15.1 radioactivity monitor 4.4.6.1, Perform Channel Operational Test - containment atmosphere SR 3.4.15.2 Table 4.3-3 radioactivity monitor Perform Channel Calibration - containment sump monitor SR 3.4.15.3 4.4.6.1.b Perform Channel Calibration - containment atmosphere SR 3.4.15.4 4.4.6.1, radioactivity monitor Table 4.3-3 Perform Channel Operational Test - containment air cooler SR 3.4.15.5 condensate flow rate monitor 3.4.16, RCS Specific Activity Determine gross specific activity SR 3.4.16.1 4.4.8, Table 4.4-4 Determine Dose Equivalent 1-131 SR 3.4.16.2 4.4.8, Table 4.4-4 Determine E-Bar SR 3.4.16.3 ..

Tritium determination ----- 4.4.8, Table 4.4-4 Determine Dose Equivalent XE-133 ----- 4.4.8, Table 4.4-4 3.4.17, RCS Loop Isolation Valves Verify valves open, SR 3.4.17.1C4 3.4.19, RCS Loops - Test ExceptionsSR341 V erify Therm al Power >:P-7 .

.- SR 3 . .9 .--...

TURKEY POINT TECHNICAL SPECIFICATIONS 314.4.7, Chemistry Dissolved oxygen, Chloride, Fluoride L ... 4.4.7, Table 4.4-3 3/4.4.9.2, RCS Vents Verify vent path 4.4.11 3.5 Emergency Core Cooling Systems (ECCS) 3.5.1, Accumulators Verify isolation valve open SR 3.5.1.1 4.5.1.1.a.3 Verify water volume SR 3.5.1.2 4.5.1.1.a.1 Verify nitrogen cover pressure SR 3.5.1.3 4.5.1.1.a.2 Verify boron concentration SR 3.5.1.4 4.5.1.1.b Verify power removed from isolation valve operator SR 3.5.1.5 4.5.1.1.c Check valve operability .... 4.5.1.1.d 3.5.2, ECCS - Operating Verify valve positions with power removed SR 3.5.2.1 4.5.2.a Verify flow path valve positions SR 3.5.2.2 4.5.2.b.2 Verify piping full of water SR 3.5.2.3 4.5.2.b.1 Verify valve automatic actuations SR 3.5.2.5 4.5.2.f.1 Verify automatic pump starts SR 3.5.2.6 4.5.2.f.2.a 4.5.2.f.2.b Verify throttle valve positions SR 3.5.2.7 4.5.21g.2 Inspect containment sump suction inlets SR 3.5.2.8 4.5.2.e.3 Page 8 of 13

Turkey Point Units 3 and 4 L-2014-033 Docket Nos. 50-250 and 50-251 Attachment 6 TSTF-425 Turkey Point Surveillance Requirements Surveillance Surveillance Requirement Requirement Operatepumps ----- 4.7.1.6.2 Feed steam generatorswith pumps .... 4.7.1.6.3 Operate diesel driven pump --- 4.7.1.6.4.a Diesel inspection .... 4.7.1.6.4.b 3/4.7.7, Sealed Source Contamination Test sources in use .... 4.7.7.2.a 3.8 Electrical Power Systems 3.8.1, AC Sources Verify correct breaker alignment and indicated power SR 3.8.1.1 4.8.1.1.1.a 4.8.1.1.2.a.6 Verify starts from standby conditions SR 3.8.1.2 4.8.1.1.2.a.4 Verify DG is synchronized and loaded SR 3.8.1.3 4.8.1.1.2.a.5 Verify day tank volume SR 3.8.1.4 4.8.1.1.2.a.1 Check for and remove accumulated water SR 3.8.1.5 4.8.1.1.2.c Verify fuel oil transfer system operates SR 3.8.1.6 4.8.1.1.2.b Verify diesel starts from standby condition SR 3.8.1.7 4.8.1.1.2.a.4 Verify transfer of AC power sources SR 3.8.1.8 4.8.1.1.1 .b Verify DG rejects a load SR 3.8.1.9 4.8.1.1.2.g.2 Verify DG does not trip on load rejection SR 3.8.1.10 4.8.1.1.2.g.3 Verify on a loss of power signal SR 3.8.1.11 4.8.1.1.2.g.4 Verify on an ESF actuation signal SR 3.8.1.12 4.8.1.1.2.g.5 Verify DG's noncritical automatic trips are bypassed SR 3.8.1.13 Verify DG operates for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.8.1.14 4.8.1.1.2.g.7 Verify DG state voltage and frequency SR 3.8.1.15 4.8.1.1.2.g.7 Verify DG synchronizes SR 3.8.1.16 4.8.1.1.2.g.9 Verify ESF overrides test mode SR 3.8.1.17 4.8.1.1.2.g.10 Verify interval between each sequenced load block. SR 3.8.1.18 4.8.1.1.2.g.12 Verify on LOOP with an ESF SR 3.8.1.19 4.8.1.1.2.g.6 Verify simultaneously start SR 3.8.1.20 4.8.1.1.2.h Verify auto-connected loads .... 4.8.1.1.2.g.8 Verify fuel oil transferpump transfers oil 4.8.1.1.2.g. 11 Verify DG lockout relay 4.8.1.1.2.g.13 A

Clean fuel oil storage tank 4.8.1.1.2.1.1 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air Verify fuel oil storage tank volume SR 3.8.3.1 4.8.1.1.2.a.2 Verify lubricating oil inventory SR 3.8.3.2 4.8.1.1.2.a.3 Verify DG air start receiver pressure SR 3.8.3.4 ....

Check for and remove accumulated water SR 3.8.3.5 4.8.1.1.2.d 3.8.4, DC Sources - Operating Verify battery terminal voltage SR 3.8.4.1 4.8.2.1.a.2 Verify each battery charge supplies SR 3.8.4.2 4.8.2.1.c.3 Page 12 of 13

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