RC-18-0136, (Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683)

(Vcsns), Unit 1 - Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications (LAR-18-04683)

ML18346A595
Person / Time
Site:	Summer
Issue date:	12/12/2018
From:	Lippard G South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EPID L-2018-LLA-0226, LAR-18-04683, RC-18-0136
Download: ML18346A595 (31)

Text

A SCANA COMPANY George A. Lippard Vice President, Nuclear Operations 803.345.4810 December 12, 2018 RC-18-0136 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSE AMENDMENT REQUEST LAR-18-04683 REQUEST TO REMOVE THE EXPIRED ONE-TIME EXTENSION TO SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION AND TO REMOVE THE INDEX FROM TECHNICAL SPECIFICATIONS

References:

1. Letter from Michael Mahoney to George A. Lippard dated September 25, 2018 "VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - ISSUANCE OF EXIGENT AMENDMENT RE: ONE-TIME EXTENSION TO THE SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION (EPIDNO. L-2018-LLA-0226) [ML18260A027]

Pursuant to 10 CFR 50.90, South Carolina Electric & Gas Company (SCE&G), acting for itself and as an agent for South Carolina Public Service authority, hereby requests a license amendment to revise the VCSNS Unit 1 Technical Specifications (TS). The proposed change will revise TS 4.3.3.6, which describes the Surveillance Requirements for the Accident Monitoring Instrumentation. Amendment Number 211 (Reference 1) added a one-time extension of the frequency of the Core Exit Temperature Instrumentation channel calibrations, which has since expired. The proposed change will remove the expired one-time extension to the channel calibration interval.

Additionally, this proposed change will remove the Index from the Technical Specifications and place them under licensee control.

The Enclosure provides a description and assessment of each proposed change. Attachment 1 provides the existing TS pages marked to show the proposed changes. Attachment 2 provides revised (clean) TS pages. This request contains no new regulatory commitments and fulfills one regulatory commitment.

Approval of the proposed amendment is requested by September 30, 2019. SCE&G will implement the amendment within 90 days of the NRC approval date.

In accordance with 10 CFR 50.91, SCE&G is notifying the State of South Carolina of this request by transmitting a copy of this letter and enclosure to the designated State Official.

V. C. Summer Nuclear Station

• P. 0. Box 88

• Jenkinsville, South Carolina

• 29065

• F (803) 941-9776

• www.sceg.com

Document Control Desk RC-18-0136 CR-18-04683 Page 2 of 2 If there are any questions or if additional information is needed, please contact Michael S.

Moore at (803) 345-4752.

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

Executed on BAB/GAL/wk

Enclosure:

Description and Assessment of the Proposed Changes : Existing TS Pages Marked to Show the Proposed Changes : Revised (Clean) TS Pages c:

J. E. Addison NRC Resident Inspector K. M. Sutton S. E. Jenkins P. Led better NSRC RTS (CR-18-04683)

File (813.20)

PRSF (RC-18-0136)

W. K. Kissam J. B. Archie J. H. Hamilton G. J. Lindamood W. M. Cherry C. Haney S. A. Williams

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 1 of 7 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ENCLOSURE Description and Assessment of the Proposed Changes

Subject:

License Amendment Request LAR-18-04683 Request to Remove the Expired One-Time Extension to Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation and to Remove the Index from Technical Specifications

1.

SUMMARY

DESCRIPTION

2.

DETAILED DESCRIPTION 2.1 Description of the Proposed Change

3.

TECHNICAL EVALUATION

4.

REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration Determination Analysis 4.4 Conclusions

5.

ENVIRONMENTAL CONSIDERATION

6.

REFERENCES ATTACHMENTS:

1.

Technical Specification Page Markups

2.

Retyped Technical Specification Pages

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 2 of 7 1

SUMMARY

DESCRIPTION The proposed change will revise Technical Specification (TS) 4.3.3.6, which describes the Surveillance Requirements for the Accident Monitoring Instrumentation. VCSNS TS Amendment Number 211 (Reference 1) added a one-time extension of the frequency of the Core Exit Temperature Instrumentation channel calibrations, which has since expired. The proposed change will remove the expired one-time extension to the channel calibration interval.

Additionally, this proposed change will remove the Index from the Technical Specifications and place them under licensee control.

2 DETAILED DESCRIPTION The proposed changes to TS 4.3.3.6 described below are administrative non-technical changes only.

By application dated August 24, 2018, as supplemented by letters dated August 31, September 11, and September 19, 2018 (References 2 through 5, respectively) South Carolina Electric &

Gas Company (SCE&G) submitted a license amendment request (LAR) that proposed to revise the Virgil C. Summer Nuclear Station (VCSNS), Unit 1, Technical Specifications for Surveillance Requirement (SR) 4.3.3.6. The request was to allow a one-time extension of the frequency of the Core Exit Temperature Instrumentation channel calibrations from "every refueling outage" to "every 19 months". The U.S. Nuclear Regulatory Commission (NRC) approved this request and issued Amendment No. 211 on September 25, 2018 (Reference 1). The application contained one commitment which was to submit a LAR to remove the revision to TS 4.3.3.6 within 30 days of the completion of RF-24. The proposed change will fulfill this commitment and remove the expired one-time extension to the channel calibration interval.

The additional proposed change will remove the Index from the TS and place it under licensee control.

The Index for the TS is not being eliminated. Following approval of this license amendment request, responsibility for maintenance and issuance of updates to the TS Index will transfer from the NRC to VCSNS. The Index will no longer be included in the NRC issued TSs and as such will no longer be part of the TS (Appendix A to the Operating License). An Index for the TSs will be maintained under VCSNS (licensee) control. The Index will be issued by VCSNS in conjunction with the implementation of NRC-approved TS amendments.

2.1 Description of the Proposed Change VCSNS TS 4.3.3.6 describes the Surveillance Requirements of Accident Monitoring Instrumentation and currently reads as follows:

"Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performing a monthly CHANNEL CHECK and a CHANNEL CALIBRATION every refueling outage. An extension for the CHANNEL CALIBRATION interval for Item 12 in Table 3.3-10 to 19 months is permitted on a one-time basis. This extension expires prior to entering MODE 3, following the RF-24 refueling outage. The Reactor Building Radiation Level Instrumentation

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 3 of 7 CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for the range decades above 10R/hr and a single point calibration of the detector below 10R/hr with an installed or portable gamma source."

The expired one-time extension will be deleted for Item 12 of Table 3.3-10. The new Surveillance Requirement will read as follows:

"Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performing a monthly CHANNEL CHECK and a CHANNEL CALIBRATION every refueling outage. The Reactor Building Radiation Level Instrumentation CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for the range decades above 10R/hr and a single point calibration of the detector below 10R/hr with an installed or portable gamma source."

The Index for the TS is not being eliminated. Following approval of this license amendment request, responsibility for maintenance and issuance of updates to the TS Index will transfer from the NRC to VCSNS. The Index will no longer be included in the NRC issued TSs and as such will no longer be part of the TS (Appendix A to the Operating License). An Index for the TSs will be maintained under VCSNS (licensee) control. The Index will be issued by VCSNS in conjunction with the implementation of NRC-approved TS amendments.

3 TECHNICAL EVALUATION The proposed changes to TS 4.3.3.6 and removal of the Index from TS described below are administrative non-technical changes only. The Index does not meet the criteria specified in 10 CFR 50.36 requiring its inclusion within a plant's TS. The Index references where specific TS sections can be found throughout the TS, but does not contain technical information required by 10 CFR 50.36. Since the Index does not include information required by 10 CFR 50.36 to be reviewed by the NRC staff, inclusion of an Index within the TS is optional, and is not required by the regulation. Removal of the Index from the TS constitutes an administrative change and is therefore acceptable.

Additionally, the "Writer's Guide for Plant-Specific Improved Technical Specifications (ITS)"

(Reference 6) was reviewed for guidance. The Writer's Guide refers to the Table of Contents (TOC) as "Technical Specification Front Matter," which also includes the Title Page and List of Effective Pages. The Writer's Guide describes the TS content as starting with Chapter 1, "Use and Application" and does not include the TOC as part of the content of the TS.

Since the proposed changes to TS 4.3.3.6 and the removal of the Index from TS are administrative non-technical changes, a technical evaluation of the changes proposed in this LAR is not necessary.

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 4 of 7 4

REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria The proposed changes to TS 4.3.3.6 are administrative and non-technical in nature. Upon approval and implementation of the proposed changes, the VCSNS TSs will continue to comply with the applicable regulatory requirements and criteria discussed in the Regulatory Evaluation associated with SCE&G's August 24, 2018 LAR which was approved by the NRC as part of their September 25, 2018 SER. Therefore, additional discussion of the applicable regulatory requirements and criteria is not required.

The proposed removal of the Index from TS is also administrative and non-technical in nature.

10 CFR 50.36(a)(1) states the following:

"Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications."

Similar to the TS Bases, the Index does not meet the criteria specified in 10 CFR 50.36 for inclusion within a plant's TS.

VCSNS has evaluated these changes against the applicable regulatory requirements as described above. Based on this, there is reasonable assurance that the health and safety of the public, following approval of this change will remain unaffected.

4.2 Precedent By letter dated May 5, 2016 and supplemented by letter dated June 16, 2016 (References 7 and 8, respectively), Duke Energy submitted a license amendment request to remove superseded TS requirements. This amendment was issued by NRC letter dated March 8, 2017 (Reference 9).

By letter dated June 23, 2011, NextEra Energy submitted a license amendment request to remove the TOC from the TS and place it under licensee control (Reference 10). This amendment was issued by NRC letterdated October 11, 2011 (Reference 11).

4.3 No Significant Hazards Considerations Determination Analysis SCE&G has evaluated whether a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1)

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

Response: No.

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 5 of 7 This LAR proposes administrative non-technical changes only. These proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configurations of the facility. The proposed changes do not alter or prevent the ability of structures, systems and components (SSCs) to, perform their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits.

Therefore, it is concluded the proposed amendment does not significantly increase the probability or consequences of an accident previously evaluated.

2)

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

Response: No.

This LAR proposes administrative non-technical changes only. The proposed changes will not alter the design requirements of any Structure, System or Component (SSC) or its function during accident conditions. No new or different accidents result from the proposed changes. The changes do not involve a physical alteration of the plant or any changes in methods governing normal plant operation. The changes do not alter assumptions made in the safety analysis.

Therefore, it is concluded the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3)

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

Response: No.

This LAR proposes administrative non-technical changes only. The proposed changes do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation in a configuration outside the design basis. The proposed changes do not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.

Therefore, it is concluded the proposed amendment does not involve a significant reduction in the margin of safety.

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

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 6 of 7 4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5 ENVIRONMENTAL CONSIDERATION The proposed amendment is confined to changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

6 REFERENCES

1. Letter from Michael Mahoney to George A. Lippard dated September 25, 2018 "VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - ISSUANCE OF EXIGENT AMENDMENT RE: ONE-TIME EXTENSION TO THE SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION (EPID NO. L-2018-LLA-0226) [ML18260A027]

2. Letter from George A. Lippard to NRC Document Control Desk dated August 24, 2018.

"LICENSE AMENDMENT REQUEST LAR-18-03422, REQUEST FOR A ONE-TIME EXTENSION TO THE SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION" [ML18236A383]

3. Letter from George A. Lippard to NRC Document Control Desk dated August 31,2018.

"SUPPLEMENT TO LICENSE AMENDMENT REQUEST LAR-18-03422, REQUEST FOR A ONE-TIME EXTENSION TO THE SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION" [ML18243A392]

4. Letter from George A. Lippard to NRC Document Control Desk dated September 11, 2018. "LICENSE AMENDMENT REQUEST LAR-18-03422, REQUEST FOR A ONE-TIME EXTENSION TO THE SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION, RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION" [ML18254A406]

5. Letter from George A. Lippard to NRC Document Control Desk dated September 19, 2018. "SUPPLEMENT TO LICENSE AMENDMENT REQUEST LAR-18-03422, REQUEST FOR A ONE-TIME EXTENSION TO THE SURVEILLANCE FREQUENCY 4.3.3.6 OF THE CORE EXIT TEMPERATURE INSTRUMENTATION" [ML18262A088]

6. TSTF-GG-05-01 Revision 1, "Writer's Guide for Plant-Specific Improved Technical Specifications", Dated August 2010 [ML12046A089]

Document Control Desk Enclosure RC-18-0136 CR-18-04683 Page 7 of 7

7. Letter from Steven D. Capps to NRC Document Control Desk dated May 5, 2016 "Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station (MNS), Units 1 and 2 Docket Numbers 50-369 and 50-370 Renewed Facility Operating License Nos. NPF-9 and NPF-17 Removal of Superseded Technical Specification (TS) Requirements"

[ML16134A068]

8. Letter from Steven D. Capps to NRC Document Control Desk dated June 16, 2016 "Supplement to McGuire Nuclear Station, Units 1 and 2 License Amendment Request (LAR), for the Removal of Superseded Technical Specification (TS) Requirements, dated, May 5, 2016, TAC Nos. MF7682 and MF7683." [ML16180A179]

9. Letter from Michael Mahoney to Steven D. Capps dated March 8, 2017 "MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING CHANGE TO TECHNICAL SPECIFICATIONS (TS), REMOVAL OF SUPERSEDED TS REQUIREMENTS (CAC NOS. MF7682 AND MF7683) [ML17003A019]

10. Letter from Larry Meyer to NRC Document Control Desk dated June 23, 2011 "License Amendment Request 254 Removal of the Table of Contents from Technical Specifications" [ML111740873]

11. Letter from Terry A. Beltz to Larry Meyer dated October 11, 2011 "POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT RE: REQUEST TO REMOVE THE TABLE OF CONTENTS FROM THE TECHNICAL SPECIFICATIONS" (TAC NOS. ME6580 AND ME6581) [ML112640016]

Document Control Desk RC-18-0136 CR-18-04683 Page 1 of 20 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 ATTACHMENT 1 EXISTING TS PAGES MARKED TO SHOW THE PROPOSED CHANGES

INDEX 1.0 DEFINITIONS SBCTION PAGE l\\

ACTION 1-1 1.2 \\

ACTUATION LOGIC TEST 1-1 1.3

\\ANALOG CHANNEL OPERATIONAL TEST 1-1 1.4 A^IAL FLUX DIFFERENCE 1-1 1.5 CHSyNNEL CALIBRATION 1-1 1.6 CHANNEL CHECK 1-1 1.7 CONTAlVMENT INTEGRITY 1-2 1.8 CONTROE^ED LEAKAGE 1-2 1.9 CORE ALTERATION 1-2 1.9a CORE OPERARNG LIMITS REPORT 1-2 1.10 DOSE EQUIVALENT 1-131 1-2 1.11 E-AVERAGE DISINTEGRATION ENERGY 1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME 1-3 1.13 FREQUENCY NOTATION 1-3 1.14 GASEOUS RADWASTE TREATMENT SYSTEM 1-3 1.15 IDENTIFIED LEAKAGE \\.

1-3 1.16 MASTER RELAY TEST V

1-3 1.17 OFFSITE DOSE CALCULATIONV\\NUAL (ODCM) 1-4 1.18 OPERABLE - OPERABILITY

.V.

1-4 1.19 OPERATIONAL MODE - MODE V

1-4 1.20 PHYSICS TESTS

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1-4 1.21 PRESSURE BOUNDARY LEAKAGE

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.V.

1-4 1.24 QUADRANT POWER TILT RATIO V

1-5 1.25 RATED THERMAL POWER 1-5 1.26 REACTOR TRIP SYSTEM RESPONSE TIME

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.V.

1-5 1.29 SLAVE RELAY TEST V

1-5 1.30 DELETE 1.31 SOURCE CHECK

.V.

1-5 1.32 STAGGERED TEST BASIS V

1-6 1.33 THERMAL POWER

.V....

1-6 1.34 TRIP ACTUATING DEVICE OPERATIONAL TEST V

1-6 1.35 UNIDENTIFIED LEAKAGE

\\ 1-6 1.36 VENTILATION EXHAUST TREATMENT SYSTEM

\\l-6 1.37 VENTING 1\\6 TABLE 1.1 OPERATIONAL MODES 1-\\

TABLE 1.2 FREQUENCY NOTATION 1-8 ^

SUMMER-UNIT 1 Amendment No. 35, 88, 104

INDEX vFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS PAGE 2.1 SAFEV LIMITS 2.1.1 REACTOR CORE 2.1.2 REALTOR COOLANT SYSTEM PRESSURE 2-1 2-1 2.2 LIMITING SAFETY SYS>

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0

\\APPLICABILITY 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BOKATION CONTROL ShutdWn Margin - Modes 1 and 2 3/4 1-1 Shutdown Margin - Modes 3, 4 and 5...

3/4 1-3 ModeratoMremperature Coefficient 3/4 1-4 Minimum Temperature for Criticality 3/4 1-6 3/4 1.2 BORATION SYSTEMS Flow Path - ShuSjown 3/4 1-7 Flow Path - Operating 3/4 1-8 Deleted X.

3/4 1-9 Deleted

^..

3/4 1-10 Borated Water Source -T^hutdown 3/4 1-11 Borated Water Sources - Operating 3/4 1-12 3/4 1.3 MOVABLE CONTROL ASSEMBLIES Group Height

.V 3/4 1-14 Position Indication Systems - Operating 3/4 1-17 Position Indication Systems - Shutdown 3/4 1-18 Rod Drop Time V.

3/4 1-19 Shutdown Rod Insertion Limit 3/4 1-20 Control Rod Insertion Limits

\\.

3/4 1-21 SUMMER-UNIT1 III Amendment 7^-134

INDEX W/1ITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTtoN PAGE 3/4.2 XPOWER DISTRIBUTION LIMITS 3/4.2.1 AXh^L FLUX DIFFERENCE 3/4 2-1 3/4.2.2 HEATKLUX HOT CHANNEL FACTOR 3/4 2-4 3/4.2.3 RCS FLOWRATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4 2-8 3/4.2.4 QUADRANT PO^ER TILT RATIO 3/4 2-12 3/4.2.5 DNB PARAMETERS^

3/4 2-15 3/4.3 INSTRUMENTATION

\\

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMWTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION

\\

Radiation Monitoring 3/4 3-41 Movable Incore Detectors 3/4 3-46 DELETED 3/4 3-47 Meteorological Instrumentation 3/4 3-50 Remote Shutdown Instrumentation 3/4 3-53 Accident Monitoring Instrumentation

^V.. 3/4 3-56 Explosive Gas Monitoring Instrumentation

.^/4 3-67 Loose-Part Detection Instrumentation 3/^^72 Power Distribution Monitoring System 3/4 S-Yfi SUMMER-UNIT 1 IV Amendment No. 79, 104, 122, 142

X INDEX ING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION X PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation 3/4 4-1 Hot Standb^X.

3/4 4-2 Hot Shutdown.^V.

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3/4 4-18 Operational Leakage iV.

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\\ 3/4 4-29 Pressurizer 3M 4-33 Overpressure Protection Systems 3/4^34 3/4.4.10 STRUCTURAL INTEGRITY 3/4 4-3^

SUMMER - UNIT 1 V

Amendment No. 179

INDEX EW1ITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5

\\ EMERGENCY CORE COOLING SYSTEMS (ECCS1 3/4.5.1

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INDEX IJMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION!

PAGE 3/4.6 CONLTAINMENT SYSTEMS 3/4.6.1 P^MARY CONTAINMENT Containment Integrity 3/4 6-1 ContainrS^nt Leakage 3/4 6-2 ContainmentAir Locks 3/4 6-4 Internal Pressure 3/4 6-6 Air Temperature.^.

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SUMMER-UNIT 1 VII Amendment No. 44-8r 170

V INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIONX PAGE 3/4.7 PLAl\\sYSTEMS 3/4.7.1 TuSeiNE CYCLE Safet^alves 3/4 7-1 Emergent Feedwater System 3/4 7-4 Condensate attorage Tank 3/4 7-6 Activity 3/4 7-7 Main Steam Line Isolation Valves 3/4 7-9 Feedwater Isolation \\^ves 3/4 7-9a 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION 3/4 7-10 3/4.7.3 COMPONENT COOLING VWVER SYSTEM 3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM..V 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK TV 3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (CREFS).... 3/4 7-14 3/4.7.7 SNUBBERS

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3/4 7-23 3/4.7.9 AREA TEMPERATURE MONITORING

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3/4 7-37 3/4.7.10 WATER LEVEL - SPENT FUEL POOL 3/4 7-39 3/4.7.11 DELETED TV 3/4 7-40 3/4.7.12 SPENT FUEL ASSEMBLY STORAGE

.TV 3/4 7-42 3/4.7.13 SPENT FUEL POOL BORON CONCENTRATION

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3/4 7-44 SUMMER-UNIT 1 VIII Amendment No. 23, 79, 160, 4SQr 183

SECTIONX PAGE 3/4.8 ELBCTR1CAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OperatingX 3/4 8-1 Shutdown 3/4 8-8 3/4.8.2 D C. SOURCES^

Operating

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3/4 8-9 Shutdown 3/4 8-12 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Operating X

3/4 8-13 Shutdown V.

3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES Containment Penetration Conductor O^/ercurrent Protective Devices 3/4 8-16 Circuit Protection Devices X

3/4 8-23 SUMMER-UNIT 1 IX Amendment No. 38, 63, 137

SECTION \\

PAGE 3/4.9 REFUBLING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/4 9-1 3/4.9.2 INSTRUMENTATION 3/4 9-2 3/4.9.3 DECAY 'E 3/4 9-3 3/4.9.4 DELETED.. V.

3/4 9-4 3/4.9.5 COMMUNICATES 3/4 9-5 3/4.9.6 MANIPULATOR CRANE 3/4 9-6 3/4.9.7 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level 3/4 9-7 Low Water Level

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3/4 9-8 3/4.9.8 DELETED V.

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3/4.10.1 SHUTDOWN MARGIN

.V.

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWEROSTRIBUTION LIMITS 3/4 10-2 3/4.10.3 PHYSICS TESTS V

3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS

!V.

3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN,...\\

3/4 10-5 SUMMER - UNIT 1 X

Amendment No. 49, 160, 183

INDEX LLXFLNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECIlOrX PAGE 3/4.11 RADIATIVE EFFLUENTS 3/4.11.1 LIQUTO EFFLUENTS Liquid HSWup Tanks 3/4 11-1 Settling Po^d 3/4 11-2 3/4.11.2 GASEOUS EFFI^ENTS Explosive Gas Mixtur^

3/4 11-4 Gas Storage Tanks.....V.

3/4 11-5

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I SUMMER-UNIT 1 XI Amendment No. 104

INDEX SUMMER - UNIT 1 XII

INDEX BAS SECTION \\

PAGE 3/4.4.5 sSEAM GENERATOR TUBE INTEGRITY B 3/4 4-3 3/4.4.6 REALTOR COOLANT SYSTEM LEAKAGE B 3/4 4-4 3/4.4.7 CHEMISTRY B 3/4 4-5 3/4.4.8 SPECIFIcWriVITY B 3/4 4-6 3/4.4.9 PRESSURE/TEMPERATURE LIMITS B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-15 3/4.5 EMERGENCY CORE COOIJNG SYSTEM (ECCS) 3/4.5.1 ACCUMULATORS B 3/4 5-1 3/4.5.2

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AND ECCS SUBSYSTEMS

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B 3/4.5-1 3/4.5.3

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3/4.5.4 FUELING WATER STORAGE TANKW/ST)

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS

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3/4.6.1 ACCUMULATORS

.V.

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS^.

B 3/4 6-3 3/4.6.3 PARTICULATE IODINE CLEANUP SYSTEM B 3/4 6-4 3/4.6.4 CONTAINMENT ISOLATION VALVES V

B 3/4 6-5 3/4.6.5 COMBUSTIBLE GAS CONTROL

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B 3/4 6-5 SUMMER-UNIT 1 XIII Amendment No. 44, 143, 179

INDEX BASES SECTIONX PAGE 3/4.7 PLAITkSYSTEMS 3/4.7.1 TURBINE CYCLE B 3/4 7-1 3/4.7.2 STEAMsGENERATOR PRESSURE/TEMPERATURE LIMITATION B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM B 3/4 7-3 3/4.7.4 SERVICE SYSTEM B 3/4 7-3 3/4.7.5 ULTIMATE HE/vlSSINK B 3/4 7-3 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (CREFS).... B 3/4 7-4 3/4.7.7 SNUBBERS Ay B 3/4 7-4f 3/4.7.8 SEALED SOURCE CONTAMINATION B 3/4 7-6 3/4.7.9 AREA TEMPERATURE MONNORING B 3/4 7-6 3/4.7.10 WATER LEVEL - SPENT FUEL P^OL B 3/4 7-6 3/4.7.11 DELETED Ay.

B 3/4 7-6 3/4.7.12 SPENT FUEL ASSEMBLY STORAGE Ay B 3/4 7-7 3/4.7.13 SPENT FUEL POOL BORON CONCENTIWION B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS

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3/4.8.1,

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3/4.8.2 A.C. SOURCES, D.C. SOURCES AND ONSITE POWERS, b 3/4 AND DISTRIBUTION SYSTEMS

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3/4.8.3

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3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES Ac. B 3/4 8-4 178, 180, 183

INDEX BASfcS SECTION X PAGE 3/4.9 REFUEklNG OPERATIONS 3/4.9.1 BORONSX)NCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 3/4.9.3 DECAY TIME.X^

B 3/4 9-1 3/4.9.4 DELETED

^V.

B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE.N.

B 3/4 9-2 3/4.9.7 RESIDUAL HEAT REMOVALXD COOLANT CIRCULATION B 3/4 9-2 3/4.9.8 DELETED X^.

B 3/4 9-2 3/4.9.9 WATER LEVEL - REACTOR VESSELX^.

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS X,

3/4.10.1 SHUTDOWN MARGIN X^

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PHYSICS TESTS X,

B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN X.---

B 3/4 10-1 SUMMER-UNIT 1 XV Amendment No. A9, 160, 183

SECTION^

PAGE 5.1 SITE \\

5.1.1 EXCLUSION AREA 5-1 5.1.2 LOW POPULATION ZONE 5-1 5.1.3 SITE BOUNDARY FOR GASEOUS EFFLUENTS 5-1 5.1.4 SITE BOUNDARYSFOR LIQUID EFFLUENTS 5-1 5.2 REACTOR BUILDING \\

5.2.1 CONFIGURATION

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5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE 5-1 5.3 REACTOR CORE

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5.3.1 FUEL ASSEMBLIES V

5-6 5.3.2 CONTROL ROD ASSEMBLIES V.

5-6 5.4 REACTOR COOLANT SYSTEM

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5.4.1 DESIGN PRESSURE AND TEMPERATURE

.V.

5-6 5.4.2 VOLUME 5-6 5.5 METROLOGICAL TOWER LOCATION V

5-6 5.6 FUEL STORAGE

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5.6.1 CRITICALITY

\\ 5-7 5.6.2 DRAINAGE

^-7 5.6.3 CAPACITY bfta) 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-7(a)

SUMMER-UNIT 1 XVII Amendment No. 49

V INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6.2.1 OFFSITE 6-1 6.2.2 UNITSTAKF 6-1 6.2.3 NOT USED 6-3 6.2.4 SHIFT TECHNICAL ADVISOR 6-3 6.3 UNIT STAFF QUALIFICATIONS 6-3 6.4 TRAINING

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6-3 6.5 DELETED

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6.6 NOT USED

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6.7 SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES AND PROGRAMS

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6-11 6.9 REPORTING REQUIREMENTS

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6.9.1 ROUTINE REPORTS

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Startup Report

.V.

6-13 Annual Report 6-13 Annual Radiological Environmental Operating ReportX.

6-14 Annual Radioactive Effluent Release Report V

6-14 Not Used V

6-16 Core Operating Limits Report

.V 6-16 6.9.2 SPECIAL REPORTS V..

6-17 6.10 DELETED V. 6-17 6.11 RADIATION PROTECTION PROGRAM

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6-17 6.12 HIGH RADIATION AREA 6^7 6.13 PROCESS CONTROL PROGRAM 6-18\\

6.14 OFFSITE DOSE CALCULATION MANUAL 6-19 SUMMER-UNIT 1 XVIII Amendment No. 104, 151, 185, 188

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown on Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 30 days or submit a Special Report within the following 14 days from the time the action is required. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to operable status.

b.1 With the number of OPERABLE Reactor Building radiation monitoring channels less than the Minimum Channels Operable requirement of Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

i)

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

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

b.2 Deleted b.3 With the number of OPERABLE accident monitoring channels less than the Minimum Channels Operable requirement of Table 3.3-10, either restore the inoperable channels to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 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 next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS Remove 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performing a monthly CHANNEL CHECK and a CHANNEL CALIBRATION every refueling outage. An extension for tho CHANNEL CALIBRATION interval for Item 12 in Tablo 3.3 10 to 19 months is permitted on a one-timo basi3. This extension expires prior to entering MODE 3, following tho RF 24 rofuoling outage. The Reactor Building Radiation Level Instrumentation CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for the range decades above 10R/hr and a single point calibration of the detector below 10R/hr with an installed or portable gamma source.

SUMMER-UNIT 1 3/4 3-56 Amendment No. 118,170, 24+

Document Control Desk RC-18-0136 CR-18-04683 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 ATTACHMENT 2 REVISED (CLEAN) TS PAGES Replace the following pages of the Technical Specifications with the attached revised pages.

The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Entirety of Index 3/4 3-56 Insert Pages Not Applicable 3/4 3-56

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown on Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 30 days or submit a Special Report within the following 14 days from the time the action is required. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to operable status.

b.1 With the number of OPERABLE Reactor Building radiation monitoring channels less than the Minimum Channels Operable requirement of Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

i)

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

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

b.2 Deleted b.3 With the number of OPERABLE accident monitoring channels less than the Minimum Channels Operable requirement of Table 3.3-10, either restore the inoperable channels to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 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 next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performing a monthly CHANNEL CHECK and a CHANNEL CALIBRATION every refueling outage. The Reactor Building Radiation Level Instrumentation CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for the range decades above 10R/hr and a single point calibration of the detector below 10R/hr with an installed or portable gamma source.

SUMMER - UNIT 1 3/4 3-56 Amendment No. 118, 170, 211