ML25338A316

Response to Request for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-596, Expand the Applicability

ML25338A316
Person / Time
Site:	Grand Gulf, Arkansas Nuclear, River Bend, Waterford
Issue date:	12/04/2025
From:	Couture P Entergy Operations
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
CNRO2025-01001
Download: ML25338A316 (0)

Text

Phil Couture Senior Manager Fleet Regulatory Assurance - Licensing 601-368-5102 Entergy Operations, Inc. 1340 Echelon Parkway, Jackson, MS 39213 CNRO2025-01001 10 CFR 50.90 December 04, 2025 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Response to Request for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-596, "Expand the Applicability of the Surveillance Frequency Control Program (SFCP)"

Arkansas Nuclear One, Unit 1 Arkansas Nuclear One, Unit 2 NRC Docket No. 50-313 NRC Docket No. 50-368 Renewed Facility Operating Renewed Facility Operating License No. DPR-51 License No. NPF-6 Grand Gulf Nuclear Station, Unit 1 River Bend Station, Unit 1 NRC Docket No. 50-416 NRC Docket No. 50-458 Renewed Facility Operating Renewed Facility Operating License No. NPF-29 License No. NPF-47 Waterford Steam Electric Station, Unit 3 NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38 By letter dated April 29, 2025 (Reference 1), Entergy Operations, Inc. (Entergy), requested Nuclear Regulatory Commission (NRC) approval to adopt Technical Specification Task Force (TSTF) Traveler TSTF-596, "Expand the Applicability of the Surveillance Frequency Control Program (SFCP)" for Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2), Grand Gulf Nuclear Station, Unit 1 (GGNS), River Bend Station, Unit 1 (RBS), and Waterford Steam Electric Station, Unit 3 (WF3). Entergy received a Request for Additional Information (RAI) on November 18, 2025 (Reference 2) in regard to the Reference 1 application.

The Enclosure provides Entergy's response to the RAI.

Attachments 1 through 3 of the enclosure provides updated TS page markups in response to the RAI associated with ANO-1, ANO-2, and WF3, respectively.

Attachments 4 through 6 of the enclosure provides updated retyped (clean) TS pages in response to the RAI associated with ANO-1, ANO-2, and WF3, respectively.

CNRO2025-01001 Page 2 of 3 No changes to the Reference 1 TS Bases page markups are required. There is no change to the Reference 1 requested approval date of the amendment or implementation period. Entergy requests the associated TS pages of the original Reference 1 application be replaced with the pages included in the Enclosure attachments.

Entergy has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The changes do not affect the bases for concluding that the proposed amendment does not involve a significant hazards consideration. In addition, Entergy has concluded that the information in this response does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

This letter contains no new regulatory commitments.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), a copy of this license amendment request, with enclosure, is being provided to the designated State Officials.

Should you have any questions or require additional information, please contact me at 601-368-5102.

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

Executed on December 04, 2025.

Respectfully, Phil Couture PC/dbb/chm

Enclosure:

Response to Request for Additional Information Attachments to

Enclosure:

1.

Technical Specification Page Markup - ANO-1

2.

Technical Specification Page Markup - ANO-2

3.

Technical Specification Pages Markup - WF3

4.

Technical Specification Page Retyped - ANO-1

5.

Technical Specification Page Retyped - ANO-2

6.

Technical Specification Pages Retyped - WF3 Philip Couture Digitally signed by Philip Couture Date: 2025.12.04 13:26:05 -06'00'

CNRO2025-01001 Page 3 of 3

References:

1.

Entergy letter to NRC, "Application to Revise Technical Specifications to Adopt TSTF-596, "Expand the Applicability of the Surveillance Frequency Control Program (SFCP)," ML25119A223, April 29, 2025.

2.

NRC email to Entergy, "Entergy Fleet - Request for Additional Information - TSTF-596 LAR," ML25322A305, November 18, 2025.

cc:

NRC Region IV Regional Administrator NRC Senior Resident Inspector - ANO-1, and ANO-2 NRC Senior Resident Inspector - GGNS NRC Senior Resident Inspector - RBS NRC Senior Resident Inspector - WF3 NRC Fleet Project Manager Designated State Official - Arkansas Department of Health Designated State Official - Mississippi State Department of Health Designated State Official - Louisiana Department of Environmental Quality

Enclosure CNRO2025-01001 Response to Request for Additional Information

CNRO2025-01001 Enclosure Page 1 of 4 TABLE OF CONTENTS

1.0 DESCRIPTION

................................................................................................................... 2

2.0 BACKGROUND

................................................................................................................. 2 3.0 REGULATORY BASIS....................................................................................................... 2 4.0 RAI-1.................................................................................................................................. 3 4.1 RAI-1 Response............................................................................................................ 3 5.0 RAI-2.................................................................................................................................. 3 5.1 RAI-2 Response............................................................................................................ 3 6.0 RAI-3.................................................................................................................................. 4 6.1 RAI-3 Response............................................................................................................ 4

7.0 REFERENCES

................................................................................................................... 4 8.0 ATTACHMENTS................................................................................................................ 4

CNRO2025-01001 Enclosure Page 2 of 4 Response to Request for Additional Information

1.0 DESCRIPTION

By letter dated April 29, 2025 (Reference 1), Entergy Operations, Inc. (Entergy), requested Nuclear Regulatory Commission (NRC) approval to adopt Technical Specification Task Force (TSTF) Traveler TSTF-596, "Expand the Applicability of the Surveillance Frequency Control Program (SFCP)" for Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2), Grand Gulf Nuclear Station, Unit 1 (GGNS), River Bend Station, Unit 1 (RBS), and Waterford Steam Electric Station, Unit 3 (WF3). Entergy received a Request for Additional Information (RAI) on November 18, 2025 (Reference 2) in regard to the Reference 1 application.

The following is the RAI received from the NRC in Reference 2. Entergy's responses are provided after each question.

2.0 BACKGROUND

In letter dated April 24 [29], 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25119A223), Entergy Operations, Inc. (Entergy) requested adoption of TSTF-596, "Expand the Applicability of the Surveillance Frequency Control Program (SFCP)" which is an approved change to the Standard Technical Specifications (STS), into the Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2), Grand Gulf Nuclear Station, Unit 1, River Bend Station, Unit 1, and Waterford Steam Electric Station, Unit 3, Technical Specifications (TSs). TSTF-596 expands the applicability of the SFCP to include other periodic testing frequencies in TSs The NRC staff requires additional from the licensee to complete their review of the proposed changes. This request contains three RAIs.

3.0 REGULATORY BASIS The regulation at Title 10 of the Code of Federal Regulations (CFR), Section 50.36(c)(3) requires that TSs include Surveillance Requirements (SRs). Per 10 CFR 50.36(c)(3), SRs "are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."

The regulation at 10 CFR 50.36(c)(5) requires administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.

The Commissions "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (58 FR 39132, dated July 22, 1993) explained that "[e]ach [limiting condition for operation] LCO [limiting condition for operation], Action, and Surveillance Requirement should have supporting Bases." In addition, the Bases in part, for each SR should address the following question, "[w]hy is this surveillance necessary at the specified frequency to assure that the system or component function is maintained, that facility operation will be within the Safety Limits, and that the LCO will be met?"

CNRO2025-01001 Enclosure Page 3 of 4 4.0

RAI-1

For ANO-1, the LAR does not include "periodic" assessment for program 5.5.5.d "Control Room Envelope Habitability Program" (page 41). However, the TSTF-596 Traveler has "periodic assessment of the CRE boundary" under the Babcock & Wilcox STS program 5.5.17.d "Control Room Envelope Habitability Program" (page 179). ANO-1 is a Babcock & Wilcox design.

The NRC staff request the licensee to provide justification for not adopting periodic assessments and supporting bases to assure operation in a safe manner.

4.1 RAI-1 Response The "periodic" term included in the respective TS section of TSTF-596 is appropriate.

Therefore, the "periodic" term has been added to ANO-1 TS 5.5.5.d. Please see Attachments 1 and 4 of this enclosure for updated TS Markups and Retyped pages.

5.0

RAI-2

For Waterford Unit 3, the LAR proposes to add the text "lift settings > 2411 psia and

< 2559 psia" to the following surveillance requirements (SRs):

SRs 4.4.2.1 and 4.4.2.2 (page 115 and 116)

These SRs lift settings are different from the related LCOs (3.4.2.1/3.4.2.2) lift settings of "2500 psia +/- 3%" (>2425, <2575).

The NRC staff have reviewed the LCOs and Bases document. The NRC staff request the licensee to provide a justification for the proposed SR lift settings and any supporting bases to assure the LCOs will be met.

5.1 RAI-2 Response The Pressurizer safety valve lift setting pressure values shown in the original Reference 1 letter were equivalent to "psig" values instead of "psia" values. Because the subject Limiting Condition for Operation (LCO) lift setting pressure value is given in "psia", it is appropriate for the lift settings in the SR to also be shown in "psia".

Therefore, the lift setting pressure values contained in WF3 TS SRs 4.4.2.1 and 4.4.2.2 are revised to state " 2425 psia and 2575" psia (equivalent to the LCO requirement of 2500 psia +/- 3%). Please see Attachments 3 and 6 of this enclosure for updated TS Markups and Retyped pages.

CNRO2025-01001 Enclosure Page 4 of 4 6.0

RAI-3

For ANO-2, the LAR does not include "periodic" assessment for program 6.5.12.d "Control Room Envelope Habitability Program" (page 62). However, the TSTF-596 Traveler has "periodic assessment of the CRE boundary" under the Combustion Engineering (CE) STS program 5.5.17.d "Control Room Envelope Habitability Program" (page 179).

The NRC staff request the licensee to provide justification for not adopting periodic assessments and supporting bases to assure operation in a safe manner.

6.1 RAI-3 Response The "periodic" term included in the respective TS section of TSTF-596 is appropriate.

Therefore, the "periodic" term has been added to ANO-2 TS 6.5.12.d. Please see Attachments 2 and 5 of this enclosure for updated TS Markups and Retyped pages.

7.0 REFERENCES

1.

Entergy letter to NRC, "Application to Revise Technical Specifications to Adopt TSTF-596, "Expand the Applicability of the Surveillance Frequency Control Program (SFCP),"

ML25119A223, April 29, 2025.

2.

NRC email to Entergy, "Entergy Fleet - Request for Additional Information - TSTF-596 LAR," ML25322A305, November 18, 2025.

8.0 ATTACHMENTS

1.

Technical Specification Page Markup - ANO-1

2.

Technical Specification Page Markup - ANO-2

3.

Technical Specification Pages Markup - WF3

4.

Technical Specification Page Retyped - ANO-1

5.

Technical Specification Page Retyped - ANO-2

6.

Technical Specification Pages Retyped - WF3

Enclosure, Attachment 1 CNRO2025-01001 Technical Specification Page Markup - ANO-1 (1 TS Page Follows)

Programs and Manuals 5.5 ANO-1 5.0-9 Amendment No. 215,239,264, 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.5 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE at the periodic Frequencies in accordance with the Surveillance Frequency Control Program and in accordance with the testing methods and at the event-driven fFrequencies 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 required by the VFTP, at a Frequency in accordance with the Surveillance Frequency Control Program. The results shall be trended and used as part of the periodic CRE boundary assessment specified in TS 5.5.5.c.

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.

Enclosure, Attachment 2 CNRO2025-01001 Technical Specification Page Markup - ANO-2 (1 TS Page Follows)

ARKANSAS - UNIT 2 6-16 Amendment No. 255,288,293,315, ADMINISTRATIVE CONTROLS 6.5.12 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem Total Effective Dose Equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE at the periodic Frequencies in accordance with the Surveillance Frequency Control Program and in accordance with the testing methods and at the event-driven fFrequencies 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 required by the VFTP, at a Frequency in accordance with the Surveillance Frequency Control Program. The results shall be trended and used as part of the periodic 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 Specification 4.0.2 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.

Enclosure, Attachment 3 CNRO2025-01001 Technical Specification Pages Markup - WF3 (2 TS Pages Follow)

WATERFORD - UNIT 3 3/4 4-7 AMENDMENT NO. 111,189,250, REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 psia +/- 3%.*

APPLICABILITY:

MODE 4.

ACTION:

With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes (except cooldown in shutdown cooling) and place an OPERABLE shutdown cooling loop into operation.

SURVEILLANCE REQUIREMENTS 4.4.2.1 In accordance with the Surveillance Frequency Control Program, vVerify each required pressurizer code safety valve is OPERABLE with lift settings 2425 psia and 2575 psiain accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within +/- 1%.

• The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

WATERFORD - UNIT 3 3/4 4-8 AMENDMENT NO. 111,189,250, REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 psia +/- 3%.*

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.4.2.2 In accordance with the Surveillance Frequency Control Program, vVerify each required pressurizer code safety valve is OPERABLE with lift settings 2425 psia and 2575 psiain accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within +/- 1%.

• The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

Enclosure, Attachment 4 CNRO2025-01001 Technical Specification Page Retyped - ANO-1 (1 TS Page Follows)

Programs and Manuals 5.5 ANO-1 5.0-9 Amendment No. 215,239,264, 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.5 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE at the periodic Frequencies in accordance with the Surveillance Frequency Control Program and in accordance with the testing methods and at the event-driven 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 required by the VFTP, at a Frequency in accordance with the Surveillance Frequency Control Program. The results shall be trended and used as part of the periodic CRE boundary assessment specified in TS 5.5.5.c.

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.

Enclosure, Attachment 5 CNRO2025-01001 Technical Specification Page Retyped - ANO-2 (1 TS Page Follows)

ARKANSAS - UNIT 2 6-16 Amendment No. 255,288,293,315, ADMINISTRATIVE CONTROLS 6.5.12 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem Total Effective Dose Equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE at the periodic Frequencies in accordance with the Surveillance Frequency Control Program and in accordance with the testing methods and at the event-driven 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 required by the VFTP, at a Frequency in accordance with the Surveillance Frequency Control Program. The results shall be trended and used as part of the periodic 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 Specification 4.0.2 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.

Enclosure, Attachment 6 CNRO2025-01001 Technical Specification Pages Retyped - WF3 (2 TS Pages Follow)

WATERFORD - UNIT 3 3/4 4-7 AMENDMENT NO. 111,189,250, REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 psia +/- 3%.*

APPLICABILITY:

MODE 4.

ACTION:

With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes (except cooldown in shutdown cooling) and place an OPERABLE shutdown cooling loop into operation.

SURVEILLANCE REQUIREMENTS 4.4.2.1 In accordance with the Surveillance Frequency Control Program, verify each required pressurizer code safety valve is OPERABLE with lift settings 2425 psia and 2575 psia. Following testing, lift settings shall be within +/- 1%.

• The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

WATERFORD - UNIT 3 3/4 4-8 AMENDMENT NO. 111,189,250, REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 psia

+/- 3%.*

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.4.2.2 In accordance with the Surveillance Frequency Control Program, verify each required pressurizer code safety valve is OPERABLE with lift settings 2425 psia and 2575 psia. Following testing, lift settings shall be within +/- 1%.

• The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.