CNL-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program...

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Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program...
ML20017A303
Person / Time
Site: Watts Bar  Tennessee Valley Authority icon.png
Issue date: 01/17/2020
From: Polickoski J
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-19-084, EPID L-2018-LLA-0279, WBN-TS-18-14
Download: ML20017A303 (155)


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-19-084 January 17, 2020 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391

Subject:

Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) (EPID L-2018-LLA-0279)

References:

1. TVA Letter to NRC, CNL-18-067, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14), dated October 12, 2018 (ML18288A352)
2. TVA Letter to NRC, CNL-19-035, Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) (EPID L-2018-LLA-0279), dated May 7, 2019 (ML19127A323)
3. TVA Letter to NRC, CNL-19-054, Correction to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) (EPID L-2018-LLA-0279),

dated June 6, 2019 (ML19157A302)

4. TVA Letter to NRC, CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) (EPID L-2018-LLA-0279),

dated August 29, 2019 (ML19242D967)

U.S. Nuclear Regulatory Commission CNL-19-084 Page 2 January 17, 2020

5. NRC Letter to TVA, Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 (EPID L-2017-LLA-0287), dated August 30, 2018 (ML18197A307)
6. NRC Letter to TVA, Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments Regarding Technical Specification Changes Pertaining to 120-Volt Alternating Current Vital Buses (EPID L-2018-LLA-0050), dated June 7, 2019 (ML19098A774)
7. NRC Letter to TVA, Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 129 and 32 Regarding Changes to Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9 (EPID L-2018-LLA-0492),

dated November 26, 2019 (ML19238A005)

8. NRC Letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection (EPID L-2017-LLA-0391),

dated August 27, 2019 (ML18277A110)

9. NRC Letter to TVA, Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Regarding Revision to Watts Bar Nuclear Plant, Unit 2, Technical Specification 4.2.1, "Fuel Assemblies," and Watts Bar Nuclear Plant, Units 1 and 2, Technical Specifications Related To Fuel Storage (EPID L-2017-LLA-0427), dated May 22, 2019 (ML18347B330)
10. NRC letter to TVA, Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 130 and 33 Regarding Adoption of Technical Specifications Task Force Traveler TSTF-500, DC Electrical Rewrite - Update to TSTF-360 (EPID L-2018-LLA-0494), dated December 9, 2019 (ML19276E557)

In Reference 1, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for the Watts Bar Nuclear Plant (WBN) Units 1 and 2 to modify the WBN Technical Specifications (TS), by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, in accordance with Technical Specification Task Force (TSTF) Standard Technical Specifications Change TSTF-425, Revision 3. In Reference 2, TVA submitted a response to a request for additional information (RAI) regarding this LAR. In Reference 3, TVA submitted a correction letter for an element of the LAR. In Reference 4, TVA submitted a supplement to the LAR to rescind one of the proposed Surveillance Requirements (SR)

Frequency changes and to make several errata changes to the LAR.

U.S. Nuclear Regulatory Commission CNL-19-084 Page 3 January 17, 2020 The purpose of this letter is to provide an additional supplement to the Reference 1 LAR to address several overlapping licensing actions, as described below.

x In Reference 5, the Nuclear Regulatory Commission (NRC) issued License Amendments 122/21 for WBN Units 1 and 2, respectively, which revised Surveillance Requirements (SRs) 3.2.4.1 and 3.2.4.2 with frequencies that are also proposed to be controlled under the Surveillance Frequency Control Program (SFCP) by Reference 1. These amendments were inadvertently not included in the Reference 1 LAR.

x In Reference 6, the NRC issued License Amendments 126/29 for WBN Units 1 and 2, respectively, after the Reference 1 LAR had been submitted. These amendments revised TS Pages 3.8-42/3.8-38 that the Reference 1 LAR markup and clean pages had been based. In Reference 7, the NRC issued License Amendments 129/32 for WBN Units 1 and 2, respectively, which further revised these pages, and also revised SRs 3.8.7.1 and SRs 3.8.8.1 with frequencies that are also proposed to be controlled under the SFCP by Reference 1.

x In Reference 8, the NRC issued License Amendments 128/31 for WBN Units 1 and 2, respectively, after the Reference 1 LAR had been submitted. These amendments revised certain TS pages that the Reference 1 LAR markup and clean pages had been based.

Accordingly, in Enclosure 1 TVA is providing change instructions to update the Reference 1 LAR based on the pages issued with the Reference 5, 6, 7, and 8 License Amendments.

Additional changes unrelated to the SFCP are included to correct administrative formatting in accordance with the TSTF-GG-05-01, Revision 1, Writers Guide for Plant-Specific Improved Technical Specifications, and the formatting conventions of NUREG-1431, Revision 4.0, Standard Technical Specifications Westinghouse Plants.

In Reference 9, the NRC issued License Amendments 125/27 for WBN Units 1 and 2, respectively, which revised an existing surveillance (SR 3.9.9.1) whose Frequency was proposed to be controlled under the SFCP in the Reference 1 LAR. These amendments also added a new SR 3.7.18.1 which is candidate for inclusion in the SFCP. However, as noted in Reference 9, Amendments 125/27 are not scheduled for implementation until prior to startup from the outage where any number of tritium producing burnable absorber rods is inserted in the Watts Bar Nuclear Plant, Unit 2 reactor core, not to exceed December 31, 2022. The tritium producing burnable absorber rods are currently scheduled to be inserted for WBN Unit 2 prior to the start of WBN Unit 2 Cycle 4 (projected in Fall 2020), which will exceed the requested 60-day implementation period for the Reference 1 LAR. In order to avoid having to submit a supplemental LAR to capture these SRs within the SFCP, TVA proposes a bifurcated implementation schedule for the Reference 1 LAR.

The SR 3.7.18.1 and 3.9.9.1 Frequencies will be established under the SFCP consistent with the above License Amendments 125/27 implementation schedule, with the balance of the Reference 1 LAR proposed changes implemented within 60-days of approval. Finally, Amendments 125/27 established the Spent Fuel Storage Rack Monitoring Program under TS Section 5.7.2.21, which was also the proposed section number for the discussion of the

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U.S. Nuclear Regulatory Commission CNL-19-084 Page 5 January 17, 2020

Enclosures:

1. Change Instructions to the October 12, 2018, License Amendment Request Associated with License Amendments 122/21, 126/29, 128/31, and 129/32, and Other Miscellaneous Changes
2. Change Instructions to the October 12, 2018, License Amendment Request Associated with License Amendments 125/27
3. Change Instructions to the October 12, 2018, License Amendment Request Associated with License Amendments 130/33
4. Clean Version of Attachment 7 to the October 12, 2018, License Amendment Request Showing Revisions Made to Date cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation

Enclosure 1 Change Instructions to the October 12, 2018, License Amendment Request Associated with License Amendments 122/21, 126/29, 128/31, and 129/32, and Other Miscellaneous Changes (4 Pages)

Discussion This Enclosure contains six addenda that are driving modifications to the October 12, 2018 License Amendment Request (LAR). Within each addendum, the modification pages are provided in the order that they appear in the LAR.

Addendum 1 License Amendments 122/21 (ML18197A307) were issued on August 30, 2018. These amendments have intersections with the TSTF-425 LAR in TS 3.2.4 as specified below.

- Surveillance Requirements (SRs) 3.2.4.1 and 3.2.4.2 were revised slightly. The revised SRs remain closely aligned with TSTF-425 SR 3.2.4.1 and 3.2.4.2, and the Frequency remains eligible to licensee control in accordance with the Surveillance Frequency Control Program (SFCP), consistent with the TSTF-425 Model Safety Evaluation (SE). These changes remain as administrative variations as described in Attachment 1, Section 2.2.1.1 of the TSTF-425 License Amendment Request (LAR).

Changes to Attachments 3.1, 3.2, 4.1, and 4.2 of the TSTF-425 LAR are provided that are reflective of these changes.

Addendum 2 License Amendments 126/29 (ML19098A774) were issued on June 7, 2019, which revised TS Pages 3.8-42/3.8-38 that had also been designated for change in the TSTF-425 LAR.

License Amendments 129/32 (ML19238A005) were issued on November 26, 2019, which also affected these pages. Additionally, Amendments 129/32 have intersections with the TSTF-425 LAR in SR 3.8.7.1 and SR 3.8.8.1. As a result:

- Surveillance Requirements (SRs) 3.8.7.1 and 3.8.8.1 were revised. The new wording closely aligns with TSTF-425 SR 3.8.7.1 and 3.8.8.1, and the Frequencies remains eligible for licensee control in accordance with the Surveillance Frequency Control Program (SFCP),

consistent with the TSTF-425 Model Safety Evaluation (SE). These changes remain as administrative variations as described in Attachment 1, Section 2.2.1.1 of the TSTF-425 LAR.

- TS 3.8.9 Conditions E and F were re-designated as Conditions G and H, and relocated from Page 3.8-42 to 3.8-42a for WBN1, which is also the page containing the change to SR 3.8.9.1 for control under the SFCP. The WBN2 change was similarly shifted from Page 3.8-38 to 3.8-38a.

Changes to Attachments 3.1, 3.2, 4.1, and 4.2 of the TSTF-425 LAR are provided that are reflective of these changes. Changes to Attachment 7, Page 35 of 37, for the SR 3.8.7.1 and SR 3.8.8.1 entries are shown in Enclosure 3, which has other changes on that same page.

CNL-19-084 E1-1 of 2

Enclosure 1 Addendum 3 License Amendments 128/31 (ML18277A110) were issued on August 27, 2019. These amendments have intersections with several TS pages upon which the TSTF-425 LAR markup and clean pages were based. Corrections are also made to the alignment of WBN1 Page 3.3-50 for Required Action C.1 and its Completion Time, and the lower border line, as well as insertion of additional line spaces before the start of the Surveillance Requirements. These are administrative changes consistent with TSTF-GG-05-01, Revision 1, Writers Guide for Plant Specific Improved Technical Specifications and NUREG-1431. Revised pages are provided for Attachments 3.1, 3.2, 4.1, and 4.2.

Addendum 4 License Amendment 68 (ML081620043) inserted the Notes for SR 3.3.6.2 and SR 3.3.6.3 on WBN1 Page 3.3-55. These Notes were reformatted in License Amendment 92 (ML13141A564) and was re-established as Page 3.3.54. In neither amendment were these Notes properly formatted in conformance with TSTF-GG-05-01. Page 3.3-54 is therefore revised to properly format these Notes consistent with TSTF-GG-05-01 and WBN2 Page 3.3-56, and contains no technical change in content.

Addendum 5 License Amendment 5 (ML020790130) revised the Frequency of WBN1 SR 3.6.2.1 on Page 3.6-7 to be In accordance with the Containment Leakage Rate Testing Program.

However, the placement of this Frequency was misaligned per the guidance of TSTF-GG-05-01.

Page 3.6-7 is revised to properly align this Frequency consistent with WBN2 Page 3.6-6, and contains no technical change in content.

Addendum 6 With the issuance of the WBN2 Operating License, the Frequencies for SR 3.6.11.5 and SR 3.6.11.7 on Page 3.6-27 were misaligned per the guidance of the TSTF-GG-05-01.

Page 3.6-27 is revised to properly align these Frequencies consistent with WBN1 Page 3.6-30, and contain no technical changes in content.

Note: General page instructions are provided in green font. Specific changes on each page are provided in red font.

CNL-19-084 E1-2 of 2

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Replace this page in QPTR Attachment 4.1 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 -------------------------------NOTES---------------------------

 With input from one power range neutron flux channel inoperable and THERMAL POWER

75% RTP, the remaining three power range channels can be used for calculating QPTR.

 SR 3.2.4.2 may be performed in lieu of this Surveillance if adequate power range neutron flux channel inputs are not OPERABLE.

Verify QPTR is within limit by calculation. In accordance with the Surveillance Frequency Control Program AND Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter with the QPTR alarm inoperable SR 3.2.4.2 -------------------------------NOTE-------------------------------

Only required to be performed if input WR4375from one or more power range neutron flux channels are inoperable with THERMAL POWER  75% RTP.

Verify QPTR is within limit using either the movable Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> incore detectors or the PDMS.

AND In accordance with the Surveillance Frequency Control Program Watts Bar-Unit 1 3.2-12 Amendment 82, ___

Replace this page in Attachment 4.2 QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 -------------------------------NOTES----------------------------

D With input from one power range neutron flux channel inoperable and THERMAL POWER

75% RTP, the remaining three power range channels can be used for calculating QPTR.

E SR 3.2.4.2 may be performed in lieu of this Surveillance if adequate power range neutron flux channel inputs are not OPERABLE.

Verify QPTR is within limit by calculation. In accordance with the Surveillance Frequency Control Program AND Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter with the QPTR alarm inoperable SR 3.2.4.2 -------------------------------NOTE------------------------------

Only required to be performed if input WR4375from one or more power range neutron flux channels are inoperable with THERMAL POWER  75% RTP.

Verify QPTR is within limit using the PDMS. Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND In accordance with the Surveillance Frequency Control Program Watts Bar - Unit 2 3.2-11 Amendment ___

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Replace this page in Inverters-Shutdown Attachment 4.1 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and In accordance with alignments to required AC vital bus. the Surveillance Frequency Control Program Watts Bar-Unit 1 3.8-40 Amendment 129, ___

Delete this page from Attachment 4.1 Distribution Systems-Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. Two trains with one or E.1 Enter LCO 3.0.3. Immediately more inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, vital DC, and AC vital bus electrical the Surveillance power distribution subsystems. Frequency Control Program Watts Bar-Unit 1 3.8-42 Amendment ___

Add this page to Distribution Systems-Operating Attachment 4.1 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND G.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H. Two trains with one or H.1 Enter LCO 3.0.3. Immediately more inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, vital DC, and AC vital bus electrical the Surveillance power distribution subsystems. Frequency Control Program Watts Bar-Unit 1 3.8-42a Amendment 129, ___

Replace this page in Attachment 4.2 Inverters - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and In accordance with alignment to required AC vital bus. the Surveillance Frequency Control Program Watts Bar - Unit 2 3.8-34 Amendment 32, ___

Replace this page in Inverters - Shutdown Attachment 4.2 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and In accordance with alignments to required AC vital bus. the Surveillance Frequency Control Program Watts Bar - Unit 2 3.8-36 Amendment 32, ___

Delete this page from Attachment 4.2 Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. Two trains with one or more E.1 Enter LCO 3.0.3. Immediately inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, vital DC, and AC vital bus electrical the Surveillance power distribution subsystems. Frequency Control Program Watts Bar - Unit 2 3.8-38 Amendment ___

Add this page to Distribution Systems - Operating Attachment 4.2 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND G.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H. Two trains with one or more H.1 Enter LCO 3.0.3. Immediately inoperable distribution subsystems that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, vital DC, and AC vital bus electrical the Surveillance power distribution subsystems. Frequency Control Program Watts Bar - Unit 2 3.8-38a Amendment 32, ___

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Delete this page from Attachment 4.2 LOP DG Start Instrumentation 3.3.5 ACTIONS continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Time not met. Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS


NOTE-------------------------------------------------------------

Refer to Table 3.3.5-1 to determine which SRs apply for each LOP Function.

SURVEILLANCE FREQUENCY SR 3.3.5.1 -------------------------------NOTE------------------------------

Verification of relay setpoints not required.

Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Watts Bar - Unit 2 3.3-52 Amendment ___

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Enclosure 2 Change Instructions to the October 12, 2018, License Amendment Request Associated with License Amendments 125/27 (23 Pages)

Discussion License Amendments 125/27 (ML18347B330) were issued on May 22, 2019. These amendments have an intersection with the TSTF-425 License Amendment Request (LAR) in TS 3.7.18 and TS 3.9.9, as well as in TS Section 5.7.2.21. Specifically:

- Surveillance Requirement (SR) 3.7.18.1 is a new surveillance. The SR closely aligns with TSTF-425 SR 3.7.16.1, and the Frequency is eligible for licensee control in accordance with the Surveillance Frequency Control Program (SFCP), consistent with the TSTF-425 Model Safety Evaluation (SE). Its addition qualifies as an administrative variation as described in Attachment 1, Section 2.2.1.1 of the TSTF-425 LAR. Page 3.7-40 is added to Attachments 3.1 and 4.1, and Page 3.7-38 is added to Attachments 3.2 and 4.2. Bases Page B 3.7-93 is added to Attachment 5. Page 26 of 37 of Attachment 7 is revised.

- SR 3.9.9.1 was revised to change the fuel storage pool boron concentration from 2000 ppm to 2300 ppm and additionally removed a Frequency requirement Prior to movement of fuel in the spent fuel pool. Although there is no analogous TSTF-425 SR, it remains eligible for licensee control in accordance with the SFCP, consistent with the TSTF-425 Model SE. The revised SR remains an administrative variation as described in Attachment 1, Section 2.2.1.5 of the TSTF-425 LAR. Page 3.9-16 is replaced in Attachment 3.1 and 4.1, and Page 3.9-12 is replaced in Attachment 3.2 and 4.2. Page 37 of 37 of Attachment 7 is revised.

- The Spent Fuel Storage Rack Monitoring Program is now described in TS Section 5.7.2.21, which was also the proposed location for the description of the SFCP. TS Section 5.7.2.22 has been assigned to the Battery Monitoring and Maintenance Program, as described in Enclosure 3. Accordingly, the SFCP location has been re-assigned to TS Section 5.7.2.23.

Specifically, Insert 2 from Attachments 3.1 and 3.2 are replaced. Pages 5.0-25a is deleted and Page 5.0-25b is added to Attachment 3.1. Page 5.0-27 is deleted and Page 5.0-27b is added to Attachment 3.2. Page 5.0-25a is deleted and Page 5.0-25c is added to Attachment 4.1. Pages 5.0-27 and 5.0-27a are deleted and Page 5.0-27a is added in Attachment 4.2. Page 37 of 37 from Attachment 7 is replaced.

The above changes to Attachments 3.1, 3.2, 4.1, 4.2, 5, and 7 of the TSTF-425 LAR are provided in the following pages as they are ordered in the LAR. Note: General page instructions are provided in green font. Specific changes on each page are provided in red font.

CNL-19-084 E2-1 of 1

Replace this page in Attachment 3.1 INSERT 1 In accordance with the Surveillance Frequency Control Program 23 INSERT 2 5.7.2.21 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

CNL-18-067

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Replace this page in Attachment 3.2 INSERT 1 In accordance with the Surveillance Frequency Control Program INSERT 2 23 5.7.2.21 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

CNL-18-067

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Add this page to Attachment 4.1 Fuel Storage Pool Boron Concentration 3.7.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify the fuel storage pool boron concentration is In accordance within limit. with the Surveillance Frequency Control Program Watts Bar-Unit 1 3.7-40 Amendment 125, ___

Replace this page Spent Fuel Pool Boron Concentration in Attachment 4.1 3.9.9 3.9 REFUELING OPERATIONS 3.9.9 Spent Fuel Pool Boron Concentration LCO 3.9.9 Boron concentration of the spent fuel pool shall be t 2300 ppm.

APPLICABILITY: Whenever any fuel assembly is stored in the flooded spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Initiate action to restore fuel Immediately not within limit. storage pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.9.1 Verify boron concentration in the spent fuel pool is In accordance with t 2300 ppm. the Surveillance Frequency Control Program Watts Bar-Unit 1 3.9-16 Amendment 125, ___

Delete this page in Attachment 4.1 Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.20 Control Room Envelope Habitability Program (continued)

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate defined in the Ventilation Filter Testing Program (VFTP), at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

5.7.2.21 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

Watts Bar-Unit 1 5.0-25a Amendment 70, 78, ___

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Delete this page in Attachment 4.2 Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.20 Control Room Envelope Habitability Program (continued)

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate defined in the Ventilation Filter Testing Program (VFTP), at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
e. The quantitative limits on unfiltered air inleakage into the CRE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.

Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

5.7.2.21 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

(continued)

Watts Bar - Unit 2 5.0-27 Amendment ___

Delete this page in Procedures, Programs, and Manuals Attachment 4.2 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.21 Surveillance Frequency Control Program (continued)

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies,"

Revision 1.Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate defined in the Ventilation Filter Testing Program (VFTP), at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Watts Bar - Unit 2 5.0-27a Amendment ___

Add this page to Attachment 4.2 Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.22 Battery Monitoring and Maintenance Program (continued)

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;
4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and
5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

5.7.2.23 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

Watts Bar-Unit 2 5.0-27b Amendment 33, ___

Add this page to Fuel Storage Pool Boron Concentration Attachment 5 B 3.7.18 BASES (continued)

SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies that the concentration of boron in the fuel storage pool is within the required limit. As long as this SR is met, the analyzed accidents are fully addressed. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Frequency is appropriate because no major replenishment of pool water is expected to take place over such a short period of time.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A)

2. FSAR, Section 4.3.2.7 Watts Bar-Unit 1 B 3.7-93 Revision XX Amendment 125

Replace this page in Attachment 7 3.7.18 Fuel Storage Pool Boron Concentration TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

3.7.15 Fuel Storage Pool Water Level 3.7.13 Fuel Storage Pool Water Level 3.7.15.1 9HULI\WKHIXHOVWRUDJHSRROZDWHUOHYHOLV 3.7.13.1 Verify the fuel storage pool water level is Administrative Variation -

ft above the top of the irradiated fuel t 23 ft above the top of the irradiated fuel Section 2.2.1.1 1 assemblies seated in the storage racks. assemblies seated in the storage racks.

3.7.16 Fuel Storage Pool Boron Concentration N/A N/A 3.7.16.1 Verify the fuel storage pool boron N/A N/A Administrative Variation -

concentration is within limit. Section 2.2.1.2 3.7.18 Secondary Specific Activity 3.7.14 Secondary Specific Activity 3.7.18.1 Verify the specific activity of the secondary 3.7.14.1 Verify the specific activity of the secondary Administrative Variation -

FRRODQWLV>@&LJP'26( coolant is d 0.10 PCi/gm DOSE Section 2.2.1.1 EQUIVALENT I-131. EQUIVALENT I-131.

N/A N/A 3.7.16 Component Cooling System (CCS) -

Shutdown N/A N/A 3.7.16.1 Verify correct breaker alignment and Administrative Variation -

indicated power available to the required Section 2.2.1.5 3.7.18.1 pump(s) that is not in operation.

N/A N/A 3.7.16.2 Verify two CCS pumps are aligned to CCS Administrative Variation -

Train B. Section 2.2.1.5 N/A N/A Verify the fuel 3.7.17 Essential Raw Cooling Water (ERCW) storage pool System - Shutdown N/A N/A concentration is 3.7.17.1 Verify correct breaker alignment and Administrative Variation -

within limit. indicated power available to the required Section 2.2.1.5 pump(s) that is not in operation.

3.8.1 AC Sources - Operating 3.8.1 AC Sources - Operating 3.8.1.1 Verify correct breaker alignment and indicated 3.8.1.1 Verify correct breaker alignment and No variation power availability for each [required] offsite indicated power availability for each required circuit. offsite circuit.

3.8.1.2 Verify each DG starts from standby conditions 3.8.1.2 Verify each DG starts from standby Administrative Variation -

DQGDFKLHYHVVWHDG\VWDWHYROWDJH>@9 conditions and achieves steady state voltage Section 2.2.1.1 DQG>@9DQGIUHTXHQF\>@+]DQG t 6800 V and d 7260 V, and frequency of

>@+] [Frequency - 31 days] 60 Hz nominal. [Frequency - As specified in The SFCP is not adopted Table 3.8.1-1] for this SR CNL-18-067 Page 26 of 37

Replace this page in Attachment 7 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

3.9.7 Refueling Cavity Water Level 3.9.7 Refueling Cavity Water Level 3.9.7.1 9HULI\UHIXHOLQJFDYLW\ZDWHUOHYHOLVIW 3.9.7.1 Verify refueling cavity water level is t 23 ft No variation above the top of reactor vessel flange. above the top of reactor vessel flange.

N/A N/A 3.9.9 Spent Fuel Pool Boron Concentration N/A N/A 3.9.9.1 Verify boron concentration in the spent fuel Administrative Variation -

pool is t 2000 ppm. Section 2.2.1.5 5.5. Programs and Manuals 5.7 Procedures, Programs, and Manuals 5.5.18 Surveillance Frequency Control Program 5.7.2.21 Surveillance Frequency Control Program Administrative Variation -

Section 2.2.1.1 2300 5.7.2.23 CNL-18-067 Page 37 of 37

Enclosure 3 Change Instructions to the October 12, 2018, License Amendment Request Associated with License Amendments 130/33 (4 Pages)

Discussion License Amendments 130/33 (ML19276E557) were issued on December 9, 2019. These amendments have intersections with the TSTF-425 LAR in TS 3.8.4, and 3.8.6. These amendments require updates be made to the TSTF-425 License Amendment Request.

Specifically, the proposed updates are as follows:

- Surveillance Requirements (SRs) 3.8.4.1 and 3.8.4.2 are revised. The new wording closely aligns with TSTF-425 SR 3.8.4.1, and the Frequency remains eligible for licensee control in accordance with the Surveillance Frequency Control Program (SFCP), consistent with the TSTF-425 Model Safety Evaluation (SE).

- SRs 3.8.4.5, 3.8.4.6, 3.8.4.7, 3.8.4.8, 3.8.4.9, 3.8.4.10, 3.8.4.11, and 3.8.4.12 are deleted.

Therefore, the previously proposed Frequency changes to the SFCP are no longer applicable.

- SR 3.8.4.14 is relocated to SR 3.8.6.7, and SR 3.8.4.13 Note 1 is revised reflect that change (and is re-designated as SR 3.8.4.7 to reflect the prior SR deletions, as noted below). The previously proposed SR 3.8.4.14 Frequency change to the SFCP remains applicable.

- New SR 3.8.4.5 is proposed. The SR closely aligns with TSTF-425 SR 3.8.4.2, and the Frequency is eligible for licensee control in accordance with the SFCP, consistent with the TSTF-425 Model SE.

- New SR 3.8.4.6 is proposed. The SR partially aligns with TSTF-425 SR 3.8.4.2, and the Frequency is eligible for licensee control in accordance with the SFCP, consistent with the TSTF-425 Model SE.

- SR 3.8.4.13 is re-designated as SR 3.8.4.7, and revises Note 1. This as-revised SR closely aligns with TSTF-425 SR 3.8.4.3, and the Frequency is eligible for licensee control in accordance with the SFCP, consistent with the TSTF-425 Model SE.

- SRs 3.8.6.1, 3.8.6.2, and 3.8.6.3 are being deleted. Therefore, the previously proposed Frequency changes to the SFCP are no longer applicable.

- New SRs 3.8.6.1, 3.8.6.2, 3.8.6.3, 3.8.6.4, 3.8.6.5, and 3.8.6.6 are proposed. The SRs closely align with TSTF-425 SR 3.8.6.1, 3.8.6.2, 3.8.6.3, 3.8.6.4, 3.8.6.5, and 3.8.6.6, and the Frequencies are eligible for licensee control in accordance with the SFCP, consistent with the TSTF-425 Model SE.

- TS Section 5.7.2.22 now describes the Battery Monitoring and Maintenance Program, which along with Amendments 125/27 have caused relocation of the Surveillance Frequency Control Program description to TS Section 5.7.2.23. This is described in further detail in Enclosure 2.

CNL-19-084 E3-1 of 3

Enclosure 3

- A correction is made to the WBN1 Page 3.8-36 header to state Battery Parameters versus Battery Cell Parameters.

The net results of the above changes on the LAR are as follows:

Attachment 3.1

- Delete Page 3.8-25

- Replace Pages 3.8-26 and 3.8-27

- Delete Pages 3.8-28, 3.8-29, and 3.8-34

- Replace Page 3.8-35

- Add Page 3.8-36

- Changes to Pages 5.0-25a and 5.0-25b are described in Enclosure 2 Attachment 3.2

- Delete Page 3.8-22

- Replace Page 3.8-23 and 3.8-24

- Delete Page 3.8-25

- Replace Page 3.8-31

- Add Page 3.8-32

- Changes to Pages 5.0-27 and 5.0-27b are described in Enclosure 2 Attachment 4.1

- Delete Page 3.8-25

- Replace Pages 3.8-26 and 3.8-27

- Delete Pages 3.8-28, 3.8-29, and 3.8-34

- Replace Page 3.8-35

- Add Page 3.8-36

- Changes to Pages 5.0-25a and 5.0-25c are described in Enclosure 2 Attachment 4.2

- Delete Page 3.8-22

- Replace Pages 3.8-23, 3.8-24, 3.8-31

- Add Page 3.8-32

- Changes to Pages 5.0-27 and 5.0-27b are described in Enclosure 2 Attachment 5

- Delete Page B 3.8-60 and B 3.8-61

- Replace Page B 3.8-62

- Add Pages B 3.8-62a and B 3.8-63

- Replace Page B 3.8-64

- Deleted Pages B 3.8-66, B 3.8-68, B 3.8-76, and B 3.8-77

- Add Pages B 3.8-80, B-3.8-81, and B 3.8-82 Attachment 7

- Replace Pages 32, 33, 34, and 35 (as revised by Amendment 125/27 in Enclosure 2)

CNL-19-084 E3-2 of 3

Enclosure 3 The following pages are ordered as they appear in the LAR. General page instructions are provided in Green font. Specific changes on each page are provided in red font.

CNL-19-084 E3-3 of 3

Delete this page from .1 Insert 1 Amendment ___

Replace this page in Attachment 3.1 Insert 1

Replace this page in Attachment 3.1 Insert 1

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Delete this page from .1 Insert 1 Amendment ___

Replace this page in Attachment 3.1 Insert 1

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DWWV%DU8QLW  Amendment ___

Replace this page in Attachment 3.2 Insert 1

Add this page to .2 Insert 1

Delete this page from Attachment 4.1 DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify vital battery terminal voltage is t 128 V (132 V In accordance with for vital battery V) on float charge. the Surveillance Frequency Control Program SR 3.8.4.2 Verify DG battery terminal voltage is t 124 V on float In accordance with charge. the Surveillance Frequency Control Program SR 3.8.4.3 Verify for the vital batteries that the alternate feeder In accordance with breakers to each required battery charger are open. the Surveillance Frequency Control Program SR 3.8.4.4 Verify correct breaker alignment and indicated power In accordance with availability for each DG 125 V DC distribution panel the Surveillance and associated battery charger. Frequency Control Program (continued)

Watts Bar-Unit 1 3.8-25 Amendment ___

Replace this page in Attachment 4.1 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify vital battery terminal voltage is greater than or In accordance with equal to the minimum established float voltage. the Surveillance Frequency Control Program SR 3.8.4.2 Verify DG battery terminal voltage is greater than or In accordance with equal to the minimum established float voltage. the Surveillance Frequency Control Program SR 3.8.4.3 Verify for the vital batteries that the alternate feeder In accordance with breakers to each required battery charger are open. the Surveillance Frequency Control Program SR 3.8.4.4 Verify correct breaker alignment and indicated power In accordance with availability for each DG 125 V DC distribution panel the Surveillance and associated battery charger. Frequency Control Program SR 3.8.4.5 Verify each vital battery charger supplies 200 amps In accordance with at greater than or equal to the minimum established the Surveillance float voltage for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Frequency Control Program OR Verify each vital battery charger can recharge the battery to the fully charged state within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

(continued)

Watts Bar-Unit 1 3.8-26 Amendment 130, ___

Replace this page in Attachment 4.1 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.6 -------------------------------NOTE-------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify each DG DC battery charger can recharge the In accordance with battery to the fully charged state within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the Surveillance supplying the largest combined demands of the Frequency Control various continuous steady state loads, after a battery Program discharge to the bounding design basis event discharge state.

SR 3.8.4.7 ------------------------------NOTES------------------------------

1. The modified performance discharge test in SR 3.8.6.7 may be performed in lieu of the service test in SR 3.8.4.7.
2. This Surveillance is not performed in MODE 1, 2, 3, or 4 for required vital batteries.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required the Surveillance emergency loads and any connected nonsafety loads Frequency Control for the design duty cycle when subjected to a battery Program service test.

Watts Bar-Unit 1 3.8-27 Amendment 54, 130, ___

Delete this page from DC Sources - Operating Attachment 4.1 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.12 -------------------------------NOTE-------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify each diesel generator battery charger is In accordance with capable of recharging its associated battery from a the Surveillance service or capacity discharge test while supplying Frequency Control normal loads. Program SR 3.8.4.13 ------------------------------NOTES------------------------------

1. The modified performance discharge test in SR 3.8.4.14 may be performed in lieu of the service test in SR 3.8.4.13 once per 60 months.
2. This Surveillance is not performed in MODE 1, 2, 3, or 4 for required vital batteries.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required the Surveillance emergency loads and any connected nonsafety loads Frequency Control for the design duty cycle when subjected to a battery Program service test.

(continued)

Watts Bar-Unit 1 3.8-28 Amendment 12, ___

Delete this page from Attachment 4.1 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.14 ------------------------------NOTES------------------------------

This Surveillance is not performed in MODE 1, 2, 3, or 4 for required vital batteries. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is t 80% of the manufacturer's In accordance with rating when subjected to a performance discharge the Surveillance test or a modified performance discharge test. Frequency Control Program AND 12 months when battery shows degradation or has reached 85% of expected life with capacity < 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity t 100% of manufacturer's rating Watts Bar-Unit 1 3.8-29 Amendment 12, ___

Delete this page from Attachment 4.1 Battery Cell Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated battery Immediately associated Completion inoperable.

Time of Condition A not met.

OR One or more batteries with average electrolyte temperature of the representative cells < 60qF for vital batteries and <

50qF for DG batteries.

OR One or more batteries with one or more battery cell parameters not within Category C values.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet Table 3.8.6-1 In accordance with Category A limits. the Surveillance Frequency Control Program (continued)

Watts Bar-Unit 1 3.8-34 Amendment ___

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Delete this page from Attachment 4.2 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify vital battery terminal voltage is 9 9 In accordance with for vital battery V) on float charge. the Surveillance Frequency Control Program SR 3.8.4.2 Verify DG battery terminal voltage is 9RQIORDW In accordance with charge. the Surveillance Frequency Control Program SR 3.8.4.3 Verify for the vital batteries that the alternate feeder In accordance with breakers to each required battery charger are open. the Surveillance Frequency Control Program SR 3.8.4.4 Verify correct breaker alignment and indicated power In accordance with availability for each DG 125 V DC distribution panel the Surveillance and associated battery charger Frequency Control Program SR 3.8.4.5 Verify no visible corrosion at terminals and In accordance with connectors for the vital batteries. the Surveillance Frequency Control OR Program Verify connection resistance for the vital batteries is

(-6 ohm for inter-cell connections,

(-6 ohm for inter-rack connections,

(-6 ohm for inter-tier connections, and

(-6 ohm for terminal connections.

SR 3.8.4.6 Verify no visible corrosion at terminals and In accordance with connectors for the DG batteries. the Surveillance Frequency Control OR Program Verify connection resistance for the DG batteries is

(-6 ohm for inter-cell connections,

 E-6 ohm for inter-tier connections, and

(-6 ohm for terminal connections.

(continued)

Watts Bar - Unit 2 3.8-22 Amendment ___

Replace this page in Attachment 4.2 '&6RXUFHV2SHUDWLQJ



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Replace this page DC Sources - Operating in Attachment 4.2 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.6 -------------------------------NOTE-------------------------------

Credit may be taken for unplanned events that satisfy this SR.

Verify each DG DC battery charger can recharge the In accordance with battery to the fully charged state within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while the Surveillance supplying the largest combined demands of the Frequency Control various continuous steady state loads, after a battery Program discharge to the bounding design basis event discharge state.

SR 3.8.4.7 ------------------------------NOTES------------------------------

1. The modified performance discharge test in SR 3.8.6.7 may be performed in lieu of the service test in SR 3.8.4.7.
2. This Surveillance is not performed in MODE 1, 2, 3, or 4 for required vital batteries.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required the Surveillance emergency loads and any connected nonsafety loads Frequency Control for the design duty cycle when subjected to a battery Program service test.

Watts Bar - Unit 2 3.8-24 Amendment 33, ___

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Delete this page from DC Sources-Operating Attachment 5 B 3.8.4 BASES (continued)

SURVEILLANCE SR 3.8.4.1 and SR 3.8.4.2 REQUIREMENTS Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the critical design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with manufacturer recommendations and IEEE-450 (Ref. 9). The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.3 Verifying that for the vital batteries that the alternate feeder breakers to each required battery charger is open ensures that independence between the power trains is maintained. The 7-day Frequency is based on engineering judgement, is consistent with procedural controls governing breaker operation, and ensures correct breaker position. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.4 This SR demonstrates that the DG 125V DC distribution panel and associated charger are functioning properly, with all required circuit breakers closed and buses energized from normal power. The 7 day Frequency takes into account the redundant DG capability and other indications available in the control room that will alert the operator to system malfunctions. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.5 and SR 3.8.4.6 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each intercell, interrack, intertier, and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

(continued)

Watts Bar-Unit 1 B 3.8-60

Delete this page from Attachment 5 DC Sources-Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.5 and SR 3.8.4.6 (continued)

REQUIREMENTS The limits established for this SR must be no more than 20% above the resistance as measured during installation, or not above the ceiling value established by the manufacturer.

The Surveillance Frequency for these inspections, which can detect conditions that can cause power losses due to resistance heating, is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.7 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The 12 month Frequency for this SR is consistent with IEEE-450 (Ref. 9), which recommends detailed visual inspection of cell condition and rack integrity on a yearly basis. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.8, SR 3.8.4.9 and SR 3.8.4.10 Visual inspection and resistance measurements of intercell, interrack, intertier, and terminal connections provide an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anticorrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each terminal connection. The removal of visible corrosion is a preventive maintenance SR. The presence of visible corrosion does not necessarily represent a failure of this SR provided visible corrosion is removed during performance of SR 3.8.4.8. For the purposes of trending, inter-cell (vital and DG batteries) and inter-tier (vital and DG batteries) connections are measured from battery post to battery post. Inter-rack (vital batteries), inter-tier (DG Batteries), and terminal connections (vital and DG batteries) are measured from terminal lug to battery post.

(continued)

Watts Bar-Unit 1 B 3.8-61 Revision 56, 69 Amendment 54

Replace this page in Attachment 5 DC Sources-Operating B 3.8.4 BASES (continued)

SURVEILLANCE SR 3.8.4.1 and SR 3.8.4.2 REQUIREMENTS Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the battery chargers, which support the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery and maintain the battery in a fully charged state while supplying the continuous steady state loads of the associated DC subsystem.

On float charge, battery cells will receive adequate current to optimally charge the battery. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the minimum float voltage established by the battery manufacturer (2.20 Vpc times the number of connected cells or 132 V at the battery terminals for a 60 cell vital battery; 127.6 V at the battery terminals for a 58 cell DG battery). This voltage maintains the battery plates in a condition that supports maintaining the grid life. The 7 day Frequency is consistent with manufacturer recommendations.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.3 Verifying that for the vital batteries that the alternate feeder breakers to each required battery charger is open ensures that independence between the power trains is maintained. The 7-day Frequency is based on engineering judgement, is consistent with procedural controls governing breaker operation, and ensures correct breaker position.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.4 This SR demonstrates that the DG 125V DC distribution panel and associated charger are functioning properly, with all required circuit breakers closed and buses energized from normal power. The 7 day Frequency takes into account the redundant DG capability and other indications available in the control room that will alert the operator to system malfunctions.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.5 This SR verifies the design capacity of the vital battery chargers. According to Regulatory Guide 1.32 (Ref. 5), the battery charger supply is recommended to be based on the largest combined demands of the various steady state loads and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the plant during these demand occurrences. The minimum required amperes and duration ensure that these requirements can be satisfied.

(continued)

Watts Bar-Unit 1 B 3.8-62

Add this page to Attachment 5 DC Sources-Operating B 3.8.4 BASES (continued)

SURVEILLANCE SR 3.8.4.5 (continued)

REQUIREMENTS This SR provides two options. One option requires that each battery charger be capable of supplying 200 amps at the minimum established float voltage (132 V DC) for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The ampere requirements are based on the output rating of the chargers. The voltage requirements are based on the charger voltage level after a response to a loss of AC power.

The other option requires that each vital battery charger be capable of recharging the battery after a service test coincident with supplying the largest coincident demands of the various continuous steady state loads (irrespective of the status of the plant during which these demands occur). This level of loading may not normally be available following the battery service test and will need to be supplemented with additional loads. The duration for this test may be longer than the charger sizing criteria since the battery recharge is affected by float voltage, temperature, and the exponential decay in charging current. The battery is UHFKDUJHGZKHQWKHPHDVXUHGFKDUJLQJFXUUHQWLV 2 amps.

The Surveillance Frequency is acceptable, given the plant conditions required to perform the test and the other administrative controls existing to ensure adequate charger performance during these 18 month intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.4.6 This SR verifies the design capacity of the DG battery chargers. According to Regulatory Guide 1.32 (Ref. 5), the battery charger supply is recommended to be based on the largest combined demands of the various steady state loads and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the plant during these demand occurrences. The minimum required amperes and duration ensure that these requirements can be satisfied.

This SR requires that each DG battery charger be capable of recharging the battery after a service test coincident with supplying the largest coincident demands of the various continuous steady state loads (irrespective of the status of the plant during which these demands occur). This level of loading may not normally be available following the battery service test and will need to be supplemented with additional loads. The duration for this test may be longer than the charger sizing criteria since the battery recharge is affected by float voltage, temperature, and the exponential decay in charging current. The battery is recharged when the measured charging current iVDPS

The Surveillance Frequency is acceptable, given the administrative controls existing to ensure adequate charger performance during these 18 month intervals.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

Watts Bar-Unit 1 B 3.8-62a

Add this page to DC Sources-Operating Attachment 5 B 3.8.4 BASES SURVEILLANCE SR 3.8.4.6 (continued)

REQUIREMENTS For the DG DC electrical subsystem, this Surveillance may be performed in MODES 1, 2, 3, or 4 in conjunction with LCO 3.8.1.B since the DG DC electrical power subsystem supplies loads only for the inoperable diesel generator and would not otherwise challenge safety systems supplied from vital electrical distribution systems. If available, the C-S DG and its associated DC electrical power subsystem may be substituted in accordance with LCO Note 2.

Additionally, credit may be taken for unplanned events that satisfy this SR.

Examples of unplanned events may include:

1) Unexpected operational events which cause the equipment to perform the function specified by this Surveillance, for which adequate documentation of the required performance is available; and
2) Post corrective maintenance testing that requires performance of this Surveillance in order to restore the component to OPERABLE, provided the maintenance was required, or performed in conjunction with maintenance required to maintain OPERABILITY or reliability.

SR 3.8.4.7 A battery service test is a special test of battery capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length should correspond to worst case design duty cycle requirements based on References 8 and 10.

The Surveillance Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.32 (Ref. 5) and Regulatory Guide 1.129 (Ref. 9), which state that the battery service test should be performed during refueling operations or at some other outage, with intervals between tests, not to exceed 18 months.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

This SR is modified by two Notes. Note 1 allows the performance of a modified performance discharge test in lieu of a service test.

The reason for Note 2 is that performing the Surveillance may perturb the vital electrical distribution system and challenge safety systems. However, this Surveillance may be performed in MODES l, 2, 3, or 4 provided that Vital Battery V is substituted in accordance with LCO Note l. For the DG DC electrical subsystem, this surveillance may be performed in MODES l, 2, 3, or 4 in conjunction with LCO 3.8.l.B since the supplied loads are only for the inoperable diesel generator and would not otherwise challenge safety system loads which are supplied from vital electrical distribution systems. If available, the C-S DG and its associated DC electrical power subsystem may be substituted in accordance with LCO Note 2. Additionally, credit may be taken for unplanned events that satisfy this SR. Examples of unplanned events may include:

(continued)

Watts Bar-Unit 1 B 3.8-63 Revision 112

Replace this page in Attachment 5 DC Sources-Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.7 (continued)

REQUIREMENTS

1) Unexpected operational events which cause the equipment to perform the function specified by this Surveillance, for which adequate documentation of the required performance is available; and
2) Post corrective maintenance testing that requires performance of this Surveillance in order to restore the component to OPERABLE, provided the maintenance was required, or performed in conjunction with maintenance required to maintain OPERABILITY or reliability.

REFERENCES 1. Title 10, Code of Federal Regulations, Part 50, Appendix A, General Design Criterion 17, Electric Power System.

2. Regulatory Guide 1.6, Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems, U.S.

Nuclear Regulatory Commission, March 10, 1971.

3. IEEE-308-1971, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, Institute of Electrical and Electronic Engineers.
4. Watts Bar FSAR, Section 8.3.2, DC Power System.
5. Regulatory Guide 1.32, Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants, February 1977, U.S. Nuclear Regulatory Commission.
6. Watts Bar FSAR, Section 15, Accident Analysis and Section 6 Engineered Safety Features.
7. Regulatory Guide 1.93, Availability of Electric Power Sources, U.S.

Nuclear Regulatory Commission, December 1974.

8. TVA Calculation WBN EEB-MS-TI11-0003, 125 VDC Vital Battery and Charger Evaluation.
9. Regulatory Guide 1.129, Maintenance Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Subsystems, U.S. Nuclear Regulatory Commission, February 1978.Deleted
10. TVA Calculation WBN EEB-MS-TI11-0062, "125 V DC Diesel Generator Control Power System Evaluation."

Watts Bar-Unit 1 B 3.8-64

Delete this page from DC Sources-Operating Attachment 5 B 3.8.4 BASES SURVEILLANCE SR 3.8.4.13 (continued)

REQUIREMENTS

2) Post corrective maintenance testing that requires performance of this Surveillance in order to restore the component to OPERABLE, provided the maintenance was required, or performed in conjunction with maintenance required to maintain OPERABILITY or reliability.

SR 3.8.4.14 A battery performance discharge test is a test of constant current capacity of a battery, normally done in the as found condition, after having been in service, to detect any change in the capacity determined by the acceptance test. The test is intended to determine overall battery degradation due to age and usage.

A battery modified performance discharge test is described in the Bases for 3.8.4.13. Either the battery performance discharge test or the modified performance discharge test is acceptable for satisfying SR 3.8.4.14; however, only the modified performance discharge test may be used to satisfy SR 3.8.4.14 while satisfying the requirements of SR 3.8.4.13 at the same time.

The acceptance criteria for this Surveillance are consistent with IEEE-450 (Ref. 9) and IEEE-485 (Ref. 5). These references recommend that the battery be replaced if its capacity is below 80% of the manufacturer rating. A capacity of 80% shows that the battery rate of deterioration is increasing, even if there is ample capacity to meet the load requirements.

The Surveillance Frequency for this test is normally 60 months. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. If the battery shows degradation, or if the battery has reached 85% of its expected life and capacity is < 100% of the manufacturer's rating, the Surveillance Frequency is reduced to 12 months. However, if the battery shows no degradation but has reached 85% of its expected life, the Surveillance Frequency is only reduced to 24 months for batteries that retain capacity > 100% of the manufacturer's rating. Degradation is indicated, according to IEEE-450 (Ref. 9),

when the battery capacity drops by more than 10% relative to its capacity on the previous performance test or when it is > 10% below the manufacturer rating.

These Frequencies are consistent with the recommendations in IEEE-450 (Ref. 9).

(continued)

Watts Bar-Unit 1 B 3.8-66 Revision 19 Amendment 12

Delete this page from DC Sources-Operating Attachment 5 B 3.8.4 BASES (continued)

REFERENCES 1. Title 10, Code of Federal Regulations, Part 50, Appendix A, General Design Criterion 17, Electric Power System.

2. Regulatory Guide 1.6, Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems, U.S.

Nuclear Regulatory Commission, March 10, 1971.

3. IEEE-308-1971, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, Institute of Electrical and Electronic Engineers.
4. Watts Bar FSAR, Section 8.3.2, DC Power System.
5. IEEE-485-1983, Recommended Practices for Sizing Large Lead Storage Batteries for Generating Stations and Substations, Institute of Electrical and Electronic Engineers.
6. Regulatory Guide 1.32, Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants, February 1977, U.S. Nuclear Regulatory Commission.
7. Watts Bar FSAR, Section 15, Accident Analysis and Section 6 Engineered Safety Features.
8. Regulatory Guide 1.93, Availability of Electric Power Sources, U.S.

Nuclear Regulatory Commission, December 1974.

9. IEEE-450-1980/1995, IEEE Recommended Practice for Maintenance Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Subsystems, Institute of Electrical and Electronic Engineers.
10. TVA Calculation WBN EEB-MS-TI11-0003, 125 VDC Vital Battery and Charger Evaluation.
11. Regulatory Guide 1.129, Maintenance Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Subsystems, U.S. Nuclear Regulatory Commission, February 1978.Deleted (continued)

Watts Bar-Unit 1 B 3.8-68

Delete this page from Attachment 5 Battery Cell Parameters B 3.8.6 BASES ACTIONS A.1, A.2, and A.3 (continued) parameters are not severely degraded, this time is considered reasonable. The verification is repeated at 7 day intervals until the parameters are restored to Category A and B limits. This periodic verification is consistent with the normal Frequency of pilot cell surveillances.

Continued operation is only permitted for 31 days before battery cell parameters must be restored to within Category A and B limits. With the consideration that, while battery capacity is degraded, sufficient capacity exists to perform the intended function and to allow time to fully restore the battery cell parameters to normal limits, this time is acceptable prior to declaring the battery inoperable.

B.1 With one or more batteries with one or more battery cell parameters outside the Category C limits for any connected cell, sufficient capacity to supply the maximum expected load requirement is not assured and the corresponding vital DC or DG DC electrical power subsystem must be declared inoperable.

Additionally, other potentially extreme conditions, such as not completing the Required Actions of Condition A within the required Completion Time or average electrolyte temperature of representative cells falling below 60qF for the vital batteries or 50qF for DG batteries, are also cause for immediately declaring the associated vital DC or DG DC electrical power subsystem inoperable.

SURVEILLANCE SR 3.8.6.1 REQUIREMENTS This SR verifies that Category A battery cell parameters are consistent with IEEE-450 (Ref. 2), which recommends regular battery inspections (at least one per month) including voltage, specific gravity, and electrolyte temperature of pilot cells. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

Watts Bar-Unit 1 B 3.8-76

Delete this page from Attachment 5 Battery Cell Parameters B 3.8.6 BASES SURVEILLANCE SR 3.8.6.2 REQUIREMENTS (continued) The quarterly inspection of specific gravity and voltage is consistent with IEEE-450 (Ref. 2). In addition, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a battery discharge < 110 V (113.5V for Vital Battery V or 106.5 for DG batteries) or a battery overcharge

> 150 V (155 V for Vital Battery V or 145 V for DG batteries), the battery must be demonstrated to meet Category B limits. Transients, such as motor starting transients, which may momentarily cause battery voltage to drop to d 110 V (113.5 V for Vital Battery V or 106.5 V for DG batteries), do not constitute a battery discharge provided the battery terminal voltage and float current return to pre-transient values. This inspection is also consistent with IEEE-450 (Ref. 2),

which recommends special inspections following a severe discharge or overcharge, to ensure that no significant degradation of the battery occurs as a consequence of such discharge or overcharge. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.6.3 This Surveillance verification that the average temperature of representative cells is t 60qF for the vital batteries and t 50qF for the DG batteries, is consistent with a recommendation of IEEE-450 (Ref. 2), that states that the temperature of electrolytes in representative cells should be determined on a quarterly basis.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Lower than normal temperatures act to inhibit or reduce battery capacity. This SR ensures that the operating temperatures remain within an acceptable operating range. This limit is based on manufacturer recommendations.

Table 3.8.6-1 This table delineates the limits on electrolyte level, float voltage, and specific gravity for three different categories. The meaning of each category is discussed below.

(continued)

Watts Bar-Unit 1 B 3.8-77

Add this page to Battery Parameters Attachment 5 B 3.8.6 BASES SURVEILLANCE SR 3.8.6.1 and SR 3.8.6.2 REQUIREMENTS Verifying battery float current while on float charge is used to determine the state of charge of the battery. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery and maintain the battery in a charged state. The equipment used to monitor float current must have the necessary accuracy and capability to measure electrical currents in the expected range. The float current requirements are based on the float current indicative of a charged battery. The 7 day Frequency is consistent with IEEE-450 (Ref. 2).The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.6.1 is modified by a Note that states the float current requirement is not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1. When this float voltage is not maintained the Required Actions of LCO 3.8.4 ACTION A are being taken, which provide the necessary and appropriate verifications of the battery condition. Furthermore, the float current limit of 2 amps is established based on the nominal float voltage value and is not directly applicable when this voltage is not maintained.

SR 3.8.6.2 is modified by a Note that states the float current requirement is not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.2. When this float voltage is not maintained the Required Actions of LCO 3.8.4 ACTION D are being taken, which provide the necessary and appropriate verifications of the battery condition. Furthermore, the float current limit of 1 amp is established based on the nominal float voltage value and is not directly applicable when this voltage is not maintained.

SR 3.8.6.3 and SR 3.8.6.6 Optimal long term battery performance is obtained by maintaining a float voltage greater than or equal to the minimum established design limits provided by the battery manufacturer, which corresponds to 132 V at the battery terminals, or 2.20 VDC. This provides adequate overpotential, which limits the formation of lead sulfate and self discharge, which could eventually render the battery inoperable.

Float voltages in this range or less, but greater than 2.07 VDC, are addressed in Specification 5.7.2.22. SRs 3.8.6.3 and 3.8.6.6 require verification that the cell float voltages are equal to or greater than the short term absolute minimum voltage of 2.07 V. The Frequency for cell voltage verification every 31 days for pilot cell and 92 days for each connected cell is consistent with IEEE-450 (Ref. 2).The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.6.4 The limit specified for electrolyte level ensures that the plates suffer no physical damage and maintains adequate electron transfer capability. The minimum design electrolyte level is the minimum level indication mark on the battery cell jar. The (continued)

Watts Bar-Unit 1 B 3.8-80

Add this page to Battery Parameters Attachment 5 B 3.8.6 BASES Frequency is consistent with IEEE-450 (Ref. 2).The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

Watts Bar-Unit 1 B 3.8-8

Add this page to Battery Parameters Attachment 5 B 3.8.6 BASES SURVEILLANCE SR 3.8.6.5 REQUIREMENTS This Surveillance verifies that the pilot cell temperature is greater than or equal to the minimum established design limit (i.e., 60°F for the vital batteries and 50°F for the DG batteries). Pilot cell electrolyte temperature is maintained above this temperature to assure the battery can provide the required current and voltage to meet the design requirements. Temperatures lower than assumed in battery sizing calculations act to inhibit or reduce battery capacity. The Frequency is consistent with IEEE-450 (Ref. 2).The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.8.6.7 A battery performance discharge test is a test of constant current capacity of a battery, normally done in the as found condition, after having been in service, to detect any change in the capacity determined by the acceptance test. The test is intended to determine overall battery degradation due to age and usage.

Either the battery performance discharge test or the modified performance discharge test is acceptable for satisfying SR 3.8.6.7; however, only the modified performance discharge test may be used to satisfy the battery service test requirements of SR 3.8.4.7.

A modified discharge test is a test of the battery capacity and its ability to provide a high rate, short duration load (usually the highest rate of the duty cycle). This will often confirm the battery's ability to meet the critical period of the load duty cycle, in addition to determining its percentage of rated capacity. Initial conditions for the modified performance discharge test should be identical to those specified for a service test.

It may consist of just two rates; for instance the one minute rate for the battery or the largest current load of the duty cycle, followed by the test rate employed for the performance test, both of which envelope the duty cycle of the service test. Since the ampere-hours removed by a one minute discharge represents a very small portion of the battery capacity, the test rate can be changed to that for the performance test without compromising the results of the performance discharge test. The battery terminal voltage for the modified performance discharge test must remain above the minimum battery terminal voltage specified in the battery service test for the duration of time equal to that of the service test.

The acceptance criteria for this Surveillance are consistent with IEEE-450 (Ref. 2) and IEEE-485 (Ref. 4). These references recommend that the battery be replaced if its capacity is below 80% of the manufacturer's rating. A capacity of 80% shows that the battery rate of deterioration is increasing, even if there is ample capacity to meet the load requirements. Furthermore, the battery is sized to meet the assumed duty cycle loads when the battery design capacity reaches this 80% limit.

(continued)

Watts Bar-Unit 1 B 3.8-8

Add this page to Battery Parameters Attachment 5 B 3.8.6 BASES SURVEILLANCE SR 3.8.6.7 (continued)

REQUIREMENTS The Surveillance Frequency for this test is normally 60 months. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. If the battery shows degradation, or if the battery has reached 85% of its expected life and capacity is < 100% of the manufacturer's rating, the Surveillance Frequency is reduced to 12 months. However, if the battery shows no degradation but has reached 85% of its expected life, the Surveillance Frequency is only reduced to 24 months for batteries that UHWDLQFDSDFLW\RIWKHPDQXIDFWXUHU VUDWLQJV

Degradation is indicated, according to IEEE-450 (Ref. 2), when the battery capacity drops by more than 10% relative to its capacity on the previous SHUIRUPDQFHWHVWRUZKHQLWLVEHORZWKHPDQXIDFturer's rating. These Frequencies are consistent with the recommendations in IEEE-450 (Ref. 2).

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would perturb the electrical distribution system and challenge safety systems. Credit may be taken for unplanned events that satisfy this SR.

REFERENCES 1. Watts Bar FSAR, Section 15, "Accident Analysis," and Section 6, "Engineered Safety Features."

2. IEEE-450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications."
3. Watts Bar FSAR, Section 8, "Electric Power."
4. IEEE-485-1983, "IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations."

Watts Bar-Unit 1 B 3.8-8

Replace this page of Attachment 7 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3.1 Verify each fuel oil storage tank coQWDLQV 3.8.3.1 Verify each 7 day fuel oil storage tank Administrative Variation -

[33,000] gal of fuel. contains t 56,754 gal of fuel. Section 2.2.1.1 3.8.3.2 9HULI\OXEULFDWLQJRLOLQYHQWRU\LVD>500] gal. 3.8.3.2 Verify lubricating oil inventory is t 287 gal Administrative Variation -

per engine. Section 2.2.1.1 3.8.3.4 Verify each DG air start receiver SUHVVXUHLV 3.8.3.4 Verify each DG air start receiver pressure is No variation

[225] psig. t 190 psig.

3.8.3.5 Check for and remove accumulated water from 3.8.3.5 Check for and remove accumulated water Administrative Variation -

each fuel oil storage tank. from each of the four interconnected tanks Section 2.2.1.1 which constitute the 7 day fuel oil storage tank.

N/A N/A 3.8.3.6 Perform a visual inspection for leaks in the Administrative Variation -

exposed fuel oil system piping while the DG Section 2.2.1.5 is running.

N/A N/A Verify DG battery terminal voltage is 3.8.3.7 For each of the four interconnected tanks Administrative Variation -

which constitute the 7 day fuel oil storage Section 2.2.1.5 greater than or equal to the minimum tank: Verify vital battery terminal voltage is greater established float voltage. a. Drain the fuel oil; than or equal to the minimum established float 3.8.4.2 b. Remove the sediment; and voltage.

c. Clean the tank.

3.8.4 DC Sources - Operating 3.8.4 DC Sources - Operating 3.8.4.1 Verify battery terminal voltage is greater than 3.8.4.1 Verify vital battery terminal voltage is t 128 V Administrative Variation -

or equal to the minimum established float (132 V for vital battery V) on float charge. Section 2.2.1.1 voltage.

3.8.4.2 9HULI\HDFKEDWWHU\FKDUJHUVXSSOLHV>@ N/A N/A Administrative Variation -

amps at greater than or equal to the minimum Section 2.2.1.2 HVWDEOLVKHGIORDWYROWDJHIRU>@KRXUV

OR 3.8.4.5 Verify each vital battery charger supplies 200 Verify each battery charger can recharge the amps at greater than or equal to the minimum 2.2.1.1 battery to the fully charged state within [24] established float voltage for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

hours while supplying the largest combined demands of the various continuous steady OR state loads, after a battery discharge to the bounding design basis event discharge state.

Verify each vital battery charger can recharge the battery to the fully charged state within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> while supplying the largest combined CNL-18-067 Page 32 of 37 demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

Replace this page of Attachment 7 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

N/A N/A 3.8.4.2 Verify DG battery terminal voltage is t 124 V Administrative Variation -

on float charge. Section 2.2.1.5 N/A N/A 3.8.4.3 Verify for the vital batteries that the alternate Administrative Variation -

feeder breakers to each required battery Section 2.2.1.5 charger are open.

N/A N/A 3.8.4.4 Verify correct breaker alignment and Administrative Variation -

indicated power availability for each DG Section 2.2.1.5 125 V DC distribution panel and associated battery charger.

N/A N/A 3.8.4.5 Verify no visible corrosion at terminals and Administrative Variation -

connectors for the vital batteries. Section 2.2.1.5 OR Verify connection resistance for the vital (See 3.8.4.2) batteries is d 80 E-6 ohm for inter-cell connections, d 50 E-6 ohm for inter-rack connections, d 120 E-6 ohm for inter-tier connections, and d 50 E-6 ohm for terminal connections.

N/A N/A 3.8.4.6 Verify no visible corrosion at terminals and Administrative Variation -

connectors for the DG batteries. Section 2.2.1.5 Verify each DG battery charger can recharge the battery to OR the fully charged state within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of the various continuous Verify connection resistance for the DG steady state loads, after a battery discharge to the batteries is 80 E-6 ohm for inter-cell bounding design basis event discharge state. FRQQHFWLRQV 50 E-6 ohm for inter-tier FRQQHFWLRQVDQG 50 E-6 ohm for terminal connections.

N/A N/A 3.8.4.7 Verify battery cells, cell plates, and racks Administrative Variation -

show no visual indication of physical damage Section 2.2.1.5 or abnormal deterioration.

N/A N/A 3.8.4.8 Remove visible terminal corrosion and verify Administrative Variation -

battery cell to cell and terminal connections Section 2.2.1.5 are coated with anti-corrosion material.

CNL-18-067 Page 33 of 37

Replace this page in Attachment 7 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

N/A N/A 3.8.4.9 Verify connection resistance for the vital Administrative Variation -

batteries is d 80 E-6 ohm for inter-cell Section 2.2.1.5 connections, d 50 E-6 for inter-rack connections, d 120 E-6 ohm for inter-tier connections, and d 50 E-6 ohm for terminal connections.

N/A N/A 3.8.4.10 Verify connection resistance for the DG Administrative Variation -

EDWWHULHVLV 80 E-6 ohm for inter-cell Section 2.2.1.5 FRQQHFWLRQV 50 E-6 ohm for inter-tier connections, and 50 E-6 ohm for terminal connections.

N/A N/A 3.8.4.11 Verify each vital battery charger is capable of Administrative Variation -

recharging its associated battery from a Section 2.2.1.5 service or capacity discharge test while supplying normal loads.

OR Verify each vital battery charger is capable of operating for t 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at current limit 220 -

250 amps.

N/A N/A 3.8.4.12 Verify each diesel generator battery charger Administrative Variation -

3.8.4.7 is capable of recharging its associated Section 2.2.1.5 battery from a service or capacity discharge test while supplying normal loads.

3.8.4.3 Verify battery capacity is adequate to supply, 3.8.4.13 Verify battery capacity is adequate to supply, Administrative Variation -

and maintain in OPERABLE status, the and maintain in OPERABLE status, the Section 2.2.1.1 required emergency loads for the design duty required emergency loads and any cycle when subjected to a battery service test. connected nonsafety loads for the design duty cycle when subjected to a battery service test.

N/A N/A 3.8.4.14 Verify battery capacity is t 80% of the Administrative Variation -

manufacturer's rating when subjected to a Section 2.2.1.5 performance discharge test or a modified performance discharge test.

CNL-18-067 Page 34 of 37

Verify each vital battery float Replace this page in current is 2 amps.

Verify each required vital battery Attachment 7 and each DG battery pilot cell Verify each DG battery float float voltage is 2.07 V. current is 1 amp.

TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No. 2.2.1.1 3.8.6 Battery Parameters 3.8.6 Battery Parameters 3.8.6.1 9HULI\HDFKEDWWHU\IORDWFXUUHQWLV>@DPSV N/A N/A Administrative Variation -

Section 2.2.1.2 N/A N/A 3.8.6.1 3.8.6.1 Verify battery cell parameters meet Administrative Variation -

3.8.6.2 Table 3.8.6-1 Category A limits. Section 2.2.1.5 3.8.6.2 Verify each battery pilot cell float voltage is N/A N/A Administrative Variation -

[2.07] V. Section 2.2.1.2 N/A N/A 3.8.6.3 3.8.6.2 Verify battery cell parameters meet Administrative Variation -

Table 3.8.6-1 Category B limits. Section 2.2.1.5 3.8.6.3 Verify each battery connected cell electrolyte N/A N/A Administrative Variation -

level is greater than or equal to minimum Section 2.2.1.2 established design limits. 3.8.6.4 3.8.6.4 Verify each battery pilot cell temperature is 3.8.6.3 Verify average electrolyte temperature of Administrative Variation -

greater than or equal to minimum established representative cells is t 60qF for vital Section 2.2.1.1 design limits. 3.8.6.5 batteries and t 50qF for the DG batteries.

3.8.6.5 Verify each battery connected cell float voltage N/A N/A Verify each required vital battery Administrative Variation -

LV>@9 and each DG battery connected Section 2.2.1.2 3.8.6.6 9HULI\EDWWHU\FDSDFLW\LV>@RIWKH 3.8.6.6 N/A N/A cell float voltage is 2.07 V. Administrative Variation -

manufacturer's rating when subjected to a Section 2.2.1.2 performance discharge test or a modified Verify battery capacity is 80% of the manufacturer's performance discharge test. 3.8.6.7 rating when subjected to a performance discharge test or 3.8.7 Inverters - Operating 3.8.7 Inverters Operating a -modified performance discharge test.

3.8.7.1 Verify correct inverter voltage, [frequency], and 3.8.7.1 Verify correct inverter voltage, frequency, Administrative Variation -

alignment to required AC vital buses. and alignment to required AC vital bus and Section 2.2.1.1 from associated vital battery board and 480 V shutdown board.

3.8.8 Inverters - Shutdown 3.8.8 Inverters - Shutdown 3.8.8.1 Verify correct inverter voltage, [frequency,] and 3.8.8.1 Verify correct inverter voltage, frequency, Administrative Variation -

alignments to required AC vital buses. and alignments to required AC vital bus and Section 2.2.1.1 from associated vital battery board and 480 V shutdown board.

3.8.9 Distribution System - Operating 3.8.9 Distribution Systems - Operating 3.8.9.1 Verify correct breaker alignments and voltage 3.8.9.1 Verify correct breaker alignments and Administrative Variation -

to [required] AC, DC, and AC vital bus voltage to required AC, vital DC, and AC vital Section 2.2.1.1 electrical power distribution subsystems. bus electrical power distribution subsystems.

Verify each required vital battery and each DG Verify each required vital battery and each DG battery battery pilot cell temperature is greater than or connected cell electrolyte level is greater than or equal to CNL-18-067 equal to minimum established design limits. Page 35 of 37 minimum established design limits.

Enclosure 4 Clean Version of Attachment 7 to the October 12, 2018, License Amendment Request Showing Revisions Made to Date CNL-19-084 E4-1 of 36

Enclosure 4 TSTF-425 vs. WBN Cross-Reference TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

1.1 Staggered Test Basis put in brackets 1.1 Retained Staggered Test Basis No variation 3.1.1 Shutdown Margin (SDM) N/A N/A 3.1.1.1 Verify SDM to be within the limits specified in N/A N/A Administrative Variation -

the COLR. Section 2.2.1.2 N/A N/A 3.1.1 Shutdown Margin (SDM) -Tavg > 200°F N/A N/A 3.1.1.1 Verify SDM is 1.6% ¨k/k. Administrative Variation -

Section 2.2.1.5 N/A N/A 3.1.2 Shutdown Margin (SDM) -Tavg 200°F N/A N/A 3.1.2.1 Verify SDM is 1.0% ¨k/k. Administrative Variation -

Section 2.2.1.5 3.1.2 Core Reactivity 3.1.3 Core Reactivity 3.1.2.1 Verify measured core reactivity is within +/- 1% 3.1.3.1 Verify measured core reactivity is within +/- Administrative Variation -

k/k of predicted values. 1% k/k of predicted values. Section 2.2.1.1 3.1.4 Rod Group Alignment Limits 3.1.5 Rod Group Alignment Limits 3.1.4.1 Verify individual rod positions within alignment 3.1.5.1 Verify position of individual rods within Administrative Variation -

limit. alignment limit. Section 2.2.1.1 3.1.4.2 Verify rod freedom of movement (trippability) 3.1.5.2 Verify rod freedom of movement (trippability) Administrative Variation -

by moving each rod not fully inserted in the by moving each rod not fully inserted in the Section 2.2.1.1 core 10 steps in either direction. core 10 steps in either direction.

3.1.5 Shutdown Bank Insertion Limits 3.1.6 Shutdown Bank Insertion Limits 3.1.5.1 Verify each shutdown bank is within the 3.1.6.1 Verify each shutdown bank is within the Administrative Variation -

insertion limits specified in the COLR. insertion limits specified in the COLR. Section 2.2.1.1 3.1.6 Control Bank Insertion Limits 3.1.7 Control Bank Insertion Limits 3.1.6.2 Verify each control bank insertion is within the 3.1.7.2 Verify each control bank insertion is within Administrative Variation -

insertion limits specified in the COLR. the limits specified in the COLR. Section 2.2.1.1 3.1.6.3 Verify sequence and overlap limits specified in 3.1.7.3 Verify sequence and overlap limits specified Administrative Variation -

the COLR are met for control banks not fully in the COLR are met for control banks not Section 2.2.1.1 withdrawn from the core. fully withdrawn from the core.

N/A N/A 3.1.9 Physics Tests Exceptions - Mode 1 N/A N/A 3.1.9.1 Verify THERMAL POWER is 85% RTP. Administrative Variation -

Section 2.2.1.5 N/A N/A 3.1.9.3 Perform SR 3.2.1.1 and SR 3.2.2.1. Administrative Variation -

Section 2.2.1.5 CNL-19-084 E4-2 of 36

Enclosure 4 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

N/A N/A 3.1.9.4 Verify SDM is 1.6% ¨k/k. Administrative Variation -

Section 2.2.1.5 3.1.8 Physics Tests Exceptions - Mode 2 3.1.10 Physics Tests Exceptions - Mode 2 3.1.8.2 Verify the RCS lowest loop average 3.1.10.2 Verify the RCS lowest loop average Administrative Variation -

temperature is [531]°F. temperature is 541°F. Section 2.2.1.1 3.1.8.3 Verify THERMAL POWER is 5% RTP. N/A N/A Administrative Variation -

Section 2.2.1.2 3.1.8.4 Verify SDM is within the limits specified in the 3.1.10.3 Verify SDM is 1.6% ¨k/k. Administrative Variation -

COLR. Section 2.2.1.1 3.2.1C Heat Flux Hot Channel (FQ(Z) (CAOC-W(Z) 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

Methodology) 3.2.1.1 Verify FCQ(Z) is within limit. 3.2.1.1 Verify FCQ(Z) is within limit. No variation 3.2.1.2 Verify FWQ(Z) is within limit. 3.2.1.2 Verify FWQ(Z) is within limit. No variation 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN¨H) (FN¨H)

N N 3.2.2.1 Verify F ¨H is within limits specified in the 3.2.2.1 Verify F 'H is within limits specified in the No variation COLR. COLR.

3.2.3B Axial Flux Difference (AFD) (RAOC 3.2.3 Axial Flux Difference (AFD)

Methodology) 3.2.3.1 Verify AFD within limits for each OPERABLE 3.2.3.1 Verify AFD within limits for each OPERABLE Administrative Variation -

excore channel. excore channel. Section 2.2.1.1 3.2.4 Quadrant Power Tilt Ratio (QPTR) 3.2.4 Quadrant Power Tilt Ratio (QPTR) 3.2.4.1 Verify QPTR is within limit by calculation. 3.2.4.1 Verify QPTR is within limit by calculation. Administrative Variation -

Section 2.2.1.1 3.2.4.2 Verify QPTR is within limit using the movable 3.2.4.2 Unit 1 - Verify QPTR is within limit using Administrative Variation -

incore detectors. [Frequency - 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s] either the movable incore detectors or the Section 2.2.1.1 PDMS. [Frequency - AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter]

Unit 2 - Verify QPTR is within limit using the PDMS. [Frequency - AND every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter]

3.3.1 Reactor Trip System (RTS) Instrumentation 3.3.1 RTS Instrumentation 3.3.1.1 Perform CHANNEL CHECK. [Functions 2a/b, 3.3.1.1 Perform CHANNEL CHECK. [Functions 2a/b, Administrative Variation -

4, 5, 6, 7, 8a/b, 9, 10, 14, 15, 18f] 4, 5, 6, 7, 8a/b, 9, 10, 13] Section 2.2.1.3 CNL-19-084 E4-3 of 36

Enclosure 4 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

3.3.1.2 Compare results of calorimetric heat balance 3.3.1.2 Compare results of calorimetric heat balance Administrative Variation -

calculation to power range channel output. calculation to Nuclear Instrumentation Section 2.2.1.3 Adjust power range channel output if System (NIS) channel output. [Function 2a]

calorimetric heat balance calculations results exceed power range channel output by more than +2% RTP. [Function 2a]

3.3.1.3 Compare results of the incore detector 3.3.1.3 Unit 1 - Compare results of the incore Administrative Variation -

measurements to Nuclear Instrumentation detector or PDMS measurements to Section 2.2.1.3 System (NIS) AFD. Adjust NIS channel if NIS AFD. [Function 6]

absolute difference is 3%. [Function 6]

Unit 2 - Compare results of the PDMS measurements to NIS AFD. [Function 6]

3.3.1.4 Perform TADOT [Trip Actuating Device 3.3.1.4 Perform TADOT. [Functions 17, 18] Administrative Variation -

Operational Test]. [Function 19 and 20] Section 2.2.1.3 3.3.1.5 Perform ACTUATION LOGIC TEST. 3.3.1.5 Perform ACTUATION LOGIC TEST. Administrative Variation -

[Functions 18b, 21] [Function 19] Section 2.2.1.3 3.3.1.6 Calibrate excore channels to agree with incore 3.3.1.6 Unit 1 - Calibrate excore channels to agree Administrative Variation -

detector measurements. [Function 6] with incore detectors or PDMS Section 2.2.1.3 measurements. [Function 6]

Unit 2 - Calibrate excore channels to agree with the PDMS measurements. [Function 6]

3.3.1.7 Perform COT [Channel Operational Test]. 3.3.1.7 Perform COT. [Functions 2a/b, 3a, 6, 7, 8a/b, Administrative Variation -

[Functions 2a, 3a/b, 5, 6, 7, 8a/b, 9, 10, 14, 15] 9, 10, 13] Section 2.2.1.3 3.3.1.8 Perform COT. [Functions 2b, 4, 5] 3.3.1.8 Perform COT. [Functions 4, 5] Administrative Variation -

Section 2.2.1.3 3.3.1.9 Perform TADOT. [Functions 12, 13] 3.3.1.9 Perform TADOT. [Functions 11, 12] Administrative Variation -

Section 2.2.1.3 3.3.1.10 Perform CHANNEL CALIBRATION. 3.3.1.10 Perform CHANNEL CALIBRATION. Administrative Variation -

[Functions 8a/b, 9, 10, 12, 13, 14, 15, 16a/b, [Functions 8a/b, 9, 10, 11, 12, 13, 14a/b, 16f] Section 2.2.1.3 18f))

3.3.1.11 Perform CHANNEL CALIBRATION. 3.3.1.11 Perform CHANNEL CALIBRATION. Administrative Variation -

[Functions 2a/b, 3a/b, 4, 5, 18a/c/d/e] [Functions 2a/b, 3a, 4, 5, 16a/b/c/d/e] Section 2.2.1.3 3.3.1.12 Perform CHANNEL CALIBRATION. 3.3.1.10 Perform CHANNEL CALIBRATION. Administrative Variation -

[Functions 6, 7] [Functions 6, 7] Section 2.2.1.3 3.3.1.13 Perform COT. [Functions 18a/c/d/e/f] 3.3.1.12 Perform COT. [Functions 16a/b/c/d/e/f] Administrative Variation -

Section 2.2.1.3 CNL-19-084 E4-4 of 36

Enclosure 4 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

3.3.1.14 Perform TADOT. [Functions 1, 11a/b, 17] 3.3.1.13 Perform TADOT. [Functions 1, 15] Administrative Variation -

Section 2.2.1.3 3.3.1.16 Verify RTS RESPONSE TIME is within limits. 3.3.1.15 Verify RTS RESPONSE TIME is within limits. Administrative Variation -

[Functions 2a/b, 3b, 5, 6, 7, 8a/b, 10, 12, 13, [Functions 2a/b, 5, 6, 7, 8a/b, 10, 11, 12, 13] Section 2.2.1.3 14, 15]

3.3.2 Engineered Safety Feature Actuation 3.3.2 ESFAS Instrumentation System (ESFAS) Instrumentation 3.3.2.1 Perform CHANNEL CHECK. 3.3.2.1 Perform CHANNEL CHECK. Administrative Variation -

[Functions 1c/d/e(1)(2)/f/g, 2c/d, 3b(3), [Functions 1c/d/e, 2c, 3b(3), 4c/d(1)(2), 5b, Section 2.2.1.3 4c/d(1)(2)/e/f/g/h, 5b, 6c/h, 7b/c, 8b/c] 6b, 7b, 8b(1)(2) 3.3.2.2 Perform ACTUATION LOGIC TEST. 3.3.2.2 Perform ACTUATION LOGIC TEST. No variation

[Functions 1b, 2b, 3a(2)/b(2). 4b, 5a, 6a, 7a] [Functions 1b, 2b, 3a(2)/b(2), 4b, 5a, 6a, 7a]

3.3.2.3 Perform ACTUATION LOGIC TEST. [Function N/A N/A Administrative Variation -

6b] Section 2.2.1.2 3.3.2.4 Perform MASTER RELAY TEST. 3.3.2.3 Perform MASTER RELAY TEST. Administrative Variation -

[Functions 1b, 2b, 3a(2)/b(2), 4b, 5a, 6a, 7a] [Functions 1b, 2b, 3a(2)/b(2), 4b, 5a, 6a, 7a] Section 2.2.1.3 3.3.2.5 Perform COT. [Functions 1c/d/e(1)(2)/f/g, 2c/d, 3.3.2.4 Perform COT. [Functions 1c/d/e, 2c, 3b(3), Administrative Variation -

3b(3), 4c/d(1)(2)/e/f/g/h, 5b, 6c, 7b/c, 8b/c] 4c/d(1)(2), 5b, 6b, 7b, 8b(1)(2)] Section 2.2.1.3 3.3.2.6 Perform SLAVE RELAY TEST. [Functions 1b, 3.3.2.5 Perform SLAVE RELAY TEST. Administrative Variation -

2b, 3a(2)/b(2), 4b, 5a, 6a, 7a] [Functions 1b, 2b, 3a(2)/b(2), 4b, 5a, 6a, 7a] Section 2.2.1.3 3.3.2.7 Perform TADOT. [Functions 6e/f/h] 3.3.2.6 Perform TADOT. [Functions 5d/e, 6f] Administrative Variation -

Section 2.2.1 N/A N/A 3.3.2.7 Perform SLAVE RELAY TEST on slave Administrative Variation -

relays K603A, K603B, K604A, K604B, Section 2.2.1.5 K607A, K607B, K609A, K609B, K612A, K625A, and K625B. [Functions 1b, 3a(2)/b(2)]

3.3.2.8 Perform TADOT. [Functions 1a, 2a, 3a(1)/b(1), 3.3.2.8 Perform TADOT [Functions 1a, 2a, Administrative Variation -

4a, 6g] 3a(1)/b(1), 4a, 6e] Section 2.2.1.3 3.3.2.9 Perform CHANNEL CALIBRATION. 3.3.2.9 Perform CHANNEL CALIBRATION. Administrative Variation -

[Functions 1c/d/e(1)(2)/f/g, 2c/d, 3b(3), [Functions 1c/d/e, 2c, 3b(3), 4c/d(1)(2), Section 2.2.1.3 4c/d(1)(2)/e/f/g/h, 5b, 6c/e/f/g/h, 7b/c, 8b/c] 5b/d/e, 6b/e/f, 7b, 8b(1)(2) 3.3.2.10 Verify ESFAS RESPONSE TIMES are within 3.3.2.10 Verify ESFAS RESPONSE TIMES are within Administrative Variation -

limit. [Functions 1c/d/e(1)(2)/f/g, 2c/d, 3b(3), limit. [Functions 1c/d/e, 2c, 3b(3), 4c/d(1)(2), Section 2.2.1.3 4c/d(1)(2)/e/f/g/h, 5b, 6c/e/f/g, 7b/c] 5b, 6b/e/f, 7b]

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3.3.3 Post Accident Monitoring (PAM) 3.3.3 PAM Instrumentation Instrumentation 3.3.3.1 Perform CHANNEL CHECK for each required 3.3.3.1 Perform CHANNEL CHECK for each No variation instrumentation channel that is normally required instrumentation channel that is energized. normally energized.

3.3.3.2 Perform CHANNEL CALIBRATION. 3.3.3.2 Perform CHANNEL CALIBRATION. Administrative Variation -

Section 2.2.1.1 (SR Notes are different)

N/A N/A 3.3.3.3 Perform TADOT. Administrative Variation -

Section 2.2.1.5 3.3.4 Remote Shutdown System 3.3.4 Remote Shutdown System 3.3.4.1 Perform CHANNEL CHECK for each required 3.3.4.1 Perform CHANNEL CHECK for each No variation instrumentation channel that is normally required instrumentation channel that is energized. normally energized.

3.3.4.2 Verify each required control circuit and transfer 3.3.4.2 Verify each required control circuit and No variation switch is capable of performing the intended transfer switch is capable of performing the function. intended function.

3.3.4.3 Perform CHANNEL CALIBRATION for each 3.3.4.3 Perform CHANNEL CALIBRATION for each No variation required instrumentation channel. required instrumentation channel.

3.3.4.4 Perform TADOT of the reactor trip breaker 3.3.4.4 Perform TADOT of the reactor trip breaker No variation open/closed indication. open/closed indication.

3.3.5 Loss of Power (LOP) Diesel Generator (DG) 3.3.5 LOP DG Start Instrumentation Start Instrumentation 3.3.5.1 Perform CHANNEL CHECK. N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.5.2 Perform TADOT. 3.3.5.1 Perform TADOT. [Functions 1a, 2a, 3, 4] Administrative Variation -

Section 2.2.1.3 N/A N/A 3.3.5.2 Perform CHANNEL CALIBRATION. Administrative Variation -

{Functions 1a, 2a, 3, 4] Section 2.2.1.5 3.3.5.3 Perform CHANNEL CALIBRATION with 3.3.5.3 Perform CHANNEL CALIBRATION. Administrative Variation -

[Nominal Trip Setpoint and Allowable Value] as [Functions 1b, 2b] Section 2.2.1.3 follows: []

3.3.6 Containment Purge and Exhaust Isolation 3.3.6 Containment Vent Isolation Instrumentation Instrumentation 3.3.6.1 Perform CHANNEL CHECK. 3.3.6.1 Perform CHANNEL CHECK. [Function 3] Administrative Variation -

[Functions 3a/b/c/d] Section 2.2.1.3 CNL-19-084 E4-6 of 36

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3.3.6.2 Perform ACTUATION LOGIC TEST. N/A N/A Administrative Variation -

[Function 2] Section 2.2.1.2 3.3.6.3 Perform MASTER RELAY TEST. [Function 2] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.6.4 Perform ACTUATION LOGIC TEST. 3.3.6.2 Perform ACTUATION LOGIC TEST. Administrative Variation -

[Function 2] [Function 2] Section 2.2.1.3 3.3.6.5 Perform MASTER RELAY TEST. [Function 2] 3.3.6.3 Perform MASTER RELAY TEST. [Function Administrative Variation -

2] Section 2.2.1.3 3.3.6.6 Perform COT. [Functions 3a/b/c/d] 3.3.6.4 Perform COT. [Function 3] Administrative Variation -

Section 2.2.1.3 3.3.6.7 Perform SLAVE RELAY TEST. [Function 2] 3.3.6.5 Perform SLAVE RELAY TEST. [Function 2] Administrative Variation -

Section 2.2.1.3 3.3.6.8 Perform TADOT. [Function 1] 3.3.6.6 Perform TADOT. [Function 1] Administrative Variation -

Section 2.2.1.3 3.3.6.9 Perform CHANNEL CALIBRATION. [Functions 3.3.6.7 Perform CHANNEL CALIBRATION. Administrative Variation -

3a/b/c/d] [Function 3] Section 2.2.1.3 3.3.7 Control Room Emergency Filtration System 3.3.7 Control Room Emergency Ventilation (CREFS) Actuation Instrumentation System (CREVS) Actuation Instrumentation 3.3.7.1 Perform CHANNEL CHECK. [Functions 3a/b] 3.3.7.1 Perform CHANNEL CHECK. [Function 2] Administrative Variation -

Section 2.2.1.3 3.3.7.2 Perform COT. [Functions 3a/b] 3.3.7.2 Perform COT. [Function 2] Administrative Variation -

Section 2.2.1.3 3.3.7.3 Perform ACTUATION LOGIC TEST. N/A N/A Administrative Variation -

[Function 2] Section 2.2.1.2 3.3.7.4 Perform MASTER RELAY TEST. [Function 2] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.7.5 Perform ACTUATION LOGIC TEST. N/A N/A Administrative Variation -

[Function 2] Section 2.2.1.2 3.3.7.6 Perform MASTER RELAY TEST. [Function 2] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.7.7 Perform SLAVE RELAY TEST. [Function 2] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.7.8 Perform TADOT. [Function 1] 3.3.7.3 Perform TADOT. [Function 1] Administrative Variation -

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3.3.7.9 Perform CHANNEL CALIBRATION. 3.3.7.4 Perform CHANNEL CALIBRATION. Administrative Variation -

[Functions 3a/b] [Function 2] Section 2.2.1.3 3.3.8 Fuel Building Air Cleanup System (FBACS) N/A N/A Actuation Instrumentation 3.3.8.1. Perform CHANNEL CHECK. [Functions 3a/b] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.8.2 Perform COT. [Functions 3a/b] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.8.3 Perform ACTUATION LOGIC TEST. N/A N/A Administrative Variation -

[Function 2] Section 2.2.1.2 3.3.8.4 Perform TADOT. [Function 1] N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.8.5 Perform CHANNEL CALIBRATION. N/A N/A Administrative Variation -

[Functions 3a/b] Section 2.2.1.2 N/A N/A 3.3.8 Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation N/A N/A 3.3.8.1 Perform TADOT. [Function 1] Administrative Variation -

Section 2.2.1.5 3.3.9 Boron Dilution Protection System (BDPS) 3.3.9 N/A 3.3.9.1 Perform CHANNEL CHECK. N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.9.2 Perform COT. N/A N/A Administrative Variation -

Section 2.2.1.2 3.3.9.3 Perform CHANNEL CALIBRATION. N/A N/A Administrative Variation -

Section 2.2.1.2 3.4.1 RCS Pressure, Temperature, and Flow 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Departure from Nucleate Boiling (DNB)

Limits Limits 3.4.1.1 Verify pressurizer pressure is greater than or 3.4.1.1 Verify pressurizer pressure is t 2214 psig. Administrative Variation -

equal to the limit specified in the COLR. Section 2.2.1.1 3.4.1.2 Verify RCS average temperature is less than or 3.4.1.2 Verify RCS average temperature is Administrative Variation -

equal to the limit specified in the COLR. d 593.2°F. Section 2.2.1.1 3.4.1.3 Verify RCS total flow rate is [284,000] gpm 3.4.1.3 Verify RCS total flow rate is t 380,000 gpm Administrative Variation -

and greater than or equal to the limit specified (process computer or control board Section 2.2.1.1 in the COLR. indication).

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3.4.1.4 Verify by precision heat balance that RCS total 3.4.1.4 Unit 1 - Verify by precision heat balance or Administrative Variation -

flow rate is [284,000] gpm and greater than elbow tap 'p method that RCS total flow rate Section 2.2.1.1 or equal to the limit specified in the COLR. is t 380,000 gpm.

Unit 2 - Verify by precision heat balance method that RCS total flow rate is t 380,000 gpm.

3.4.2 RCS Minimum Temperature for Criticality 3.4.2 RCS Minimum Temperature for Criticality 3.4.2.1 Verify RCS Tavg in each loop [541]°F. 3.4.2.1 Verify RCS Tavg in each loop t 551qF. No variation 3.4.3 RCS Pressure and Temperature (P/T) Limits 3.4.3 RCS Pressure and Temperature (P/T)

Limits 3.4.3.1 Verify RCS pressure, RCS temperature, and 3.4.3.1 Verify RCS pressure, RCS temperature, and No variation RCS heatup and cooldown rates are within the RCS heatup and cooldown rates are within limits specified in the PTLR. the limits specified in the PTLR.

3.4.4 RCS Loops - MODES 1 and 2 3.4.4 RCS Loops - MODES 1 and 2 3.4.4.1 Verify each RCS loop is in operation. 3.4.4.1 Verify each RCS loop is in operation. No variation 3.4.5 RCS Loops - MODE 3 3.4.5 RCS Loops - MODE 3 3.4.5.1 Verify required RCS loops are in operation. 3.4.5.1 Verify required RCS loops are in operation. No variation 3.4.5.2 Verify steam generator secondary side water 3.4.5.2 Unit 1 - Verify steam generator secondary Administrative Variation -

levels are [17]% for required RCS loops. side water levels are greater than or equal to Section 2.2.1.1 32% narrow range for required RCS loops.

Unit 2 - Verify steam generator secondary side water levels are 6% narrow range for required RCS loops.

3.4.5.3 Verify correct breaker alignment and indicated 3.4.5.3 Verify correct breaker alignment and Administrative Variation -

power are available to each required pump. indicated power are available to the required Section 2.2.1.1 pump that is not in operation.

3.4.6 RCS Loops - MODE 4 3.4.6 RCS Loops - MODE 4 N/A N/A 3.4.6.1 Verify two RCS loops are in operation when Administrative Variation -

the rod control system is capable of rod Section 2.2.1.5 withdrawal.

3.4.6.1 Verify required RHR or RCS loop is in 3.4.6.2 Verify one required RHR or RCS loop is in Administrative Variation -

operation. operation when the rod control system is not Section 2.2.1.1 capable of rod withdrawal.

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3.4.6.2 Verify SG secondary side water levels are 3.4.6.3 Unit 1 - Verify SG secondary side water Administrative Variation -

[17]% for required RCS loops. levels are greater than or equal to 32% Section 2.2.1.1 narrow range for required RCS loops.

Unit 2 - Verify SG secondary side water levels are greater than or equal to 6% narrow range for required RCS loops.

3.4.6.3 Verify correct breaker alignment and indicated 3.4.6.4 Verify correct breaker alignment and Administrative Variation -

power are available to each required pump. indicated power are available to the required Section 2.2.1.1 pump that is not in operation.

3.4.7 RCS Loops - MODE 5, Loops Filled 3.4.7 RCS Loops - MODE 5, Loops Filled 3.4.7.1 Verify required RHR loop is in operation. 3.4.7.1 Verify one RHR loop is in operation. Administrative Variation -

Section 2.2.1.1 3.4.7.2 Verify SG secondary side water level is 3.4.7.2 Unit 1 - Verify SG secondary side water level Administrative Variation -

[17]% in required SGs. is greater than or equal to 32% narrow range Section 2.2.1.1 in required SGs.

Unit 2 - Verify SG secondary side water level is greater than or equal to 6% narrow range in required SGs.

3.4.7.3 Verify correct breaker alignment and indicated 3.4.7.3 Verify correct breaker alignment and Administrative Variation -

power are available to each required RHR indicated power are available to the required Section 2.2.1.1 pump. RHR pump that is not in operation.

3.4.8 RCS Loops - MODE 5, Loops Not Filled 3.4.8 RCS Loops - MODE 5, Loops Not Filled 3.4.8.1 Verify required RHR loop is in operation. 3.4.8.1 Verify one RHR loop is in operation. Administrative Variation -

Section 2.2.1.1 3.4.8.2 Verify correct breaker alignment and indicated 3.4.8.2 Verify correct breaker alignment and Administrative Variation -

power are available to each required RHR indicated power are available to the required Section 2.2.1.1 pump. RHR pump that is not in operation.

3.4.9 Pressurizer 3.4.9 Pressurizer 3.4.9.1 Verify pressurizer water level is [92]%. 3.4.9.1 Verify pressurizer water level is d 92%. No variation 3.4.9.2 Verify capacity of each required group of 3.4.9.2 Verify capacity of each required group of No variation pressurizer heaters is [125] kW. pressurizer heaters is t 150 kW.

3.4.9.3 Verify required pressurizer heaters are capable N/A N/A Administrative Variation -

of being powered from an emergency power Section 2.2.1.2 supply.

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3.4.11 Pressurizer Power Operated Relief Valves 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) (PORVs) 3.4.11.1 Perform a complete cycle of each block valve. 3.4.11.1 Perform a complete cycle of each block No variation valve.

3.4.11.2 Perform a complete cycle of each PORV. 3.4.11.2 Perform a complete cycle of each PORV. No variation 3.4.11.3 Perform a complete cycle of each solenoid air N/A N/A Administrative Variation -

control valve and check valve on the air Section 2.2.1.2 accumulators in PORV control systems.

3.4.11.4 Verify PORVs and block valves are capable of N/A N/A Administrative Variation -

being powered from emergency power Section 2.2.1.2 sources.

3.4.12 Low Temperature Overpressure Protection 3.4.12 Cold Overpressure Mitigation System (LTOP) System (COMS) 3.4.12.1 Verify a maximum of [one] [HPI] pump is 3.4.12.1 Verify no safety injection pumps are capable Administrative Variation -

capable of injecting into the RCS. of injecting into the RCS. Section 2.2.1.1 3.4.12.2 Verify a maximum of one charging pump is 3.4.12.2 Verify a maximum of one charging pump is No variation capable of injecting into the RCS. capable of injecting into the RCS.

3.4.12.3 Verify each accumulator is isolated. 3.4.12.3 Verify each accumulator is isolated. No variation 3.4.12.4 Verify RHR suction valve is open for each N/A N/A Administrative Variation -

required RHR suction relief valve. Section 2.2.1.2 3.4.12.5 Verify required RCS vent [2.07] square 3.4.12.4 Verify RCS vent open. Administrative Variation -

inches open. Section 2.2.1.1 3.4.12.6 Verify PORV block valve is open for each 3.4.12.5 Verify PORV block valve is open for each Administrative Variation -

required PORV. required PORV. Section 2.2.1.1 3.4.12.7 Verify associated RHR suction isolation valve 3.4.12.6 Verify both RHR suction isolation valves are Administrative Variation -

is locked open with operator power removed locked open with operator power removed for Section 2.2.1.1 for each required RHR suction relief valve. the required RHR suction relief valve.

3.4.12.8 Perform a COT on each required PORV, 3.4.12.7 Perform a COT on each required PORV, Administrative Variation -

excluding actuation. excluding actuation. Section 2.2.1.1 3.4.12.9 Perform CHANNEL CALIBRATION for each 3.4.12.8 Perform CHANNEL CALIBRATION for each Administrative Variation -

required PORV actuation channel. required PORV actuation channel. Section 2.2.1.1 3.4.13 RCS Operational LEAKAGE 3.4.13 RCS Operational LEAKAGE 3.4.13.1 Verify RCS operational LEAKAGE is within 3.4.13.1 Verify RCS operational LEAKAGE is within No variation limits by performance of RCS water inventory limits by performance of RCS water inventory balance. balance.

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3.4.13.2 Verify primary to secondary LEAKAGE is 150 3.4.13.2 Verify primary-to-secondary LEAKAGE is Administrative Variation -

gallons per day through any one SG. less than or equal to 150 gallons per day Section 2.2.1.1 through any one SG.

3.4.14 RCS Pressure Isolation Valve (PIV) Leakage 3.4.14 RCS Pressure Isolation Valve (PIV)

Leakage 3.4.14.1 Verify leakage from each RCS PIV is 3.4.14.1 Verify leakage from each RCS PIV is No variation equivalent to 0.5 gpm per nominal inch of equivalent to d 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an valve size up to a maximum of 5 gpm at an RCS pressure [2215] psig and [2255] psig. RCS pressure t 2215 psig and d 2255 psig.

3.4.14.2 Verify RHR System autoclosure interlock N/A N/A Administrative Variation -

prevents the valves from being opened with a Section 2.2.1.2 simulated or actual RCS pressure signal

[425] psig.

3.4.14.3 Verify RHR System autoclosure interlock N/A N/A Administrative Variation -

causes the valves to close automatically with a Section 2.2.1.2 simulated or actual RCS pressure signal

[600] psig.

3.4.15 RCS Leakage Detection Instrumentation 3.4.15 RCS Leakage Detection Instrumentation 3.4.15.1 Perform CHANNEL CHECK of the required 3.4.15.1 Perform CHANNEL CHECK of the required Administrative Variation -

containment atmosphere radioactivity monitor. containment atmosphere particulate Section 2.2.1.1 radioactivity monitor.

3.4.15.2 Perform COT of the required containment 3.4.15.2 Unit 1 - Perform COT of the required Administrative Variation -

atmosphere radioactivity monitor. containment atmosphere particulate Section 2.2.1.1 radioactivity level monitor.

Unit 2 - Perform COT of the required containment atmosphere particulate radioactivity monitor.

3.4.15.3 Perform CHANNEL CALIBRATION of the 3.4.15.3 Perform CHANNEL CALIBRATION of the Administrative Variation -

required containment sump monitor. required containment pocket sump level Section 2.2.1.1 monitor.

3.4.15.4 Perform CHANNEL CALIBRATION of the 3.4.15.4 Perform CHANNEL CALIBRATION of the Administrative Variation -

required containment atmosphere radioactivity required containment atmosphere particulate Section 2.2.1.1 monitor. radioactivity monitor.

3.4.15.5 Perform CHANNEL CALIBRATION of the N/A N/A Administrative Variation -

required containment air cooler condensate Section 2.2.1.2 flow rate monitor.

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3.4.16 RCS Specific Activity 3.4.16 RCS Specific Activity 3.4.16.1 Verify reactor coolant gross specific activity 3.4.16.1 Verify reactor coolant gross specific activity No variation 100/ Ci/gm. < 100/CE PCi/gm.

3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT Administrative Variation -

I-131 specific activity 1.0 Ci/gm. I-131 specific activity d 0.265 PCi/gm. Section 2.2.1.1 3.4.16.3 Determine from a sample taken in MODE 1 3.4.16.3 Determine from a sample taken in MODE 1 No variation after a minimum of 2 effective full power days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. for t 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

3.4.17 RCS Loop Isolation Valves N/A N/A 3.4.17.1 Verify each RCS loop isolation valve is open N/A N/A Administrative Variation -

and power is removed from each loop isolation Section 2.2.1.2 valve operator.

3.4.19 RCS Loops - Test Exceptions N/A N/A 3.4.19.1 Verify THERMAL POWER is < P-7. N/A N/A Administrative Variation -

Section 2.2.1.2 3.5.1 Accumulators 3.5.1 Accumulators 3.5.1.1 Verify each accumulator isolation valve is fully 3.5.1.1 Verify each accumulator isolation valve is No variation open. fully open.

3.5.1.2 Verify borated water volume in each 3.5.1.2 Verify borated water volume in each No variation accumulator is [ 7853 gallons ( )% and accumulator is t 7630 gallons and d 8000 8171 gallons ( )%]. gallons.

3.5.1.3 Verify nitrogen cover pressure in each 3.5.1.3 Verify nitrogen cover pressure in each No variation accumulator is [385] psig and [481] psig. accumulator is t 610 psig and d 660 psig.

3.5.1.4 Verify boron concentration in each accumulator 3.5.1.4 Verify boron concentration in each No variation is [1900] ppm and [2100] ppm. accumulator is t 3000 ppm and d 3300 ppm.

3.5.1.5 Verify power is removed from each 3.5.1.5 Verify power is removed from each No variation accumulator isolation valve operator when accumulator isolation valve operator when RCS pressure is [2000] psig. pressurizer pressure is t 1000 psig.

3.5.2 ECCS - Operating 3.5.2 ECCS - Operating 3.5.2.1 Verify the following valves are in the listed 3.5.2.1 Verify the following valves are in the listed No variation position with power to the valve operator position with power to the valve operator removed. removed.

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3.5.2.2 Verify each ECCS manual, power operated, 3.5.2.2 Verify each ECCS manual, power operated, No variation and automatic valve in the flow path, that is not and automatic valve in the flow path, that is locked, sealed, or otherwise secured in not locked, sealed, or otherwise secured in position, is in the correct position. position, is in the correct position.

3.5.2.3 Verify ECCS piping is full of water. 3.5.2.3 Verify ECCS piping is full of water. Administrative Variation -

Section 2.2.1.4 3.5.2.5 Verify each ECCS automatic valve in the flow 3.5.2.5 Verify each ECCS automatic valve in the flow No variation path that is not locked, sealed, or otherwise path that is not locked, sealed, or otherwise secured in position, actuates to the correct secured in position, actuates to the correct position on an actual or simulated actuation position on an actual or simulated actuation signal. signal.

3.5.2.6 Verify each ECCS pump starts automatically 3.5.2.6 Verify each ECCS pump starts automatically No variation on an actual or simulated actuation signal. on an actual or simulated actuation signal.

3.5.2.7 Verify, for each ECCS throttle valve listed 3.5.2.7 Verify for each ECCS throttle valve listed No variation below, each position stop is in the correct below, each position stop is in the correct position. position.

3.5.2.8 Verify, by visual inspection, each ECCS train 3.5.2.8 Verify, by visual inspection, each ECCS train No variation containment sump suction inlet is not restricted containment sump suction inlet is not by debris and the suction inlet trash racks and restricted by debris and the suction inlet screens show no evidence of structural trash racks and screens show no evidence of distress or abnormal corrosion. structural distress or abnormal corrosion.

3.5.4 Refueling Water Storage Tank (RWST) 3.5.4 Refueling Water Storage Tank (RWST) 3.5.4.1 Verify RWST borated water temperature is 3.5.4.1 Verify RWST borated water temperature is No variation

[35]°F and [100]°F. t 60°F and d 105°F.

3.5.4.2 Verify RWST borated water volume is 3.5.4.2 Verify RWST borated water volume is No variation

[466,200 gallons ( )%]. t 370,000 gallons.

3.5.4.3 Verify RWST boron concentration is [2000] 3.5.4.3 Verify boron concentration in the RWST is Administrative Variation -

ppm and [2200] ppm. t 3100 ppm and d 3300 ppm. Section 2.2.1.1 3.5.5 Seal Injection Flow 3.5.5 Seal Injection Flow 3.5.5.1 Verify manual seal injection throttle valves are 3.5.5.1 Verify manual seal injection throttle valves No variation adjusted to give a flow [resistance] [of [40 are adjusted to give a flow within limit with gpm] with [centrifugal charging pump discharge charging pump discharge header pressure header] pressure [2480] psig and the t 2430 psig and the pressurizer level control

[charging flow] control valve full open or valve full open.

[0.2117] ft/gpm2 or within the limit of Figure 3.5.5-1.]

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3.5.6 Boron Injection Tank (BIT) N/A N/A 3.5.6.1 Verify BIT borated water temperature is N/A N/A Administrative Variation -

[145]°F. Section 2.2.1.2 3.5.6.2 Verify BIT borated water volume is [1100] N/A N/A Administrative Variation -

gallons. Section 2.2.1.2 3.5.6.3 Verify BIT boron concentration is [20,000] N/A N/A Administrative Variation -

ppm and [22,500] ppm. Section 2.2.1.2 3.6.2 Containment Air Locks (Atmospheric, 3.6.2 Containment Air Locks Subatmospheric, Ice Condenser, and Dual) 3.6.2.2 Verify only one door in the air lock can be 3.6.2.2 Verify only one door in the air lock can be No variation opened at a time. opened at a time.

3.6.3 Containment Isolation Valves (Atmospheric, 3.6.3 Containment Isolation Valves Subatmospheric, Ice Condenser, and Dual) 3.6.3.1 Verify each [42] inch purge valve is sealed N/A N/A Administrative Variation -

closed, except for one purge valve in a Section 2.2.1.2 penetration flow path while in Condition E of this LCO.

3.6.3.2 Verify each [8] inch purge valve is closed, 3.6.3.1 Verify each containment purge valve is Administrative Variation -

except when the [8] inch containment purge closed, except when the containment purge Section 2.2.1.1 valves are open for pressure control, ALARA or valves are open for pressure control, ALARA air quality considerations for personnel entry, or air quality considerations for personnel or for Surveillances that require the valves to entry, or for Surveillances that require the be open. valves to be open.

3.6.3.3 Verify each containment isolation manual valve 3.6.3.2 Verify each containment isolation manual Administrative Variation -

and blind flange that is located outside valve and blind flange that is located outside Section 2.2.1.1 containment and not locked, sealed, or containment, the containment annulus, and otherwise secured and required to be closed the Main Steam Valve Vault Rooms, and not during accident conditions is closed, except for locked, sealed, or otherwise secured and containment isolation valves that are open required to be closed during accident under administrative controls. conditions is closed, except for containment isolation valves that are open under administrative controls.

3.6.3.5 Verify the isolation time of each automatic 3.6.3.4 Verify the isolation time of each power Administrative Variation -

power operated containment isolation valve is operated and each automatic containment Section 2.2.1.1 within limits. isolation valve is within limits.

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3.6.3.6 Cycle each weight or spring loaded check N/A N/A Administrative Variation -

valve testable during operation through one Section 2.2.1.2 complete cycle of full travel, and verify each check valve remains closed when the differential pressure in the direction of flow is

[1.2] psid and opens when the differential pressure in the direction of flow is [1.2] psid and < [5.0] psid.

3.6.3.7 Perform leakage rate testing for containment 3.6.3.5 Perform leakage rate testing for containment Administrative Variation -

purge valves with resilient seals. purge valves with resilient seals. Section 2.2.1.2. This SR is ineligible for change due to WBN 1/2 License Amendment 123/24.

3.6.3.8 Verify each automatic containment isolation 3.6.3.6 Verify each automatic containment isolation Administrative Variation -

valve that is not locked, sealed or otherwise valve that is not locked, sealed, or otherwise Section 2.2.1.1 secured in position, actuates to the isolation secured in position, actuates to the isolation position on an actual or simulated actuation position on an actual or simulated actuation signal. signal.

3.6.3.9 Cycle each weight or spring loaded check N/A N/A Administrative Variation -

valve not testable during operation through one Section 2.2.1.2 complete cycle of full travel, and verify each check valve remains closed when the differential pressure in the direction of flow is

[1.2] psid and opens when the differential pressure in the direction of flow is [1.2] psid and < [5.0] psid.

3.6.3.10 Verify each [ ] inch containment purge valve is 3.6.3.7 Verify each 24 inch containment lower Administrative Variation -

blocked to restrict the valve from opening compartment purge supply and exhaust Section 2.2.1.1

> [50]%. isolation valve is blocked to restrict the valve from opening > 50q.

3.6.4A Containment Pressure (Atmospheric, Dual, 3.6.4 Containment Pressure and Ice Condenser) 3.6.4A.1 Verify containment pressure is within limits. 3.6.4.1 Verify containment pressure is within limits. Administrative Variation -

Section 2.2.1.1 CNL-19-084 E4-16 of 36

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3.6.5B Containment Air Temperature (Ice 3.6.5 Containment Air Temperature Condenser) 3.6.5B.1 Verify containment upper compartment 3.6.5.1 Verify containment upper compartment Administrative Variation -

average air temperature is within limits. average air temperature is within limits. Section 2.2.1.1 3.6.5B.2 Verify containment lower compartment average 3.6.5.2 Verify containment lower compartment Administrative Variation -

air temperature is within limits. average air temperature is within limits. Section 2.2.1.1 3.6.6C Containment Spray System (Ice Condenser) 3.6.6 Containment Spray System 3.6.6C.1 Verify each containment spray manual, power 3.6.6.1 Verify each containment spray manual, Administrative Variation -

operated, and automatic valve in the flow path power operated, and automatic valve in the Section 2.2.1.1 that is not locked, sealed, or otherwise secured flow path that is not locked, sealed, or in position is in the correct position. otherwise secured in position is in the correct position.

3.6.6C.3 Verify each automatic containment spray valve 3.6.6.3 Verify each automatic containment spray Administrative Variation -

in the flow path that is not locked, sealed, or valve in the flow path that is not locked, Section 2.2.1.1 otherwise secured in position, actuates to the sealed, or otherwise secured in position, correct position on an actual or simulated actuates to the correct position on an actual actuation signal. or simulated actuation signal.

3.6.6C.4 Verify each containment spray pump starts 3.6.6.4 Verify each containment spray pump starts Administrative Variation -

automatically on an actual or simulated automatically on an actual or simulated Section 2.2.1.1 actuation signal. actuation signal.

3.6.6C.5 Verify each spray nozzle is unobstructed. 3.6.6.5 Verify each spray nozzle is unobstructed. Administrative Variation -

Section 2.2.1.1 3.6.7 Spray Additive System (Atmospheric, N/A N/A Subatmospheric, Ice Condenser, and Dual) 3.6.7.1 Verify each spray additive manual, power N/A N/A Administrative Variation -

operated, and automatic valve in the flow path Section 2.2.1.2 that is not locked, sealed, or otherwise secured in position is in the correct position.

3.6.7.2 Verify spray additive tank solution volume is N/A N/A Administrative Variation -

[2568] gal and [4000] gal. Section 2.2.1.2 3.6.7.3 Verify spray additive tank [NaOH] solution N/A N/A Administrative Variation -

concentration is [30]% and [32]% by Section 2.2.1.2 weight.

3.6.7.4 Verify each spray additive automatic valve in N/A N/A Administrative Variation -

the flow path that is not locked, sealed, or Section 2.2.1.2 otherwise secured in position, actuates to the CNL-19-084 E4-17 of 36

Enclosure 4 TSTF-425 NUREG-1431 Technical Specification WBN WBN Technical Specification Section Disposition and Section/ Section Title/Surveillance Description Section/ Title/Surveillance Description Attachment 1 Reference SR No. SR No.

correct position on an actual or simulated actuation signal.

3.6.7.5 Verify spray additive flow [rate] from each N/A N/A Administrative Variation -

solution's flow path. Section 2.2.1.2 3.6.8 Shield Building (Dual and Ice Condenser) 3.6.15 Shield Building 3.6.8.1 Verify annulus negative pressure is > [5] 3.6.15.1 Verify annulus negative pressure is equal to Administrative Variation -

inches water gauge. or more negative than -5 inches water gauge Section 2.2.1.1 with respect to the atmosphere.

3.6.8.2 Verify one shield building access door in each 3.6.15.2 Verify the door in each access opening is Administrative Variation -

access opening is closed. closed, except when the access opening is Section 2.2.1.1 being used for normal transient entry and exit.

3.6.8.4 Verify the shield building can be maintained at 3.6.15.4 Verify each Emergency Gas Treatment Administrative Variation -

a pressure equal to or more negative than System train with final flow t 3600 and Section 2.2.1.1

[- 0.5] inch water gauge in the annulus by one d 4400 cfm produces an annulus pressure Shield Building Air Cleanup System train with equal to or more negative than -0.61 inch final flow [ ] cfm within [22] seconds after a water gauge at elevation 783 with respect to start signal. the atmosphere and with an inleakage of d 250 cfm.

3.6.9 Hydrogen Mixing System (HMS) N/A N/A (Atmospheric, Ice Condenser, and Dual) 3.6.9.1 Operate each HMS train for 15 minutes. N/A N/A Administrative Variation -

Section 2.2.1.2 3.6.9.2 Verify each HMS train flow rate on slow speed N/A N/A Administrative Variation -

is [4000] cfm. Section 2.2.1.2 3.6.9.3 Verify each HMS train starts on an actual or N/A N/A Administrative Variation -

simulated actuation signal. Section 2.2.1.2 3.6.10 Hydrogen Ignition System (HIS) (Ice 3.6.8 Hydrogen Mitigation System (HMS)

Condenser) 3.6.10.1 Energize each HIS train power supply breaker 3.6.8.1 Energize each HMS train power supply Administrative Variation -

and verify [32] ignitors are energized in each breaker and verify t 33 ignitors are Section 2.2.1.4 train. energized in each train.

3.6.10.2 Verify at least one hydrogen ignitor is 3.6.8.2 Verify at least one hydrogen ignitor is Administrative Variation -

OPERABLE in each containment region. OPERABLE in each containment region. Section 2.2.1.1 CNL-19-084 E4-18 of 36

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3.6.10.3 Energize each hydrogen ignitor and verify 3.6.8.3 Energize each hydrogen ignitor and verify Administrative Variation -

temperature is [1700]°F. temperature is t 1700qF. Section 2.2.1.1 3.6.13 Shield Building Air Cleanup System 3.6.9 Emergency Gas Treatment System (SBACS) (Dual and Ice Condenser) (EGTS) 3.6.13.1 Operate each SBACS train for [ 10 3.6.9.1 Operate each EGTS train for t 15 continuous Administrative Variation -

continuous hours with heaters operating or (for minutes with heaters operating. Section 2.2.1.1 systems without heaters) 15 minutes].

3.6.13.3 Verify each SBACS train actuates on an actual 3.6.9.3 Verify each EGTS train actuates on an actual Administrative Variation -

or simulated actuation signal. or simulated actuation signal. Section 2.2.1.1 3.6.13.4 Verify each SBACS filter bypass damper can N/A N/A Administrative Variation -

be opened. Section 2.2.1.2 3.6.13.5 Verify each SBACS train flow rate is [ ] cfm. 3.6.9.4 Verify each EGTS train produces a flow rate Administrative Variation -

t 3600 and d 4400 cfm within 20 seconds Section 2.2.1.1 from the initiation of a Containment Isolation Phase A signal.

3.6.14 Air Return System (ARS) (Ice Condenser) 3.6.10 Air Return System (ARS) 3.6.14.1 Verify each ARS fan starts on an actual or 3.6.10.1 Verify each ARS fan starts on an actual or Administrative Variation -

simulated actuation signal, after a delay of simulated actuation signal, after a delay of Section 2.2.1.1

[9.0] minutes and [11.0] minutes, and t 8.0 minutes and d 10.0 minutes, operates for 15 minutes. and operates for t 15 minutes.

3.6.14.2 Verify, with the ARS fan dampers closed, each 3.6.10.2 Verify, with the ARS fan dampers closed, Administrative Variation -

ARS fan motor current is [20.5] amps and each ARS fan motor current is t 54 amps Section 2.2.1.1

[35.5] amps [when the fan speed is [840] and d 94 amps.

rpm and [900] rpm].

3.6.14.3 Verify, with the ARS fan not operating, each 3.6.10.3 Verify, with the ARS fan not operating, each Administrative Variation -

ARS fan damper opens when [11.0] lb is ARS fan damper opens when d 92.4 in-lb is Section 2.2.1.1 applied to the counterweight. applied.

3.6.14.4 Verify each motor operated valve in the N/A N/A Administrative Variation -

hydrogen collection header that is not locked, Section 2.2.1.2 sealed, or otherwise secured in position, opens on an actual or simulated actuation signal after a delay of [9.0] minutes and [11.0] minutes.

3.6.15 Ice Bed (Ice Condenser) 3.6.11 Ice Bed 3.6.15.1 Verify maximum ice bed temperature is 3.6.11.1 Verify maximum ice bed temperature is Administrative Variation -

[27]°F. d 27qF. Section 2.2.1.1 CNL-19-084 E4-19 of 36

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3.6.15.2 Verify total mass of stored ice is [2,200,000] 3.6.11.2 Verify total weight of stored ice is greater Administrative Variation -

lbs by calculating the mass of stored ice, at a than or equal to 2,404,500 lb by: Section 2.2.1.1 95% confidence level, in each of three Radial Zones as defined below, by selecting a random a. Weighing a representative sample of sample of 30 ice baskets in each Radial t 144 ice baskets and verifying each Zone, and basket contains greater than or equal to 1237 lb of ice; and Verify: b. Calculating total weight of stored ice, at a 95 percent confidence level, using all

1. Zone A (radial rows [7,8,9]), has a total ice basket weights determined in mass of [733,400] lbs. SR 3.6.11.2.a.
2. Zone B (radial rows [4,5,6]), has a total mass of [733,400] lbs.
3. Zone C (radial rows [1,2,3]), has a total mass of [733,400] lbs.

3.6.15.3 Verify that the ice mass of each basket 3.6.11.3 Verify azimuthal distribution of ice at a 95 Administrative Variation -

sampled in SR 3.6.15.2 is 600 lbs. percent confidence level by subdividing Section 2.2.1.1 weights, as determined by SR 3.6.11.2.a, into the following groups:

a. Group 1-bays 1 through 8;
b. Group 2-bays 9 through 16; and
c. Group 3-bays 17 through 24.

The average ice weight of the sample baskets in each group from radial rows 1, 2, 4, 6, 8, and 9 shall be greater than or equal to 1237 lb.

3.6.15.4 Verify, by visual inspection, accumulation of ice 3.6.11.4 Verify, by visual inspection, accumulation of Administrative Variation -

on structural members comprising flow ice on structural members comprising flow Section 2.2.1.1 channels through the ice bed is 15 percent channels through the ice bed is less than or blockage of the total flow area for each safety equal to 15 percent blockage of the total flow analysis section. area for each safety analysis section.

3.6.15.5 Verify, by chemical analysis of the stored ice in 3.6.11.5 Verify, by chemical analysis of the stored ice Administrative Variation -

at least one randomly selected ice basket from in at least one randomly selected ice basket Section 2.2.1.1 each ice condenser bay, that ice bed: from each ice condenser bay, that ice bed:

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a. Boron concentration is a [1800] ppm and a. Boron concentration is t 1800 ppm and

[2000] ppm and d 2000 ppm; and

b. pH is [9.0] and [9.5]. b. pH is t 9.0 and d 9.5.

3.6.15.6 Visually inspect, for detrimental structural wear, 3.6.11.6 Visually inspect, for detrimental structural Administrative Variation -

cracks, corrosion, or other damage, two ice wear, cracks, corrosion, or other damage, Section 2.2.1.1 baskets from each group of bays as defined two ice baskets from each azimuthal group of below: bays. See SR 3.6.11.3.

a. Group 1 - bays 1 through 8;
b. Group 2 - bays 9 through 16; and
c. Group 3 - bays 17 through 24.

3.6.16 Ice Condenser Doors (Ice Condenser) 3.6.12 Ice Condenser Doors 3.6.16.1 Verify all inlet doors indicate closed by the Inlet 3.6.12.1 Verify all inlet doors indicate closed by the Administrative Variation -

Door Position Monitoring System. Inlet Door Position Monitoring System. Section 2.2.1.1 3.6.16.2 Verify, by visual inspection, each intermediate 3.6.12.2 Verify, by visual inspection, each Administrative Variation -

deck door is closed and not impaired by ice, intermediate deck door is closed and not Section 2.2.1.1 frost, or debris. impaired by ice, frost, or debris.

3.6.16.3 Verify, by visual inspection, each inlet door is 3.6.12.3 Verify, by visual inspection, each inlet door is Administrative Variation -

not impaired by ice, frost, or debris. not impaired by ice, frost, or debris. Section 2.2.1.4 3.6.16.4 Verify torque required to cause each inlet door 3.6.12.4 Verify torque required to cause each inlet Administrative Variation -

to begin to open is [675] in-lb. door to begin to open is d 675 in-lb. Section 2.2.1.4 3.6.16.5 Perform a torque test on [a sampling of 25% 3.6.12.5 Perform a torque test on a sampling of Administrative Variation -

of the] inlet doors. t 50% of the inlet doors. Section 2.2.1.4 3.6.16.6 Verify for each intermediate deck door: 3.6.12.6 Verify for each intermediate deck door: Administrative Variation -

a. No visual evidence of structural a. No visual evidence of structural Section 2.2.1.1 deterioration, deterioration;
b. Free movement of the vent assemblies, and b. Free movement of the vent assemblies;
c. Free movement of the door. and
c. Free movement of the door.

3.6.16.7 Verify, by visual inspection, each top deck 3.6.12.7 Verify, by visual inspection, each top deck Administrative Variation -

[door]: door: Section 2.2.1.1

a. Is in place; and a. Is in place;
b. Has no condensation, frost, or ice formed on b. Free movement of top deck vent the [door] that would restrict its opening. assembly; and
c. Has no condensation, frost, or ice formed on the door that would restrict its opening.

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3.6.17 Divider Barrier Integrity (Ice Condenser) 3.6.13 Divider Barrier Integrity 3.6.17.2 Verify, by visual inspection, that the seals and 3.6.13.2 Verify, by visual inspection, that the seals Administrative Variation -

sealing surfaces of each personnel access and sealing surfaces of each personnel Section 2.2.1.1 door and equipment hatch have: access door and equipment hatch have:

a. No detrimental misalignments, a. No detrimental misalignments;
b. No cracks or defects in the sealing surfaces, b. No cracks or defects in the sealing and surfaces; and
c. No apparent deterioration of the seal c. No apparent deterioration of the seal material. material.

3.6.17.4 Remove two divider barrier seal test coupons N/A N/A Administrative Variation -

and verify: Section 2.2.1.1

a. Both test coupons' tensile strength is

[120] psi and

[ b. Both test coupons' elongation is [100]%. ]

3.6.17.5 Visually inspect [95]% of the divider barrier 3.6.13.5 Visually inspect t 95% of the divider barrier Administrative Variation -

seal length, and verify: seal length, and verify: Section 2.2.1.1

a. Seal and seal mounting bolts are properly a. Seal and seal mounting bolts are properly installed and installed; and
b. Seal material shows no evidence of b. Seal material shows no evidence of deterioration due to holes, ruptures, deterioration due to holes, ruptures, chemical attack, abrasion, radiation chemical attack, abrasion, radiation damage, or changes in physical damage, or changes in physical appearance. appearance.

3.6.18 Containment Recirculation Drains (Ice 3.6.14 Containment Recirculation Drains Condenser) 3.6.18.1 Verify, by visual inspection, that: 3.6.14.1 Verify, by visual inspection, that: Administrative Variation -

a. Each refueling canal drain plug is removed, a. Each refueling canal drain plug is Section 2.2.1.1
b. Each refueling canal drain is not obstructed removed; by debris, and b. Each refueling canal drain is not
c. No debris is present in the upper obstructed by debris; and compartment or refueling canal that could c. No debris is present in the upper obstruct the refueling canal drain. compartment or refueling canal that could obstruct the refueling canal drain.

3.6.18.2 Verify for each ice condenser floor drain that 3.6.14.2 Verify for each ice condenser floor drain that Administrative Variation -

the: the: Section 2.2.1.1

a. Valve opening is not impaired by ice, frost, a. Gate opening is not impaired by ice, frost, or debris, or debris; CNL-19-084 E4-22 of 36

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b. Valve seat shows no evidence of damage, b. Gate seat shows no evidence of damage;
c. Valve opening force is [66] lb, and c. Gate opening force is d 100 lb; and
d. Drain line from the ice condenser floor to d. Drain line from the ice condenser floor to the lower compartment is unrestricted. the lower compartment is unrestricted.

3.7.2 Main Steam Isolation Valves (MSIVs) 3.7.2 Main Steam Isolation Valves (MSIVs) 3.7.2.2 Verify each MSIV actuates to the isolation 3.7.2.1 Verify closure time of each MSIV is d 6.0 Administrative Variation -

position on an actual or simulated actuation seconds on an actual or simulated actuation Section 2.2.1.1 signal. signal.

3.7.3 Main Feedwater Isolation Valves (MFIVs) 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves and Main Feedwater Regulation Valves (MFRVs) and [Associated Bypass Valves] (MFRVs) and Associated Bypass Valves 3.7.3.2 Verify each MFIV, MFRV[, and associated 3.7.3.1 Verify the closure time of each MFIV, MFRV, Administrative Variation -

bypass valves] actuates to the isolation and associated bypass valve is Section 2.2.1.1 position on an actual or simulated actuation d 6.5 seconds on an actual or simulated signal. actuation signal.

3.7.4 Atmospheric Dump Valves (ADVs) 3.7.4 Atmospheric Dump Valves (ADVs) 3.7.4.1 Verify one complete cycle of each ADV. 3.7.4.1 Verify one complete cycle of each ADV. No variation 3.7.4.2 Verify one complete cycle of each ADV block 3.7.4.2 Verify one complete cycle of each ADV block No variation valve. valve.

3.7.5 Auxiliary Feedwater (AFW) System 3.7.5 Auxiliary Feedwater (AFW) System 3.7.5.1 Verify each AFW manual, power operated, and 3.7.5.1 Verify each AFW manual, power operated, No variation automatic valve in each water flow path, [and and automatic valve in each water flow path, in both steam supply flow paths to the steam and in both steam supply flow paths to the turbine driven pump,] that is not locked, sealed, steam turbine driven pump, that is not or otherwise secured in position, is in the locked, sealed, or otherwise secured in correct position. position, is in the correct position.

N/A N/A 3.7.5.2 Verify the developed head of each AFW Technical Variation -

pump at the flow test point is greater than or Section 2.2.2.1 equal to the required developed head.

3.7.5.3 Verify each AFW automatic valve that is not 3.7.5.3 Verify each AFW automatic valve that is not No variation locked, sealed, or otherwise secured in locked, sealed, or otherwise secured in position, actuates to the correct position on an position, actuates to the correct position on actual or simulated actuation signal. an actual or simulated actuation signal.

3.7.5.4 Verify each AFW pump starts automatically on 3.7.5.4 Verify each AFW pump starts automatically No variation an actual or simulated actuation signal. on an actual or simulated actuation signal.

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3.7.6 Condensate Storage Tank (CST) 3.7.6 Condensate Storage Tank (CST) 3.7.6.1 Verify the CST level is [110,000 gal]. 3.7.6.1 Verify the CST level is t 200,000 gal. No variation 3.7.7 Component Cooling Water (CCW) System 3.7.7 Component Cooling System (CCS)

N/A N/A 3.7.7.1 Verify that the alternate feeder breaker to the Administrative Variation -

C-S pump is open. Section 2.2.1.5 3.7.7.1 Verify each CCW manual, power operated, and 3.7.7.2 Verify each CCS manual, power operated, Administrative Variation -

automatic valve in the flow path servicing and automatic valve in the flow path Section 2.2.1.1 safety related equipment, that is not locked, servicing safety related equipment, that is not sealed, or otherwise secured in position, is in locked, sealed, or otherwise secured in the correct position. position, is in the correct position.

3.7.7.2 Verify each CCW automatic valve in the flow 3.7.7.3 Verify each CCS automatic valve in the flow Administrative Variation -

path that is not locked, sealed, or otherwise path that is not locked, sealed, or otherwise Section 2.2.1.1 secured in position, actuates to the correct secured in position, actuates to the correct position on an actual or simulated actuation position on an actual or simulated actuation signal. signal.

3.7.7.3 Verify each CCW pump starts automatically on 3.7.7.4 Verify each CCS pump starts automatically Administrative Variation -

an actual or simulated actuation signal. on an actual or simulated actuation signal. Section 2.2.1.1 N/A N/A 3.7.7.5 Unit 1 - Verify CCS pump 2B-B is aligned to Administrative Variation -

CCS Train B and is in operation. Section 2.2.1.5 Unit 2 - Verify CCS pump 1B-B is aligned to CCS Train B and is in operation.

3.7.8 Service Water System (SWS) 3.7.8 Essential Raw Cooling Water (ERCW)

System 3.7.8.1 Verify each SWS manual, power operated, and 3.7.8.1 Verify each ERCW manual, power operated, Administrative Variation -

automatic valve in the flow path servicing and automatic valve in the flow path Section 2.2.1.1 safety related equipment, that is not locked, servicing safety related equipment, that is not sealed, or otherwise secured in position, is in locked, sealed, or otherwise secured in the correct position. position, is in the correct position.

3.7.8.2 Verify each SWS automatic valve in the flow 3.7.8.2 Verify each ERCW automatic valve in the Administrative Variation -

path that is not locked, sealed, or otherwise flow path that is not locked, sealed, or Section 2.2.1.1 secured in position, actuates to the correct otherwise secured in position, actuates to the position on an actual or simulated actuation correct position on an actual or simulated signal. actuation signal.

3.7.8.3 Verify each SWS pump starts automatically on 3.7.8.3 Verify each ERCW pump starts automatically Administrative Variation -

an actual or simulated actuation signal. on an actual or simulated actuation signal. Section 2.2.1.1 CNL-19-084 E4-24 of 36

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3.7.9 Ultimate Heat Sink (UHS) 3.7.9 Ultimate Heat Sink (UHS) 3.7.9.1 Verify water level of UHS is [562] ft [mean N/A N/A Administrative Variation -

sea level]. Section 2.2.1.2 3.7.9.2 Verify average water temperature of UHS is 3.7.9.1 Verify average water temperature of UHS is Administrative Variation -

[90]°F. d 85qF. Section 2.2.1.1 3.7.9.3 Operate each cooling tower fan for [15] N/A N/A Administrative Variation -

minutes. Section 2.2.1.2 3.7.9.4 Verify each cooling tower fan starts N/A N/A Administrative Variation -

automatically on an actual or simulated Section 2.2.1.2 actuation signal.

3.7.10 Control Room Emergency Filtration System 3.7.10 Control Room Emergency Ventilation (CREFS) System (CREVS) 3.7.10.1 Operate each CREFS train for [ 10 3.7.10.1 Operate each CREVS train for t 15 minutes. Administrative Variation -

continuous hours with the heaters operating or Section 2.2.1.1 (for systems without heaters) 15 minutes].

3.7.10.3 Verify each CREFS train actuates on an actual 3.7.10.3 Verify each CREVS train actuates on an Administrative Variation -

or simulated actuation signal. actual or simulated actuation signal. Section 2.2.1.1 3.7.10.4 Verify one CREFS train can maintain a positive N/A N/A Administrative Variation -

pressure of [0.125] inches water gauge, Section 2.2.1.2 relative to the adjacent [turbine building] during the pressurization mode of operation at a makeup flow rate of [3000] cfm.

3.7.11 Control Room Emergency Air Temperature 3.7.11 Control Room Emergency Air Control System (CREATCS) Temperature Control System (CREATCS) 3.7.11.1 Verify each CREATCS train has the capability 3.7.11.1 Verify each CREATCS train has the No variation to remove the assumed heat load. capability to remove the assumed heat load.

3.7.12 Emergency Core Cooling System (ECCS) 3.7.12 Auxiliary Building Gas Treatment System Pump Room Exhaust Air Cleanup System (ABGTS)

(PREACS) 3.7.12.1 Operate each ECCS PREACS train for [ 10 3.7.12.1 Operate each ABGTS train for Administrative Variation -

continuous hours with the heaters operating or t 15 continuous minutes with the heaters Section 2.2.1.1 (for systems without heaters) 15 minutes]. operating.

3.7.12.3 Verify each ECCS PREACS train actuates on 3.7.12.3 Verify each ABGTS train actuates on an Administrative Variation -

an actual or simulated actuation signal. actual or simulated actuation signal. Section 2.2.1.1 CNL-19-084 E4-25 of 36

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3.7.12.4 Verify one ECCS PREACS train can maintain a 3.7.12.4 Verify one ABGTS train can maintain a Administrative Variation -

pressure [-0.125] inches water gauge relative pressure between -0.25 and -0.5 inches Section 2.2.1.1 to atmospheric pressure during the [post water gauge with respect to atmospheric accident] mode of operation at a flow rate of pressure during the post accident mode of

[3000] cfm. operation at a flow rate t 9300 and d 9900 cfm.

3.7.12.5 Verify each ECCS PREACS filter bypass N/A N/A Administrative Variation -

damper can be closed. Section 2.2.1.2 3.7.13 Fuel Building Air Cleanup System (FBACS) N/A N/A 3.7.13.1 Operate each FBACS train for [ 10 continuous N/A N/A Administrative Variation -

hours with the heaters operating or (for Section 2.2.1.2 systems without heaters) 15 minutes].

3.7.13.3 Verify each FBACS train actuates on an actual N/A N/A Administrative Variation -

or simulated actuation signal. Section 2.2.1.2 3.7.13.4 Verify one FBACS train can maintain a N/A N/A Administrative Variation -

pressure [-0.125] inches water gauge with Section 2.2.1.2 respect to atmospheric pressure during the

[post accident] mode of operation at a flow rate

[20,000] cfm.

3.7.13.5 Verify each FBACS filter bypass damper can N/A N/A Administrative Variation -

be closed. Section 2.2.1.2 3.7.14 Penetration Room Exhaust Air Cleanup N/A N/A System (PREACS) 3.7.14.1 Operate each PREACS train for [ 10 N/A N/A Administrative Variation -

continuous hours with heaters operating or (for Section 2.2.1.2 systems without heaters) 15 minutes].

3.7.14.3 Verify each PREACS train actuates on an N/A N/A Administrative Variation -

actual or simulated actuation signal. Section 2.2.1.2 3.7.14.4 Verify one PREACS train can maintain a N/A N/A Administrative Variation -

pressure [-0.125] inches water gauge relative Section 2.2.1.2 to atmospheric pressure during the [post accident] mode of operation at a flow rate of

[3000] cfm.

3.7.14.5 Verify each PREACS filter bypass damper can N/A N/A Administrative Variation -

be closed. Section 2.2.1.2 CNL-19-084 E4-26 of 36

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3.7.15 Fuel Storage Pool Water Level 3.7.13 Fuel Storage Pool Water Level 3.7.15.1 Verify the fuel storage pool water level is 23 3.7.13.1 Verify the fuel storage pool water level is Administrative Variation -

ft above the top of the irradiated fuel t 23 ft above the top of the irradiated fuel Section 2.2.1.1 assemblies seated in the storage racks. assemblies seated in the storage racks.

3.7.16 Fuel Storage Pool Boron Concentration 3.7.18 Fuel Storage Pool Water Level 3.7.16.1 Verify the fuel storage pool boron 3.7.18.1 Verify the fuel storage pool concentration is Administrative Variation -

concentration is within limit. within limit. Section 2.2.1.1 3.7.18 Secondary Specific Activity 3.7.14 Secondary Specific Activity 3.7.18.1 Verify the specific activity of the secondary 3.7.14.1 Verify the specific activity of the secondary Administrative Variation -

coolant is [0.10] Ci/gm DOSE coolant is d 0.10 PCi/gm DOSE Section 2.2.1.1 EQUIVALENT I-131. EQUIVALENT I-131.

N/A N/A 3.7.16 Component Cooling System (CCS) -

Shutdown N/A N/A 3.7.16.1 Verify correct breaker alignment and Administrative Variation -

indicated power available to the required Section 2.2.1.5 pump(s) that is not in operation.

N/A N/A 3.7.16.2 Verify two CCS pumps are aligned to CCS Administrative Variation -

Train B. Section 2.2.1.5 N/A N/A 3.7.17 Essential Raw Cooling Water (ERCW)

System - Shutdown N/A N/A 3.7.17.1 Verify correct breaker alignment and Administrative Variation -

indicated power available to the required Section 2.2.1.5 pump(s) that is not in operation.

3.8.1 AC Sources - Operating 3.8.1 AC Sources - Operating 3.8.1.1 Verify correct breaker alignment and indicated 3.8.1.1 Verify correct breaker alignment and No variation power availability for each [required] offsite indicated power availability for each required circuit. offsite circuit.

3.8.1.2 Verify each DG starts from standby conditions 3.8.1.2 Verify each DG starts from standby Administrative Variation -

and achieves steady state voltage [3740] V conditions and achieves steady state voltage Section 2.2.1.1 and [4580] V, and frequency [58.8] Hz and t 6800 V and d 7260 V, and frequency of

[61.2] Hz. [Frequency - 31 days] 60 Hz nominal. [Frequency - As specified in The SFCP is not adopted Table 3.8.1-1] for this SR CNL-19-084 E4-27 of 36

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3.8.1.3 Verify each DG is synchronized and loaded 3.8.1.3 Verify each DG is synchronized and loaded Administrative Variation -

and operates for 60 minutes at a load and operates for t 60 minutes at a load Section 2.2.1.1

[4500] kW and [5000] kW. [Frequency - 31 t 3960 kW and d 4400 kW. [Frequency - As days] specified in Table 3.8.1-1] The SFCP is not adopted for this SR 3.8.1.4 Verify each day tank [and engine mounted 3.8.1.4 Verify each skid mounted day tank contains Administrative Variation -

tank] contains [220] gal of fuel oil. t 218.5 gal of fuel oil. Section 2.2.1.1 3.8.1.5 Check for and remove accumulated water from 3.8.1.5 Check for and remove accumulated water Administrative Variation -

each day tank [and engine mounted tank]. from each skid mounted day tank. Section 2.2.1.1 3.8.1.6 Verify the fuel oil transfer system operates to 3.8.1.6 Verify the fuel oil transfer system operates to Administrative Variation -

[automatically] transfer fuel oil from storage automatically transfer fuel oil from 7 day Section 2.2.1.1 tank[s] to the day tank [and engine mounted storage tank to the skid mounted day tank.

tank].

3.8.1.7 Verify each DG starts from standby condition 3.8.1.7 Verify each DG starts from standby condition Administrative Variation -

and achieves: and achieves in d 10 seconds, voltage Section 2.2.1.1

a. In [10] seconds, voltage [3740] V and t 6800 V, and frequency t 58.8 Hz. Verify frequency 58.8] Hz and after DG fast start from standby conditions
b. Steady state voltage [3740] V and that the DG achieves steady state voltage

[4580] V, and frequency [58.8] Hz and t 6800 V and d 7260 V, and frequency

[61.2] Hz. t 59.8 Hz and d 60.1 Hz.

3.8.1.8 Verify [automatic [and] manual] transfer of AC 3.8.1.8 Verify automatic and manual transfer of each Administrative Variation -

power sources from the normal offsite circuit to 6.9 kV shutdown board power supply from Section 2.2.1.1 each alternate [required] offsite circuit. the normal offsite circuit to each alternate offsite circuit.

3.8.1.9 Verify each DG rejects a load greater than or 3.8.1.9 Verify each DG rejects a load greater than or No variation equal to its associated single largest post- equal to its associated single largest post-accident load, and: accident load, and:

a. Following load rejection, the frequency is a. Following load rejection, the frequency is

[63] Hz, d 66.75 Hz;

b. Within [3] seconds following load rejection, b. Within 3 seconds following load rejection, the voltage is [3740] V and [4580] V, the voltage is t 6555 V and d 7260 V; and and c. Within 4 seconds following load rejection,
c. Within [3] seconds following load rejection, the frequency is t 59.8 Hz and d 60.1 Hz.

the frequency is [58.8] Hz and [61.2]

Hz.

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3.8.1.10 Verify each DG does not trip and voltage is 3.8.1.10 Verify each DG operating at a power factor Administrative Variation -

maintained [5000] V during and following a t 0.8 and d 0.9 does not trip and voltage is Section 2.2.1.1 load rejection of [4500] kW and [5000] kW. maintained d 8880 V during and following a load rejection of t 3960 kW and d 4400 kW and t 2970 kVAR and d 3300 kVAR.

3.8.1.11 Verify on an actual or simulated loss of offsite 3.8.1.11 Verify on an actual or simulated loss of No variation power signal: offsite power signal:

a. De-energization of emergency buses, a. De-energization of emergency buses;
b. Load shedding from emergency buses, b. Load shedding from emergency buses;
c. DG auto-starts from standby condition and: c. DG auto-starts from standby condition and:
1. Energizes permanently connected loads in

[10] seconds, 1. energizes permanently connected loads

2. Energizes auto-connected shutdown loads in d 10 seconds, through [automatic load sequencer], 2. energizes auto-connected shutdown
3. Maintains steady state voltage [3740] V loads through automatic load sequencer, and [4580] V, 3. maintains steady state voltage
4. Maintains steady state frequency [58.8] t 6800 V and d 7260 V, Hz and [61.2] Hz, and 4. maintains steady state frequency
5. Supplies permanently connected [and auto- t 59.8 Hz and d 60.1 Hz, and connected] shutdown loads for 5 minutes. 5. supplies permanently connected and auto-connected shutdown loads for t 5 minutes.

3.8.1.12 Verify on an actual or simulated Engineered 3.8.1.12 Unit 1 - Verify on an actual or simulated Administrative Variation -

Safety Feature (ESF) actuation signal each DG Engineered Safety Feature (ESF) actuation Section 2.2.1.1 auto-starts from standby condition and: signal each Unit 1 DG auto-starts from

a. In [10] seconds after auto-start and standby condition and:

during tests, achieves voltage [3740] V a. In d 10 seconds after auto-start and and frequency [58.8] Hz, during tests, achieves voltage t 6800 V

b. Achieves steady state voltage [3740] V and frequency t 58.8 Hz; and [4580] V and frequency [58.8] Hz b. After DG fast start from standby and [61.2] Hz, conditions the DG achieves steady state
c. Operates for 5 minutes, voltage t 6800 V and d 7260 V, and
d. Permanently connected loads remain frequency t 59.8 Hz and d 60.1 Hz.

energized from the offsite power system, c. Operates for t 5 minutes; and CNL-19-084 E4-29 of 36

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e. Emergency loads are energized [or d. Permanently connected loads remain autoconnected through the automatic load energized from the offsite power system; sequencer] from the offsite power system. and
e. Emergency loads are energized from the offsite power system.

Unit 2 - Verify on an actual or simulated Engineered Safety Feature (ESF) actuation signal each Unit 2 DG auto-starts from standby condition and:

a. In d 10 seconds after auto-start and during tests, achieves voltage t 6800 V and frequency t 58.8 Hz;
b. After DG fast start from standby conditions the DG achieves steady state voltage t 6800 V and d 7260 V, and frequency t 59.8 Hz and d 60.1 Hz.
c. Operates for t 5 minutes;
d. Permanently connected loads remain energized from the offsite power system; and
e. Emergency loads are energized from the offsite power system.

3.8.1.13 Verify each DG's noncritical automatic trips are 3.8.1.13 Verify each DG's automatic trips are Administrative Variation -

bypassed on [actual or simulated loss of bypassed on automatic or emergency start Section 2.2.1.1 voltage signal on the emergency bus signal except:

concurrent with an actual or simulated ESF a. Engine overspeed; and actuation signal]. b. Generator differential current.

3.8.1.14 Verify each DG operates for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: 3.8.1.14 Verify each DG operating at a power factor Administrative Variation -

a. For [2] hours loaded [5250] kW and t 0.8 and d 0.9 operates for t 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: Section 2.2.1.1

[5500] kW and a. For t 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded t 4620 kW and

b. For the remaining hours of the test loaded d 4840 kW and t 3465 kVAR and d 3630

[4500] kW and [5000] kW. kVAR; and

b. For the remaining hours of the test loaded t 3960 kW and d 4400 kW and t 2970 kVAR and d 3300 kVAR.

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3.8.1.15 Verify each DG starts and achieves: 3.8.1.15 Verify each DG starts and achieves, in Administrative Variation -

a. In [10] seconds, voltage [3740] V and d 10 seconds, voltage t 6800 V, and Section 2.2.1.1 frequency [58.8] Hz and frequency t 58.8 Hz. Verify after DG fast
b. Steady state voltage [3740] V, and start from standby conditions that the DG

[4580] V and frequency [58.8] Hz and achieves steady state voltage t 6800 V and

[61.2] Hz. d 7260 V, and frequency t 59.8 Hz and d 60.1 Hz.

3.8.1.16 Verify each DG: 3.8.1.16 Verify each DG: No variation

a. Synchronizes with offsite power source a. Synchronizes with offsite power source while loaded with emergency loads upon a while loaded with emergency loads upon simulated restoration of offsite power, a simulated restoration of offsite power;
b. Transfers loads to offsite power source, and b. Transfers loads to offsite power source;
c. Returns to ready-to-load operation. and
c. Returns to ready-to-load operation.

3.8.1.17 Verify, with a DG operating in test mode and 3.8.1.17 Unit 1 - Verify, with each Unit 1 DG operating Administrative Variation -

connected to its bus, an actual or simulated in test mode and connected to its bus, an Section 2.2.1.1 ESF actuation signal overrides the test mode actual or simulated ESF actuation signal by: overrides the test mode by:

a. Returning DG to ready-to-load operation a. Returning DG to ready-to-load operation; and and
b. [Automatically energizing the emergency b. Automatically energizing the emergency load from offsite power]. load from offsite power.

Unit 2 - Verify, DG 2A-A and 2B-B operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:

a. Returning DG to ready-to-load operation; and
b. Automatically energizing the emergency load from offsite power.

3.8.1.18 Verify interval between each sequenced load 3.8.1.18 Verify the time delay setting for each Administrative Variation -

block is within +/- [10% of design interval] for sequenced load block is within limits for each Section 2.2.1.1 each emergency [and shutdown] load accident condition and non-accident sequencer. condition load sequence.

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3.8.1.19 Verify on an actual or simulated loss of offsite 3.8.1.19 Verify on an actual or simulated loss of No variation power signal in conjunction with an actual or offsite power signal in conjunction with an simulated ESF actuation signal: actual or simulated ESF actuation signal:

a. De-energization of emergency buses, a. De-energization of emergency buses;
b. Load shedding from emergency buses, and b. Load shedding from emergency buses;
c. DG auto-starts from standby condition and: c. DG auto-starts from standby condition and:
1. Energizes permanently connected loads in

[10] seconds, 1. energizes permanently connected loads

2. Energizes auto-connected emergency in d 10 seconds, loads through load sequencer, 2. energizes auto-connected emergency
3. Achieves steady state voltage [3740] V loads through load sequencer, and [4580] V, 3. achieves steady state voltage: t 6800 V
4. Achieves steady state frequency [58.8] and d 7260 V, Hz and [61.2] Hz, and 4. achieves steady state frequency
5. Supplies permanently connected [and t 59.8 Hz and d 60.1 Hz, and auto-connected] emergency loads for 5 5. supplies permanently connected and minutes. auto-connected emergency loads for t 5 minutes.

3.8.1.20 Verify when started simultaneously from 3.8.1.20 Verify during idle operation that any Administrative Variation -

standby condition, each DG achieves: automatic or emergency start signal disables Section 2.2.1.1

a. In [10] seconds, voltage [3740] V and the idle start circuitry and commands the frequency [58.8] Hz and engine to full speed.
b. Steady state voltage [3744] V and [4576]

V, and frequency [58.8] Hz and [61.2] Hz.

N/A N/A 3.8.1.21 Verify when started simultaneously from Administrative Variation -

standby condition, each DG achieves, in 10 Section 2.2.1.5 seconds, voltage 6800 V and frequency 58.8 Hz. Verify after DG fast start from standby conditions that the DG achieves steady state voltage 6800 V and 7260 V, and frequency 59.8 Hz and 60.1 Hz.

N/A N/A 3.8.1.22 Verify automatic transfer of each 6.9 kV Unit Administrative Variation -

Board 1B, 1C, 2B, and 2C power supply from Section 2.2.1.5 the normal power supply to the alternate power supply.

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3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3.1 Verify each fuel oil storage tank contains 3.8.3.1 Verify each 7 day fuel oil storage tank Administrative Variation -

[33,000] gal of fuel. contains t 56,754 gal of fuel. Section 2.2.1.1 3.8.3.2 Verify lubricating oil inventory is a [500] gal. 3.8.3.2 Verify lubricating oil inventory is t 287 gal Administrative Variation -

per engine. Section 2.2.1.1 3.8.3.4 Verify each DG air start receiver pressure is 3.8.3.4 Verify each DG air start receiver pressure is No variation

[225] psig. t 190 psig.

3.8.3.5 Check for and remove accumulated water from 3.8.3.5 Check for and remove accumulated water Administrative Variation -

each fuel oil storage tank. from each of the four interconnected tanks Section 2.2.1.1 which constitute the 7 day fuel oil storage tank.

N/A N/A 3.8.3.6 Perform a visual inspection for leaks in the Administrative Variation -

exposed fuel oil system piping while the DG Section 2.2.1.5 is running.

N/A N/A 3.8.3.7 For each of the four interconnected tanks Administrative Variation -

which constitute the 7 day fuel oil storage Section 2.2.1.5 tank:

a. Drain the fuel oil;
b. Remove the sediment; and
c. Clean the tank.

3.8.4 DC Sources - Operating 3.8.4 DC Sources - Operating 3.8.4.1 Verify battery terminal voltage is greater than 3.8.4.1 Verify vital battery terminal voltage is greater Administrative Variation -

or equal to the minimum established float than or equal to the minimum established Section 2.2.1.1 voltage. float voltage.

3.8.4.2 Verify DG battery terminal voltage is greater than or equal to the minimum established float voltage.

3.8.4.2 Verify each battery charger supplies [400] 3.8.4.5 Verify each vital battery charger supplies Administrative Variation -

amps at greater than or equal to the minimum 200 amps at greater than or equal to the Section 2.2.1.1 established float voltage for [8] hours. minimum established float voltage for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

OR OR Verify each battery charger can recharge the battery to the fully charged state within [24]

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hours while supplying the largest combined Verify each vital battery charger can demands of the various continuous steady recharge the battery to the fully charged state loads, after a battery discharge to the state within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> while supplying the bounding design basis event discharge state. largest combined demands of the various steady state loads, after a battery discharge to the bounding design basis event discharge state.

N/A N/A 3.8.4.3 Verify for the vital batteries that the alternate Administrative Variation -

feeder breakers to each required battery Section 2.2.1.5 charger are open.

N/A N/A 3.8.4.4 Verify correct breaker alignment and Administrative Variation -

indicated power availability for each DG Section 2.2.1.5 125 V DC distribution panel and associated battery charger.

(See (See 3.8.4.2) 3.8.4.6 Verify each DG battery charger can recharge Administrative Variation -

3.8.4.2) the battery to the fully charged state within Section 2.2.1.5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of the various steady state loads, after a battery discharge to the bounding design basis event discharge state.

3.8.4.3 Verify battery capacity is adequate to supply, 3.8.4.7 Verify battery capacity is adequate to supply, Administrative Variation -

and maintain in OPERABLE status, the and maintain in OPERABLE status, the Section 2.2.1.1 required emergency loads for the design duty required emergency loads and any cycle when subjected to a battery service test. connected nonsafety loads for the design duty cycle when subjected to a battery service test.

3.8.6 Battery Parameters 3.8.6 Battery Parameters 3.8.6.1 Verify each battery float current is [2] amps. 3.8.6.1 Verify each vital battery float current is 2 Administrative Variation -

amps. Section 2.2.1.1 3.8.6.2 Verify each DG battery float current is 1 amps.

3.8.6.2 Verify each battery pilot cell float voltage is 3.8.6.3 Verify each required vital battery and each Administrative Variation -

[2.07] V. DG battery pilot cell float voltage is 2.07 V. Section 2.2.1.1 3.8.6.3 Verify each battery connected cell electrolyte 3.8.6.4 Verify each required vital battery and each Administrative Variation -

level is greater than or equal to minimum DG battery connected cell electrolyte level is Section 2.2.1.1 established design limits.

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greater than or equal to minimum established design limits.

3.8.6.4 Verify each battery pilot cell temperature is 3.8.6.5 Verify each required vital battery and each Administrative Variation -

greater than or equal to minimum established DG battery pilot cell temperature is greater Section 2.2.1.1 design limits. than or equal to minimum established design limits.

3.8.6.5 Verify each battery connected cell float voltage 3.8.6.6 Verify each required vital battery and each Administrative Variation -

is [2.07] V. DG battery connected cell float voltage is Section 2.2.1.1 2.07 V.

3.8.6.6 Verify battery capacity is [80%] of the 3.8.6.7 Verify battery capacity is 80% of the Administrative Variation -

manufacturer's rating when subjected to a manufacturers rating when subjected to a Section 2.2.1.1 performance discharge test or a modified performance discharge test or a modified performance discharge test. performance discharge test.

3.8.7 Inverters - Operating 3.8.7 Inverters - Operating 3.8.7.1 Verify correct inverter voltage, [frequency], and 3.8.7.1 Verify correct inverter voltage, frequency, Administrative Variation -

alignment to required AC vital buses. and alignment to required AC vital bus. Section 2.2.1.1 3.8.8 Inverters - Shutdown 3.8.8 Inverters - Shutdown 3.8.8.1 Verify correct inverter voltage, [frequency,] and 3.8.8.1 Verify correct inverter voltage, frequency, Administrative Variation -

alignments to required AC vital buses. and alignments to required AC vital bus. Section 2.2.1.1 3.8.9 Distribution System - Operating 3.8.9 Distribution Systems - Operating 3.8.9.1 Verify correct breaker alignments and voltage 3.8.9.1 Verify correct breaker alignments and Administrative Variation -

to [required] AC, DC, and AC vital bus voltage to required AC, vital DC, and AC vital Section 2.2.1.1 electrical power distribution subsystems. bus electrical power distribution subsystems.

3.8.10 Distribution System - Shutdown 3.8.10 Distribution System - Shutdown 3.8.10.1 Verify correct breaker alignments and voltage 3.8.10.1 Verify correct breaker alignments and Administrative Variation -

to required AC, DC, and AC vital bus electrical voltage to required AC, vital DC, and AC vital Section 2.2.1.1 power distribution subsystems. bus electrical power distribution subsystems.

3.9.1 Boron Concentration 3.9.1 Boron Concentration 3.9.1.1 Verify boron concentration is within the limit 3.9.1.1 Verify boron concentration is within the limit No variation specified in the COLR. specified in COLR.

3.9.2 Unborated Water Source Isolation Valves 3.9.2 Unborated Water Source Isolation Valves 3.9.2.1 Verify each valve that isolates unborated water 3.9.2.1 Verify each valve that isolates unborated No variation sources is secured in the closed position. water sources is secured in the closed position.

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3.9.3 Nuclear Instrumentation 3.9.3 Nuclear Instrumentation 3.9.3.1 Perform CHANNEL CHECK. 3.9.3.1 Perform CHANNEL CHECK. No variation 3.9.3.2 Perform CHANNEL CALIBRATION. 3.9.3.2 Perform CHANNEL CALIBRATION. No variation 3.9.4 Containment Penetrations N/A N/A 3.9.4.1 Verify each required containment penetration is N/A N/A Administrative Variation -

in the required status. Section 2.2.1.2 3.9.4.2 Verify each required containment purge and N/A N/A Administrative Variation -

exhaust valve actuates to the isolation position Section 2.2.1.2 on an actual or simulated actuation signal.

3.9.5 Residual Heat Removal (RHR) and Coolant 3.9.5 Residual Heat Removal (RHR) and Circulation - High Water Level Coolant Circulation - High Water Level 3.9.5.1 Verify one RHR loop is in operation and 3.9.5.1 Verify one RHR loop is in operation and No variation circulating reactor coolant at a flow rate of circulating reactor coolant at a flow rate of

[2800] gpm. t 2500 gpm.

3.9.6 Residual Heat Removal (RHR) and Coolant 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level Circulation - Low Water Level 3.9.6.1 Verify one RHR loop is in operation and 3.9.6.1 Verify one RHR loop is in operation and No variation circulating reactor coolant at a flow rate of circulating reactor coolant at a flow rate of

[2800] gpm. t 2000 gpm.

3.9.6.2 Verify correct breaker alignment and indicated 3.9.6.2 Verify correct breaker alignment and No variation power available to the required RHR pump that indicated power available to the required is not in operation. RHR pump that is not in operation.

3.9.7 Refueling Cavity Water Level 3.9.7 Refueling Cavity Water Level 3.9.7.1 Verify refueling cavity water level is 23 ft 3.9.7.1 Verify refueling cavity water level is t 23 ft No variation above the top of reactor vessel flange. above the top of reactor vessel flange.

N/A N/A 3.9.9 Spent Fuel Pool Boron Concentration N/A N/A 3.9.9.1 Verify boron concentration in the spent fuel Administrative Variation -

pool is t 2300 ppm. Section 2.2.1.5 5.5. Programs and Manuals 5.7 Procedures, Programs, and Manuals 5.5.18 Surveillance Frequency Control Program 5.7.2.23 Surveillance Frequency Control Program Administrative Variation -

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