ML18333A194

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River Bend Station, Unit 1 - Removal of the Table of Contents from the Technical Specifications
ML18333A194
Person / Time
Site: River Bend Entergy icon.png
Issue date: 11/29/2018
From: Maguire W F
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-47918
Download: ML18333A194 (15)


Text

Entergy Operations, Inc. River Bend Station 5485 U.S. Highway 61N St. Francisville, LA 70775 Tel 225-381-4177 William F. Maguire Site Vice President River Bend Station RBG-47918

November 29, 2018

Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike

Rockville, MD 20852-2738

Subject:

Removal of the Table of Contents from the Technical Specifications River Bend Station, Unit 1

Docket No. 50-458 License No. NPF-47

Dear Sir or Madam:

Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests an amendment to Facility Operating License NFP-47 for River Bend Station (RBS) Unit 1. The proposed amendment revises the Technical Specifications (TS) to remove the table of contents (TOC) from the TS and place it under licensee control.

Enclosure 1 provides a description and evaluation of the proposed TS changes including the No Significant Hazards Consideration, environmental considerations, and the TS TOC pages. The TS TOC pages are being provided for information.

Approval of the proposed amendment is requested by November 29, 2019. Entergy will implement the amendment within 90 days of Commission approval.

The On-Site Safety Review Committee has reviewed the proposed license amendment request.

In accordance with 10 CFR 50.91 (b)(1), Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the designated State Official.

This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.

If you require additional information, please contact Mr. Tim Schenk at (225)-381-4177 or tschenk@entergy.com.

RBG-47918 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on November 29,2018. Sincerely, WFMltwf Enclosure 1: Evaluation of Proposed Change cc: U. S. Nuclear Regulatory Commission Attn: Emmanuel Sayoc 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd. Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission Attn: Ms. Lisa M. Regner, Project Manager 09-0-14 One White Flint North 11555 Rockville Pike Rockville, MD 20852 NRC Senior Resident Inspector Attn: Mr. Brian Parks 5485 U.S. Highway 61, Ste. NRC St. Francisville, LA 70775 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 Public Utility Commission of Texas Attn: PUC Filing Clerk 1701 N. Congress Avenue P. O. Box 13326 Austin, TX 78711 -3326 RBF1-18-0231 Enclosure 1 Evaluation of Proposed Change RBG-47918 Page 1 of 5 ENCLOSURE 1 Evaluation of Proposed Change 1.

SUMMARY

DESCRIPTION

2. DETAILED DESCRIPTION
3. TECHNICAL EVALUATION
4. REGULATORY EVALUATION

4.1 Applicable

Regulatory Requirements/Criteria

4.2 Precedent

4.3 No Significant Hazards Consideration

4.4 Conclusions

5. ENVIRONMENTAL CONSIDERATION
6. REFERENCES ATIACHMENT:
1. Technical Specification Table of Contents Pages (No changes. Provided for Information)

Enclosure 1 Evaluation of Proposed Change RBG-47918 Page 2 of 5 1.

SUMMARY

DESCRIPTION This evaluation supports the Entergy Operations, Inc. (Entergy) request to amend Facility Operating License NFP-47 for River Bend Station (RBS) Unit 1. The proposed changes would revise the Technical Specifications (TS) to remove the table of contents (TOC) from the TS and place it under licensee control. 2. DETAILED DESCRIPTION The proposed change would remove the TOC from the TS and place it under Entergy (licensee) control. Note that no TS pages will be issued as a result of this proposed change. The TOC for the TS is not being eliminated.

Following approval of this license amendment request (LAR), the responsibility for maintenance and issuance of updates to the TS TOC will transfer from the NRC to Entergy. The TOC will no longer be included in the TS and as such will no longer be part of the TS (Appendix A to the Operating License).

3. TECHNICAL EVALUATION The TOC does not meet the criteria specified in 10 CFR 50.36 requiring its inclusion within a plant's TS. 10 CFR 50.36(b) states: Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or § 50.22 will include technical specifications.

The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34. The result of the Entergy review of 10 CFR 50.36 indicates that the TS TOC was not listed in the regulation as one of the categories listed in 10 CFR 50.36(c).

10 CFR 50.36(a) indicates that a license application may provide other information associated with the TS, and gives an example of this information, i.e., the TS Bases, but also clearly indicates that the Bases are not a part of the TS. 10 CFR 50.36(a)(l) states: Each applicant for a license ... 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.

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

1) was reviewed for guidance.

The writer's guide refers to the 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. A TOC for the TS will be maintained under Entergy control. The TOC will be issued by Entergy in conjunction with the implementation of NRC-approved T8 amendments.

Enclosure 1 Evaluation of Proposed Change RBG-47918 Page 3 of 5 4. REGULATORY EVALUATION

4.1 Applicable

Regulatory Requirements/Criteria 10 CFR 50.36(a) states: Each applicant for a license ... shall include in his application proposed technical specification 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 specification.

Similar to the TS Bases, the TOe does not meet the criteria specified in 10 CFR 50.36 for inclusion within a plant's TS. Entergy has evaluated this change 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

  • Calvert Cliffs Nuclear Power Plant License Amendment Nos. 293 and 269 were issued by the NRC on September 21,2009 (Reference 2).
  • Monticello Nuclear Generating Plant, License Amendment No. 152, was issued by the NRC on November 8,2007 (Reference 3). 4.3 No Significant Hazards Consideration Entergy has evaluated the proposed amendment in accordance with 10 CFR 50.91 against the standards in 10 CFR 50.92 and has determined that the operation of the facility in accordance with the proposed amendment presents no significant hazards consideration.

Entergy's evaluation against each of the criteria in 10 CFR 50.92 is discussed below. 1. Does the proposed amendment involve a significant increase in the probability or conseguences of an accident previously evaluated?

Response:

No. The proposed amendment is administrative and affects control of a document, the TOC, listing the specifications in the plant TS. Transferring control from the NRC to Entergy does not affect the operation, physical configuration, 'or function of plant equipment or systems. The proposed amendment does not impact the initiators or assumptions of analyzed events; nor does it impact the mitigation of accidents or transient events. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Enclosure 1 Evaluation of Proposed Change RBG-47918 Page 4 of 5 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response:

No. The proposed change is administrative and does not alter the plant configuration, require installation of new equipment, alter assumptions about previously analyzed accidents, or impact the operation or function of plant equipment or systems. Therefore, the proposed change 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. The proposed amendment is administrative.

The TOC is not required by regulation to be in the TS. Removal does not impact any safety assumptions or have the potential to reduce a margin of safety. The proposed amendment involves a transfer of control of the TOC from the NRC to Entergy. No change in the technical content of the TS is involved.

Consequently, transfer from the NRC to Entergy has no impact on the margin of safety. Therefore the proposed amendment does not involve a significant reduction in a margin of safety. Based on the above, Entergy has determined that operation of the facility in accordance with the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), in that it does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. 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 operating in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulation, and (3) the issuances of the amendment will not be inimical to the common defense and security or to the health and safety of the public. The On-Site Safety Review Committee has reviewed this amendment and concurs with this conclusion.

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)(1 0). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

Enclosure 1 Evaluation of Proposed Change RBG-47918 Page 5 of 5 6. REFERENCES

1. Technical Specifications Task Force, TSTF-GG-05-01, "Writer's Guide for Plant-Specific Improved Technical Specifications," dated June 2005. 2. NRC letter to Calvert Cliffs Nuclear Power Plant Inc, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 -"Amendment Re: Request to Remove the Table of Contents from the Technical Specifications, (TAC Nos. ME1336 and ME1337)," dated September 21,2009. (ML092120042)
3. NRC letter to Nuclear Management Company, LLC, Monticello Nuclear Generating Plant -"Issuance of Amendment Re: Removal of the Table of Contents Out of the Technical Specifications, (TAC No. MD6027)," dated November 8,2007. (ML072960159)

ATTACHMENT 1 Technical Specification Table of Contents Pages (No changes. Provided for Information) 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 B 2.0 B 2.1.1 B 2.1.2 30 3.0 B 3.0 B 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.1.7 3.1.8 B 3.1 B 3.1.1 B 3.1.2 B 3.1.3 B 3.1.4 B 3.1.5 B 3.1.6 B 3.1.7 B 3.1.8 3.2 3.2.1 3.2.2 3.2.3

3.2.4 TECHNICAL

SPECIFICATIONS TABLE OF CONTENTS USE AND APPLICATION Definitions

.........................................................................................

... 1.0-1 Logical Connectors

.............................................................................. 1.0-8 Completion Times ................................................................................ 1.0-11 Frequency

....................

................

....................................

.................... 1.0-24 SAFETY LIMITS (SLs) SLs ............

......................

................................................

.................... 2.0-1 SL Violations

.........................

........................................

............

........... 2.0-1 SAFETY LIMITS (SLs) Reactor Core SLs ................................................................................ B 2.0-1 Reactor Coolant System (RCS) Pressure SL .......................

............... B 20-6 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITy

........... 30-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

......................... 30-4 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

........... B 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITy

.......................... B 3.0-10 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM) ........................................................

..... 3.1-1 Reactivity Anomalies

.................................

...................................

....... 3.1-4 Control Rod OPERABILITY

...........................................

...................... 3.1-6 Control Rod Scram Times .............................................

...................... 3.1-11 Control Rod Scram Accumulators

....................................................... 3.1-15 Control Rod Pattern .......................

..................................................... 3.1-18 Standby Liquid Control (SLC) System ............................

..................... 3.1-20 Scram Discharge Volume (SDV) Vent and Drain Valves .................... 3.1-24 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM) ................

............................................. B 3.1-1 Reactivity Anomalies

........................................................................... B 3.1-7 Control Rod OPERABILITy

..................

....................................

........... B 3.1-12 Control Rod Scram Times ......................

......................

....................... B 3.1-2 1 Control Rod Scram Accumulators

................................

....................... B 3.1-27 Control Rod Pattern ..............................

............................................... B 3.1-32 Standby Liquid Control (SLC) System .............

.................................... B 3.1-37 Scram Discharge Volume (SDV) Vent and Drain Valves .................... B 3.1-45 POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ... 3.2-1 MINIMUM CRITICAL POWER RATIO (MCPR) ..........

........................ 3.2-2 LINEAR HEAT GENERATION RATE (LHGR) ..........

......................

.... 3.2-3 FRACTION OF CORE BOILING BOUNDARY (FCBB) ....................... 3.2-4 (continued)

RIVER BEND Revision No. 6-5 83.2 83.2.1 8 3.2.2 8 3.2.3 83.2.4 3.3 3.3.1.1 3.3.1.2 3.3.1.3 3.3.2.1 3.3.3.1 3.3.3.2 3.3.4.1 3.3.4.2 3.3.5.1 3.3.5.2 3.3.6.1 3.3.6.2 3.3.6.3 3.3.6.4 3.3.7.1 3.3.8.1 3.3.8.2 8 3.3 83.3.1.1 B 3.3.1.2 B 3.3.1.3 B 3.3.2.1 B 3.3.3.1 B 3.3.3.2 B 3.3.4.1 B 3.3.4.2 B 3.3.5.1 B 3.3.5.2 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ... 8 3.2-1 MINIMUM CRITICAL POWER RATIO (MCPR) ..................................

83.2-5 LINEAR HEAT GENERATION RATE (LHGR) ....................................

83.2-9 FRACTION OF CORE BOILING BOUNDARY (FCBB) .......................

83.2-12 INSTRUMENTATION Reactor Protection System (RPS) Instrumentation

.............................

3.3-1 Source Range Monitor (SRM) Instrumentation

...........

........................

3.3-10 Period Based Detection System (PBDS) .............................................

3.3-14a Control Rod Block Instrumentation

......................................................

3.3-15 Post Accident Monitoring (PAM) Instrumentation

...................

.............

3.3-19 Remote Shutdown System ..................................................................

3.3-23 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation

... 3.3-25 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation

.............................................

3.3-29 Emergency Core Cooling System (ECCS) Instrumentation

................

3.3-32 Reactor Core Isolation Cooling (RCIC) System Instrumentation

.........

3.3-44 Primary Containment and Drywell Isolation Instrumentation

...............

3.3-48 Secondary Containment and Fuel Building Isolation Instrumentation.

3.3-58 Containment Unit Cooler System Instrumentation

..............................

3.3-62 Relief and Low-Low Set (LLS) Instrumentation

.....................

..............

3.3-66 Control Room Fresh Air (CRFA) System Instrumentation

...................

3.3-68 Loss of Power (LOP) Instrumentation

.................................................

3.3-72 Reactor Protection System (RPS) Electric Power Monitoring

.............

3.3-75 INSTRUMENTATION Reactor Protection System (RPS) Instrumentation

.............................

83.3-1 Source Range Monitor (SRM) Instrumentation

...................................

83.3-32 Period Based Detection System (PBDS) ....................

.........................

83.3-39a Control Rod Block Instrumentation

......................................................

B 3.3-40 Post Accident Monitoring (PAM) Instrumentation

................................

8 3.3-49 Remote Shutdown System ..................................................................

83.3-60 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation

... 8 3.3-65 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation

.............................................

8 3.3-76 Emergency Core Cooling System (ECCS) Instrumentation

................

83.3-85 Reactor Core Isolation Cooling (RCIC) System Instrumentation

.........

83.3-122 (continued)

RIVER BEND ii Revision No. 6-5 B 3.3 B 3.3.6.1 B 3.3.6.2 B 3.3.6.3 B 3.3.6.4 B 3.3.7.1 B 3.3.8.1 B 3.3.8.2 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 B3.4 B 3.4.1 B 3.4.2 B 3.4.3 B3.4.4 B 3.4.5 B 3.4.6 B3.4.7 B3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS INSTRUMENTATION (continued)

Primary Containment and Dryweli Isolation Instrumentation

...............

B 3.3-134 Secondary Containment and Fuel Building Isolation Instrumentation.

B 3.3-170 Containment Unit Cooler System Instrumentation

..............................

B 3.3-181 Relief and Low-Low Set (LLS) Instrumentation

...................................

B 3.3-191 Control Room Fresh Air (CRFA) System Instrumentation

...................

B 3.3-198 Loss of Power (LOP) Instrumentation

.................................................

B 3.3-209 Reactor Protection System (RPS) Electric Power Monitoring

.............

B 3.3-216 REACTOR COOLANT SYSTEM (RCS) Recirculation Loops Operating

........................

....................................

3.4-1 Flow Control Valves (FCVs) ..............

..................................................

3.4-6 Jet Pumps ............................................................................................

3.4-8 Safety/Relief Valves (S/RVs) ...............................................................

3.4-10 RCS Operational LEAKAGE ................................................................

3.4-12 RCS Pressure Isolation Valve (PIV) Leakage .....................................

3.4-14 RCS Leakage Detection Instrumentation

............................................

3.4-17 RCS Specific Activity ...........................................................................

3.4-20 Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown ................................................................

3.4-22 Residual Heat Removal (RH R) Shutdown Cooling System -Cold Shutdown ..............................................................

3.4-25 RCS Pressure and Temperature (PIT) Limits ......................................

3.4-27 Reactor Steam Dome Pressure ...........................................................

3.4-33 REACTOR COOLANT SYSTEM (RCS) Recirculation Loops Operating

............................................................

B 3.4-1 Flow Control Valves (FCVs) ................................................................

B 3.4-9 Jet Pumps ..................................

..........................................................

B 3.4-13 Safety/Relief Valves (S/RVs) ...............................................................

B 3.4-17 RCS Operational LEAKAGE. ...............................................................

B 3.4-22 RCS Pressure Isolation Valve (PIV) Leakage ...........

..........................

B 3.4-27 RCS Leakage Detection Instrumentation

............................................

B 3.4-32 RCS Specific Activity ...........................................................................

B 3.4-39 Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown ................................................................

B 3.4-43 Residual Heat Removal (RHR) Shutdown Cooling System -Cold Shutdown ..............................................................

B 3.4-48 RCS Pressure and Temperature (PIT) Limits ............

..........................

B 3.4-53 Reactor Steam Dome Pressure ...........................................................

B 3.4-62 (continued)

RIVER BEND iii Revision No. 6-5 3.5 3.5.1 3.5.2 3.5.3 B 3.5 83.5.1 8 3.5.2 8 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.1.10 3.6.2.1 3.6.2.2 3.6.2.3 3.6.3.1 3.6.3.2 3.6.3.3 3.6.4.1 3.6.4.2 3.6.4.3 3.6.4.4 3.6.4.5 3.6.4.6 3.6.4.7 3.6.5.1 3.6.5.2 3.6.5.3 3.6.5.4 3.6.5.5 B 3.6 83.6.1.1 83.6.1.2 83.6.1.3 83.6.1.4 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS -Operating

................................

................................................ 3.5-1 ECCS -Shutdown ....................................

.................

........................... 3.5-6 RCIC System ...............................................

........................................ 3.5-10 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS -Operating

............................................................................

.... B 3.5-1 ECCS -Shutdown ................................................................................ B 3.5-15 RCIC System ...............................

........................................................ 8 3.5-20 CONTAINMENT SYSTEMS Primary Containment-Operating

............................................

.............. 3.6-1 Primary Containment Air Locks ..............

........................

.....................

3.6-3 Primary Containment Isolation Valves (PCIVs) ...................................

3.6-9 Primary Containment Pressure .................................

.......................... 3.6-21 Primary Containment Air Temperature

........................

........................ 3.6-22 Low-Low Set (LLS) Valves ..............................

................................... 3.6-23 Primary Containment Unit Coolers ..................

....................................

3.6-25 DELETED ....................................

.......................................

................. 3.6-27 Main Steam -Positive Leakage Control System (MS -PLCS) ............. 3.6-29 Primary Containment

-Shutdown ..............................

.......................... 3.6-31 Suppression Pool Average Temperature

............................................ 3.6-33 Suppression Pool Water Level ................

...................................

......... 3.6-36 Residual Heat Removal (RHR) Suppression Pool Cooling ................. 3.6-37 DELETED .......................................

........................................

.............

3.6-39 Primary Containment and Drywell Hydrogen Igniters .......................... 3.6-41 Primary ContainmentiDrywell Hydrogen Mixing System ............

......... 3.6-44 Secondary Containment

-Operating

.................................................... 3.6-46 Secondary Containment Isolation Dampers (SCIDs) and Fuel 8uilding Isolation Dampers (FBI Os) .............................

............... 3.6-48 Standby Gas Treatment (SGT) System ..........................

..................... 3.6-51 DELETED ........................

.................................................................... 3.6-53 Fuel Building .......................................

................................................. 3.6-55 DELETED ...................................

......................................................... 3.6-56 Fuel Building Ventilation System -Fuel Handling ................................ 3.6-58 Drywel/ ..................................................

...........

.................................... 3.6-60 Drywell Air Lock ...............

.................................................................... 3.6-63 Drywell Isolation Valves .............

........................

..................................

3.6-67 Orywell Pressure ................................................................................. 3.6-71 Drywel/ Air Temperature

...................................................................... 3.6-72 CONTAINMENT SYSTEMS Primary Containment-Operating

..................

............

..........................

B 3.6-1 Primary Containment Air Locks .......................

.................................... B 3.6-5 Primary Containment Isolation Valves (PCIVs) ................................... B 3.6-15 Primary Containment Pressure ........................

.................

............

...... B 3.6-30 (continued)

RIVER BEND iv Revision No. 191 B 3.6 B3.6.1.5 B 3.6.1.6 B3.6.1.7 B 3.6.1.8 B 3.6.1.9 B3.6.1.10 B 3.6.2.1 B 3.6.2.2 B 3.6.2.3 B 3.6.3.1 B 3.6.3.2 B 3.6.3.3 B 3.6.4.1 B 3.6.4.2 B 3.6.4.3 B 3.6.4.4 B 3.6.4.5 B 3.6.4.6 B 3.6.4.7 B 3.6.5.1 B 3.6.5.2 B 3.6.5.3 B 3.6.5.4 B 3.6.5.5 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 B 3.7 B 3.7.1 B 3.7.2 B 3.7.3 B 3.7.4 B 3.7.5 B 3.7.6 B 3.7.7 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS CONTAINMENT SYSTEMS (continued)

Primary Containment Air Temperature

.........................

....................... B 3.6-32 Low-Low Set (LLS) Valves ............................

...........................

..........

B 3.6-35 Primary Containment Unit Coolers ...........................

........................... B 3.6-39 DELETED ..................

............................

.............................................. B 3.6-43 Main Steam -Positive Leakage Control System (MS -PLCS) ............. B 3.6-47 Primary Containment

-Shutdown .....................

................................... B 3.6-50 Suppression Pool Average Temperature

....................

........................ B 3.6-54 Suppression Pool Water Level ............................................................ B 3.6-59 Residual Heat Removal (RHR) Suppression Pool Cooling ................. B 3.6-62 DELETED .........................................................

................................... B 3.6-66 Primary Containment and Drywell Hydrogen Igniters ..........................

B 3.6-72 Primary Containment/Drywell Hydrogen Mixing System .....................

B 3.6-78 Secondary Containment-Operating

.................................................... B 3.6-83 Secondary Containment Isolation Dampers (SCIDs) and Fuel Building Isolation Dampers (FBI Os) ............................................ B 3.6-89 Standby Gas Treatment (SGT) System ..............

................................. B 3.6-96 DELETED ........................................................................................

.... B 3.6-101 Fuel Building ............

............................................................................ B 3.6-104 DELETED .....................................................................................

....... B 3.6-107 Fuel Building Ventilation System -Fuel Handling .........................

....... B 3.6-112 Drywell ...................................................

.............................................. B 3.6-117 Drywell Air Lock .....................................................................

..............

B 3.6-122 Drywellisolation Valves ....................................................................... B 3.6-129 Drywell Pressure ...........................................

.........................

............. B 3.6-137 Drywell Air Temperature

..............................................

........................

B 3.6-140 PLANT SYSTEMS Standby Service Water (SSW) System and Ultimate Heat Sink (UHS) .............................................

.................................... 3.7-1 Control Room Fresh Air (CRFA) System ..............................

............... 3.7-5 Control Room Air Conditioning (AC) System ..............................

......... 3.7-9 Main Condenser Offgas ....................................................................... 3.7-12 Main Turbine Bypass System .............................................................. 3.7-14 Fuel Pool Water Level ..........................................................

............... 3.7-15 Control Building Air Conditioning (CBAC) System ..............................

3.7-16 PLANT SYSTEMS Standby Service Water (SSW) System and Ultimate Heat Sink (UHS) ................................................................................. B 3.7-1 Control Room Fresh Air (CRFA) System ................................

............. B 3.7-10 Control Room Air Conditioning (AC) System ...................

.................... B 3.7-17 Main Condenser Offgas .........................................................

..............

B 3.7-22 Main Turbine Bypass System .............................................................. B 3.7-25 Fuel Pool Water Level ......................................................................... B 3.7-29 Control Building Air Conditioning (CBAC) System ............

.............

..... B 3.7-32 (continued)

RIVER BEND v Revision No. 6-5 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 3.8.10 B 3.8 B 3.8.1 B 3.8.2 B 3.8.3 B 3.8.4 B 3.8.5 B 3.8.6 B 3.8.7 B 3.8.8 B 3.8.9 B 3.8.10 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 3.9.8 3.9.9 B 3.9 B 3.9.1 B 3.9.2 B 3.9.3 B 3.9.4 B 3.9.5 B 3.9.6 B 3.9.7 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS ELECTRICAL POWER SYSTEMS AC Sources -Operating

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3.8-1 AC Sources -Shutdown ...................................

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3.8-17 Diesel Fuel Oil, Lube Oil, and Starting Air ................

........................... 3.8-21 DC Sources -Operating

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.............. 3.8-24 DC Sources -Shutdown ....................................................................... 3.8-28 Battery Cell Parameters

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..................... 3.8-31 Inverters

-Operating

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............. 3.8-35 Inverters

-Shutdown ...............................

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3.8-36 Distribution Systems -Operating

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3.8-38 Distribution Systems -Shutdown ..........................................

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3.8-41 ELECTRICAL POWER SYSTEMS AC Sources -Operating

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................................... B 3.8-1 AC Sources-Shutdown

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..... B 3.8-34 Diesel Fuel Oil, Lube Oil, and Starting Air ..................

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B 3.8-41 DC Sources -Operating

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................................................... B 3.8-50 DC Sources -Shutdown ...................................

.................................... B 3.8-59 Battery Cell Parameters

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B 3.8-63 Inverters

-Operating

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B 3.8-70 Inverters

-Shutdown ..........

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B 3.8-74 Distribution Systems-Operating

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B 3.8-78 Distribution Systems -Shutdown ......................................

................... B 3.8-89 REFUELING OPERATIONS Refueling Equipment Interlocks

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3.9-1 Refuel Position One-Rod-Out Interlock

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3.9-2 Control Rod Position ........................

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3.9-4 Control Rod Position Indication

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3.9-5 Control Rod OPERABI LlTY -Refueling

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...... 3.9-7 Reactor Pressure Vessel (RPV) Water Level-Irradiated Fuel ............

3.9-8 Reactor Pressure Vessel (RPV) Water Level-New Fuel or Control Rods ...........................

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................ 3.9-9 Residual Heat Removal (RH R) -High Water Level ............................. 3.9-10 Residual Heat Removal (RH R) -Low Water Level .............

................. 3.9-12 REFUELING OPERATIONS Refueling Equipment Interlocks

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.................. B 3.9-1 Refuel Position One-Rod-Out Interlock

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..................... B 3.9-5 Control Rod Position ...........

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B 3.9-9 Control Rod Position Indication

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................ B 3.9-12 Control Rod OPERABILITY

-Refueling

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.... B 3.9-16 Reactor Pressure Vessel (RPV) Water Level-Irradiated Fuel ........... B 3.9-19 Reactor Pressure Vessel (RPV) Water Level -New Fuel or Control Rods .............

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.............. B 3.9-22 ( continued)

RIVER BEND vi Revision No. 6-5 B 3.9 B 3.9.8 B 3.9.9 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 B 3.10 B 3.10.1 B 3.10.2 B 3.10.3 B 3.10.4 B 3.10.5 B 3.10.6 B 3.10.7 B 3.10.8 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS REFUELING OPERATIONS (continued)

Residual Heat Removal (RHR)-High Water Level ....................

......... B 3.9-25 Residual Heat Removal (RHR)-Low Water Level .....................

......... B 3.9-29 SPECIAL OPERA TIONS Inservice Leak and Hydrostatic Testing Operation

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.. 3.10-1 Reactor Mode Switch Interlock Testing ..................................

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3.10-4 Single Control Rod Withdrawal-Hot Shutdown ....... : .............

............. 3.10-6 Single Control Rod Withdrawal-Cold Shutdown ................................. 3.10-9 Single Control Rod Drive (CRD) Removal -Refueling

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3.10-13 Multiple Control Rod Withdrawal-Refueling

....................................... 3.10-16 Control Rod Testing -Operating

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............... 3.10-18 SHUTDOWN MARGIN (SDM) Test-Refueling

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......................... 3.10-19 SPECIAL OPERATIONS Inservice Leak and HydrostatiC Testing Operation

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..... B 3.10-1 Reactor Mode Switch Interlock Testing ............................................... B 3.10-6 Single Control Rod Withdrawal-Hot Shutdown .........................

......... B 3.10-11 Single Control Rod Withdrawal-Cold Shutdown ....................

............. B 3.10-16 Single Control Rod Drive (CRD) Removal-Refueling

......................... B 3.10-21 Multiple Control Rod VVithdrawal-Refueling

....................................... B 3.10-26 Control Rod Testing -Operating

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.......................... B 3.10-29 SHUTDOWN MARGIN (SDM) Test-Refueling

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.................... B 3.10-33 DESIGN FEATURES Site Location ........................................................................................ 4.0-1 Reactor Core .............................

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............................... 4.0-1 Fuel Storage ........................................

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................... 4.0-1 ADMINISTRATIVE CONTROLS Responsibility

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............................................................ 5.0-1 Organization

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................................................................ '" 5.0-2 Unit Staff Qualifications

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............................. 5.0-5 Procedures

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............................................................. 5.0-6 Programs and Manuals ....................................................................... 5.0-7 Reporting Requirements

...................................................................... 5.0-17 High Radiation Area .................

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.......................... 5.0-20 RIVER BEND vii Revision No. 6-5