RBG-47859, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control

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Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
ML18116A646
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/26/2018
From: Maguire W
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-47859
Download: ML18116A646 (17)
v • d • e


Text

  • Entergx

~

Entergy Operations, Inc.

River Bend Stallon 5485 U.S Highway 61 N St. Francisville . LA 70775 Tel 225-381 -4177 William F. Maguire Site Vice President River Bend Station RBG-47859 April 26, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington , DC 20555-0001

SUBJECT:

Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47

References:

1) Entergy Letter: License Amendment Request (LAR) (RBG-47801 , dated November 15, 2017) [ADAMS Accession Number ML17319A898].
2) Phone Call : River Bend Station, Unit 1, OPDRV TSTF-542 Clarification Call on April 18, 2018

Dear Sir or Madam:

In accordance with 10 CFR 50.90, "Amendment of License or Construction Permit at Request of Holder," Entergy previously submitted a request for an amendment to the Technical Specifications (TS) for River Bend Station, Unit I (see reference 1). The proposed change replaces existing TS requirements related to "Operations with a Potential for Draining the Reactor Vessel" (OPDRVs) with new requirements on Reactor Pressure Vessel Water Inventory Control (RPV WIC) to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor vessel water level to be greater than the top of active irradiated fuel. Per Reference 2, the NRC staff requested clarification via a telephone conversation needed to complete the license amendment request.

Please see the attached Enclosures for the responses to the NRC request for clarification.

This supplemental information provided does not change the scope of the original submittal.

There are no regulatory commitments contained in this submittal. If you require additional information, please contact Mr. Tim Schenk at (225)-381-4177 or by email at tschenk @entergy.com .

I declare under penalty of perjury that the foregoing is true and correct. Executed on April 26,2018.

Sincerely, WFM/djp

RBG-47859 Page 2 of 2 : Responses to phone call Clarification Request (RAI Questions on TSTF-542) : TS 3.3.5.2 Rev 1 : UFSAR pages 1.2-24 & 6.3-13 (LPCS LPCI & HPCS) : SR 3.5.2.5 Rev 1 cc: U.S . Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.

Arlington , TX 76011 -4511 NRC Resident Inspector Attn : Mr. Jeff Sowa 5485 U.S. Highway 61 , Suite 1 St. Francisville, LA 70775 Regional Administrator U.S Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington , TX 76011-4511 Public Utility Commission of Texas Attn : Ms. Tracie Lowrey 1701 N. Congress Ave.

Austin , TX 78711 -3326 U.S. Nuclear Regulatory Commission Attn: Ms. Lisa M. Regner, Project Manager MS-8-H4 One White Flint North 11555 Rockville Pike Rockville, MD 20852

RBG-47854 Enclosure 1 Responses to phone call Clarification Request (RAI Questions on TSTF-542)

TSTF-542, "Reactor Pressure Vessel Water Inventory Control"

REQUEST FOR ADDITIONAL INFORMATION FOR ENTERGY OPERATIONS INC.

RIVER BEND STATION, UNIT 1 APPLICATION TO REVISE TECHNICAL SPECIFICATION TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER 542, REVISION 2, " REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL" (EPI D: L-2017-LLA-0383)

By application dated November 15, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17319A898, Entergy Operations, Inc. , (the licensee),

requested to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2, which changes the Technical Specifications (TSs) for River Bend Station (RBS), Unit 1. The enclosure for TSTF-542, Revision 2dated March 14, 2016, is found in ADAMS Accession No. ML16074A448.

RBS TS Section 2.0, "Safety Limits," 2.1.1 .3 states; "Reactor vessel water level shall be greater than the top of active irradiated fueL" Safety Limit 2.1.1.3 is maintained through the TS Limiting Condition for Operation (LCO), applicability, actions, and notes. The RBS TSs require certain safety systems to be OPERABLE during "operations with a potential for draining the reactor vessel" (OPDRVs).

The proposed changes would replace the existing requirements in the TS related to OPDRVs with revised TS providing an alternative for Reactor Pressure Vessel (RPV) Water Inventory Control. These alternative requirements would protect Safety Limit 2.1.1.3.

Question 1:

In Attachment 2 of the License Amendment Request (LAR), page 3.3-43a, TS LCO 3.3.5.2, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation, Required Action B.1, states:

Declare associated flow path(s) incapable of automatic isolation.

TSTF-542, Revision 2 (ADAMS Accession No. ML16074A448, page 3.3.5.2A-1) for TS LCO 3.3.5.2, Required Action B.1 states:

Declare associated [penetrationl flow path(s) incapable of automatic isolation. [emphasis added]

Justify the deviation from TSTF-542 .

Agree , need to add "penetration" back in. Refer to Enclosure 2.

Question 2:

In Attachment 2 of the LAR , page 3.3-43b, TS LCO 3.3.5.2, Reactor Pressure Vessel (RPV)

Water Inventory Control Instrumentation , Condition E is related to High Pressure Core Spray and the Reactor Vessel Water Level 8 Function. In Attachment 1 of the LAR, Section 2.2.2.3, the variation states that the HPCS level 8 and manual initiation functions are not retained due to an error found in TSTF-542 for BWR5 and BWR6 plants. With the removal of these functions ,

Condition E is no longer referenced in TS Table 3.3.5.2-1.

Justify the retention of TS LCO 3.3.5.2, Condition E (including Required Actions and Completion Time). Note that Conditions F and G and Table 3.3.5.2-1, RPV Water Inventory Control Instrumentation, conditions should be renumbered if the LCO is removed.

Condition E should be removed; this is the BWROG TSTF correction variation and a standard variation was provided by the BWROG. Below is an email excerpt from the BWROG. Refer to :

"Last year we provided a generic variation from TSTF-542 regarding the HPCS Level 8 bypass that affected BWRl5 and BWRl6 plants. Many plants have incorporated that change into their TSTF-542 submittals.

During a review, we discovered that we did not state that the variation eliminated the only function that referenced TS 3.3.5.2, Condition E. As a result, Condition E can be omitted."

The following will be added to the RBS list of Deviations paragraph 2.2.2.3 per BWROG standard deviation:

"HPCS Function 3.a is the only function resulting in TS 3.3.5.2 Condition E. Therefore, the removal of Function 3.a results in the deletion of Condition E and the redesignation of Conditions F and G."

Question 3:

In Attachment 2 of the LAR, pages 3.3-43d and 3.3-43e, TS Table 3.3.5.2 -1, Functions 1.b-LPCS Pump Discharge Flow - Low (Bypass), 1.c - LPCI Pump A Discharge Flow - Low (Bypass), 3.b - HPCS Pump Discharge Pressure - High (Bypass), and 3.c - HPCS System Flow Rate - Low (Bypass) each specify one channel in the Required Channels Per Function column. In TSTF-542, the equivalent functions in STS Table 3.3.5.2-1 1.b, 1.c, 3.c., and 3.d, specify one per pump in this column.

For the proposed RBS TS Table 3.3.5.2-1 Functions 1.b, 1.c, 3.b, and 3.c, provide justification for varying from the "1 per pump" nomenclature specified in TSTF-542.

Justification provided. Refer to Enclosure 3.

Editorial errors noted:

LAR Attachment 2, Page 3.3.43e:

Suggest using "Reactor Pressure Vessel (RPV) Inventory Control" for LCO 3.5.2 title consistency This error was found only on pages 3.3-43d and 3.3-43e. Refer to Enclosure 2.

LAR Attachment 2, Page 3.5-8:

SR 3.5.3.5 has two notes, therefore, NOTE should be NOTES Agree. Refer to Enclosure 4.

RBG-47854 Enclosure 2 Responses to phone call Clarification Request TS 3.3.5.2 Rev 1

RPV Water Inventory Control Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.2-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.2-1 for the channel.

B. As required by B.1 Declare associated Immediately Required Action A.1 j.Iij'mmlitim flow path(s) and referenced in incapable of automatic Table 3.3.5.2-1.

isolation.

AND Immediately B.2 Calculate DRAIN TIME.

C. As required by C.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Required Action A.1 and referenced in Table 3.3.5.2-1.

(continued)

RIVER BEND 3.3-43a Amendment No. xxx

RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Declare H PCS system 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.1 and referenced inoperable in Table 3.3.5.2-1.

OR D.2 Align the HPCS pump 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> suction to the suppression pool.

Ia* As required by Required Ia.1 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action A.1 and referenced OPERABLE status.

in Table 3.3.5.2-1.

Ii* Required Action and Ii. 1 Declare associated Immediately associated Completion ECCS injection/spray Time of Condition C, D, or subsystem inoperable.

[§! not met.

\ ,.

RIVER BEND 3.3-43b Amendment No. xxx

RPV Water Inventory Control Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

N()TE---------------------------------------------------------

Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS function.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTI()NAL TEST. ",,-, 92 days SR 3.3.5.2.3 Perform L()GIC SYSTEM FUNCTI()NAL TEST. 24 months RIVER BEND 3.3-43c Amendment No.xxx

Table 3.3.5.2-1 (page 1 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCE OTHER CHANNELS FROM SPECIFIED PER REQU IRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Low Pressure Coolant Injection A (LPCI ) and Low Pressure Core Spray (LPCS) Subsytems
a. Reactor Vessel 4, 5 4(a) C SR 3.3.5.2.1 ~ 502 psig Pressure - Low SR 3.3.5.2.2 (Injection Permissive)
b. LPCS Pump 4, 5 1(a) SR 3.3.5.2.1  :?: 750 gpm Discharge Flow - SR 3.3.5.2 .2 Low (Bypass)
c. LPCI Pump A 4, 5 1(a) SR 3.3.5.2.1 ~ 900 gpm Discharge Flow - SR 3.3.5.2.2 Low (Bypass)
d. Manual Initiation 4, 5 1 per system IS SR 3.3.5.2.3 NA (a)
2. LPC I Band LPCI C Subsytems
a. Reactor Vessel 4, 5 4(a) C SR 3.3.5.2.1 ~ 502 psig Pressure - Low SR 3.3 .5.2.2 (Injection Permissive)
b. LPCI Pump Band 4, 5 1 per pump IS SR 3.3.5.2.1  :?: 900 gpm LPC I Pump C (a) SR 3.3.5.2.2 Discharge Flow -

Low (Bypass)

c. Manual Initiation 4,5 1 per system IS SR 3.3.5.2.3 NA (a)

(a)

C,,," ,I.'  !

Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Refletor Pre:!l!tJre Ve:!l!el Wflter Inventory "Reactor Pressure Vessel (RPV) Water Inventory Control."

RIVER BEND 3.3-43d Amendment No.xxx

Table 3.3.5.2-1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE MODES OR CONDITIONS OTHER REQUIRED REFERENCE SPECIFIED CHANNELS FROM FUNCTION COND ITIONS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION ACTION A.1 REQUIREMENTS VALUE

3. High Pressure Core Spray (HPCS) System
a. Condensate Storage 4(b) , 5(b) 2(a) D SR 3.3.5.2. 1 ~ -4.5 inches Tank Level - Low SR 3.3.5.2.2
b. HPCS Pump 4, 5 1(a) Ii SR 3.3.5.2.1 ~ 275 psig Discharge Pressure SR 3.3.5.2.2

- High (Bypass)

c. HPCS System Flow 4, 5 1(a) SR 3.3.5.2.1 2710 gpm Rate- Low SR 3.3.5.2.2 (Bypass)
4. RHR System Isolation Reactor Vessel (c) 2 in one trip B SR 3.3.5.2.1 ~ 8.7 inches Water Level- Low system SR 3.3.5.2.2 (Level 3)
5. Reactor Water Cleanup (RWCU ) System Isolation
a. Reactor Water Level (c) 2 in one trip B SR 3.3.5.2.1 ~ -47 inches

- Low, Low (Level system SR 3.3.5.2.2 2)

(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reacto, ,",esso,e Vessel'oVate, IlivelitOly Co"tlol."

(b) Wh en HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control" and aligned to th storage tank.

(c) When automatic isolation of th e associated penetration flow path(s) is credited in calcu lating DRAIN TIME.

"Reactor Pressure Vessel (RPV) Water Inventory Control."

RIVER BEND 3.3-43e Amendment No.xxx

RBG-47854 Enclosure 3 Responses to phone call Clarification Request UFSAR pages 1.2-24 & 6.3-13 (LPCS LPCI & HPCS)

RBS USAR

2. Automatic Depressurization Svstem (ADS) - The automatic dep ressurizati on system rapidly reduces reactor vessel pressure in a LOCA situation in which the HPCS system fails to maintain the reactor vessel water level. The depressurization provided by the system enables the low pres sure ECCS to deliver cooling water to the reactor vessel. The ADS uses some of the relief valves that are part of the nuclear system pressure relief system.

The automatic relief valves are arranged to open on conditions indicating both that a break in the RCPB has occurred and that the HPCS system is not delivering sufficient cooling water to the reactor vessel to maintain the water level above a preselected value.

The ADS is not activated unless either the LPCS or LPCI pumps are operating. This is to ensure that adequate coolant is available to maintain reactor water level after the depressurization .

3. Low Pressure Core Spray (LPCS) - The LPCS system consists of one independent pump and the valves and piping to deliver cooling water to a spray sparger over the core. The system is actuated by conditions indicating that a breach exists in the RCPB but water is delivered to the core only after reactor vessel pressure is reduced. This system provides the capability to cool the fuel by spraying water into each fuel channel. The LPCS loop functioning in conjunction with the ADS or HPCS can provide sufficient fuel cladding cooling following a LOCA.
4. Low Pressure Coolant In; ection (LPCI) Low pressure coolant injection is an operating mode of the residual heat removal (RHR) system, but is discussed here because the LPCI mode acts as an engineered safety feature in conjunction with the other emergency core cooling systems. LPCI uses the pump loops of the RHR to inject cooling water into the pressure vessel. LPCI is actuated by conditions indicating a breach in the RCPB, but water is delivered to the core only after reactor vessel pressure is reduced. LPCI operation provides the capability of core reflooding, following a LOCA, in time to maintain the fuel cladding below the prescribed temperature limit.
1. 2-24 August 1987

RES USAR the pump manufacturer. The comparison table below demonstrates that all the ECCS pumps have adequate margin of NPSH available over actual NPSH required:

NPSH Margin NPSH Required 3 Ft Adjusted to a Above Pump Mounting Reference Elevation Flange Based on 3 Ft Above Pump Performance Test Pump Mounting Flange (ft) by Pump Vendor (ft) e ~10 HPCS >5 1. 00 LPCS >5 0.30 RHR (LPCI) >5 0.30 10f-e 6.3.2.2.1 High Pressure Core Spray (HPCS) System e ~10 The HPCS system consists of a single motor-driven centrifugal pump located outside the primary containment, a spray sparger in the reactor vessel located above the core (separate from the LPCS sparger), and associated system piping , valves, controls, and instrumentation. The system is designed to operate from normal offsite auxiliary power or from a diesel generator supply if offsite power is not available. The P&ID, Fig. 6.3 - 1 for the HPCS, shows the system components and their arrangement.

10f-e e ~12 The principal active HPCS equipment is located outside the primary containment. Suction piping is provided from the condensate storage tank and the suppression pool. Such an arrangement provides the capability to use reactor grade water from the condensate storage tank when the HPCS system functions to back up the RCIC system. In the event that the condensate storage water supply becomes exhausted or is not available, automatic switchover to the suppression pool water source assures a closed cooling water supply for continuous operation of the HPCS system. HPCS pump suction is also automatically transferred to the suppression pool if the suppression pool water level exceeds a prescribed value. The condensate storage tank reserves a maximum of 125,000 gal of water just for use by the HPCS and RCIC.

12f-e After the HPCS injection piping enters the vessel, it divides and enters the shroud at two points near the top of the shroud. A semicircular sparger is attached to each outlet. Nozzles are spaced around the spargers to spray the water radially over the core and into the fuel assemblies.

Revision 12 6.3-13 December 1999

RBG-47854 Enclosure 4 Responses to phone call Clarification Request SR 3.5.2.5 Rev 1

~) EGGS Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2 .~ Verify, for the required High Pressure Core Spray 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (HPCS) System, the:

~ a.

b.

Suppression pool water level is :> 13 ft 3 inches; or Condensate storage tank water level is :> 11 ft 1 inch.

SR 3.5 .2.J Verify, for eaffi required ECCS injection/spray 31 days E!

subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

o SR 3.5 .2.4 ------------------------------ ~JOTE------------------------------

1. GRe low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal , if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system t,V",.' '; flow paths opened und tive control.

, for the ------------------------------

~ Verifyeaffi required ECCS injection/spray subsystem 31 days

~---->~ manual, power operated , and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

RIVER BEND 3.5-8 Amendment No. 8+, H~~

  • Entergx

~

Entergy Operations, Inc.

River Bend Stallon 5485 U.S Highway 61 N St. Francisville . LA 70775 Tel 225-381 -4177 William F. Maguire Site Vice President River Bend Station RBG-47859 April 26, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington , DC 20555-0001

SUBJECT:

Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control" River Bend Station , Unit 1 Docket No. 50-458 License No. NPF-47

References:

1) Entergy Letter: License Amendment Request (LAR) (RBG-47801 , dated November 15, 2017) [ADAMS Accession Number ML17319A898].
2) Phone Call : River Bend Station, Unit 1, OPDRV TSTF-542 Clarification Call on April 18, 2018

Dear Sir or Madam:

In accordance with 10 CFR 50.90, "Amendment of License or Construction Permit at Request of Holder," Entergy previously submitted a request for an amendment to the Technical Specifications (TS) for River Bend Station, Unit I (see reference 1). The proposed change replaces existing TS requirements related to "Operations with a Potential for Draining the Reactor Vessel" (OPDRVs) with new requirements on Reactor Pressure Vessel Water Inventory Control (RPV WIC) to protect Safety Limit 2.1.1.3. Safety Limit 2.1.1.3 requires reactor vessel water level to be greater than the top of active irradiated fuel. Per Reference 2, the NRC staff requested clarification via a telephone conversation needed to complete the license amendment request.

Please see the attached Enclosures for the responses to the NRC request for clarification.

This supplemental information provided does not change the scope of the original submittal.

There are no regulatory commitments contained in this submittal. If you require additional information, please contact Mr. Tim Schenk at (225)-381-4177 or by email at tschenk @entergy.com .

I declare under penalty of perjury that the foregoing is true and correct. Executed on April 26,2018.

Sincerely, WFM/djp

RBG-47859 Page 2 of 2 : Responses to phone call Clarification Request (RAI Questions on TSTF-542) : TS 3.3.5.2 Rev 1 : UFSAR pages 1.2-24 & 6.3-13 (LPCS LPCI & HPCS) : SR 3.5.2.5 Rev 1 cc: U.S . Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.

Arlington , TX 76011 -4511 NRC Resident Inspector Attn : Mr. Jeff Sowa 5485 U.S. Highway 61 , Suite 1 St. Francisville, LA 70775 Regional Administrator U.S Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington , TX 76011-4511 Public Utility Commission of Texas Attn : Ms. Tracie Lowrey 1701 N. Congress Ave.

Austin , TX 78711 -3326 U.S. Nuclear Regulatory Commission Attn: Ms. Lisa M. Regner, Project Manager MS-8-H4 One White Flint North 11555 Rockville Pike Rockville, MD 20852

RBG-47854 Enclosure 1 Responses to phone call Clarification Request (RAI Questions on TSTF-542)

TSTF-542, "Reactor Pressure Vessel Water Inventory Control"

REQUEST FOR ADDITIONAL INFORMATION FOR ENTERGY OPERATIONS INC.

RIVER BEND STATION, UNIT 1 APPLICATION TO REVISE TECHNICAL SPECIFICATION TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER 542, REVISION 2, " REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL" (EPI D: L-2017-LLA-0383)

By application dated November 15, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17319A898, Entergy Operations, Inc. , (the licensee),

requested to adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2, which changes the Technical Specifications (TSs) for River Bend Station (RBS), Unit 1. The enclosure for TSTF-542, Revision 2dated March 14, 2016, is found in ADAMS Accession No. ML16074A448.

RBS TS Section 2.0, "Safety Limits," 2.1.1 .3 states; "Reactor vessel water level shall be greater than the top of active irradiated fueL" Safety Limit 2.1.1.3 is maintained through the TS Limiting Condition for Operation (LCO), applicability, actions, and notes. The RBS TSs require certain safety systems to be OPERABLE during "operations with a potential for draining the reactor vessel" (OPDRVs).

The proposed changes would replace the existing requirements in the TS related to OPDRVs with revised TS providing an alternative for Reactor Pressure Vessel (RPV) Water Inventory Control. These alternative requirements would protect Safety Limit 2.1.1.3.

Question 1:

In Attachment 2 of the License Amendment Request (LAR), page 3.3-43a, TS LCO 3.3.5.2, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation, Required Action B.1, states:

Declare associated flow path(s) incapable of automatic isolation.

TSTF-542, Revision 2 (ADAMS Accession No. ML16074A448, page 3.3.5.2A-1) for TS LCO 3.3.5.2, Required Action B.1 states:

Declare associated [penetrationl flow path(s) incapable of automatic isolation. [emphasis added]

Justify the deviation from TSTF-542 .

Agree , need to add "penetration" back in. Refer to Enclosure 2.

Question 2:

In Attachment 2 of the LAR , page 3.3-43b, TS LCO 3.3.5.2, Reactor Pressure Vessel (RPV)

Water Inventory Control Instrumentation , Condition E is related to High Pressure Core Spray and the Reactor Vessel Water Level 8 Function. In Attachment 1 of the LAR, Section 2.2.2.3, the variation states that the HPCS level 8 and manual initiation functions are not retained due to an error found in TSTF-542 for BWR5 and BWR6 plants. With the removal of these functions ,

Condition E is no longer referenced in TS Table 3.3.5.2-1.

Justify the retention of TS LCO 3.3.5.2, Condition E (including Required Actions and Completion Time). Note that Conditions F and G and Table 3.3.5.2-1, RPV Water Inventory Control Instrumentation, conditions should be renumbered if the LCO is removed.

Condition E should be removed; this is the BWROG TSTF correction variation and a standard variation was provided by the BWROG. Below is an email excerpt from the BWROG. Refer to :

"Last year we provided a generic variation from TSTF-542 regarding the HPCS Level 8 bypass that affected BWRl5 and BWRl6 plants. Many plants have incorporated that change into their TSTF-542 submittals.

During a review, we discovered that we did not state that the variation eliminated the only function that referenced TS 3.3.5.2, Condition E. As a result, Condition E can be omitted."

The following will be added to the RBS list of Deviations paragraph 2.2.2.3 per BWROG standard deviation:

"HPCS Function 3.a is the only function resulting in TS 3.3.5.2 Condition E. Therefore, the removal of Function 3.a results in the deletion of Condition E and the redesignation of Conditions F and G."

Question 3:

In Attachment 2 of the LAR, pages 3.3-43d and 3.3-43e, TS Table 3.3.5.2 -1, Functions 1.b-LPCS Pump Discharge Flow - Low (Bypass), 1.c - LPCI Pump A Discharge Flow - Low (Bypass), 3.b - HPCS Pump Discharge Pressure - High (Bypass), and 3.c - HPCS System Flow Rate - Low (Bypass) each specify one channel in the Required Channels Per Function column. In TSTF-542, the equivalent functions in STS Table 3.3.5.2-1 1.b, 1.c, 3.c., and 3.d, specify one per pump in this column.

For the proposed RBS TS Table 3.3.5.2-1 Functions 1.b, 1.c, 3.b, and 3.c, provide justification for varying from the "1 per pump" nomenclature specified in TSTF-542.

Justification provided. Refer to Enclosure 3.

Editorial errors noted:

LAR Attachment 2, Page 3.3.43e:

Suggest using "Reactor Pressure Vessel (RPV) Inventory Control" for LCO 3.5.2 title consistency This error was found only on pages 3.3-43d and 3.3-43e. Refer to Enclosure 2.

LAR Attachment 2, Page 3.5-8:

SR 3.5.3.5 has two notes, therefore, NOTE should be NOTES Agree. Refer to Enclosure 4.

RBG-47854 Enclosure 2 Responses to phone call Clarification Request TS 3.3.5.2 Rev 1

RPV Water Inventory Control Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.2-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.2-1 for the channel.

B. As required by B.1 Declare associated Immediately Required Action A.1 j.Iij'mmlitim flow path(s) and referenced in incapable of automatic Table 3.3.5.2-1.

isolation.

AND Immediately B.2 Calculate DRAIN TIME.

C. As required by C.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Required Action A.1 and referenced in Table 3.3.5.2-1.

(continued)

RIVER BEND 3.3-43a Amendment No. xxx

RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Declare H PCS system 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.1 and referenced inoperable in Table 3.3.5.2-1.

OR D.2 Align the HPCS pump 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> suction to the suppression pool.

Ia* As required by Required Ia.1 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Action A.1 and referenced OPERABLE status.

in Table 3.3.5.2-1.

Ii* Required Action and Ii. 1 Declare associated Immediately associated Completion ECCS injection/spray Time of Condition C, D, or subsystem inoperable.

[§! not met.

\ ,.

RIVER BEND 3.3-43b Amendment No. xxx

RPV Water Inventory Control Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

N()TE---------------------------------------------------------

Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS function.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTI()NAL TEST. ",,-, 92 days SR 3.3.5.2.3 Perform L()GIC SYSTEM FUNCTI()NAL TEST. 24 months RIVER BEND 3.3-43c Amendment No.xxx

Table 3.3.5.2-1 (page 1 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCE OTHER CHANNELS FROM SPECIFIED PER REQU IRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Low Pressure Coolant Injection A (LPCI ) and Low Pressure Core Spray (LPCS) Subsytems
a. Reactor Vessel 4, 5 4(a) C SR 3.3.5.2.1 ~ 502 psig Pressure - Low SR 3.3.5.2.2 (Injection Permissive)
b. LPCS Pump 4, 5 1(a) SR 3.3.5.2.1  :?: 750 gpm Discharge Flow - SR 3.3.5.2 .2 Low (Bypass)
c. LPCI Pump A 4, 5 1(a) SR 3.3.5.2.1 ~ 900 gpm Discharge Flow - SR 3.3.5.2.2 Low (Bypass)
d. Manual Initiation 4, 5 1 per system IS SR 3.3.5.2.3 NA (a)
2. LPC I Band LPCI C Subsytems
a. Reactor Vessel 4, 5 4(a) C SR 3.3.5.2.1 ~ 502 psig Pressure - Low SR 3.3 .5.2.2 (Injection Permissive)
b. LPCI Pump Band 4, 5 1 per pump IS SR 3.3.5.2.1  :?: 900 gpm LPC I Pump C (a) SR 3.3.5.2.2 Discharge Flow -

Low (Bypass)

c. Manual Initiation 4,5 1 per system IS SR 3.3.5.2.3 NA (a)

(a)

C,,," ,I.'  !

Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Refletor Pre:!l!tJre Ve:!l!el Wflter Inventory "Reactor Pressure Vessel (RPV) Water Inventory Control."

RIVER BEND 3.3-43d Amendment No.xxx

Table 3.3.5.2-1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE MODES OR CONDITIONS OTHER REQUIRED REFERENCE SPECIFIED CHANNELS FROM FUNCTION COND ITIONS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION ACTION A.1 REQUIREMENTS VALUE

3. High Pressure Core Spray (HPCS) System
a. Condensate Storage 4(b) , 5(b) 2(a) D SR 3.3.5.2. 1 ~ -4.5 inches Tank Level - Low SR 3.3.5.2.2
b. HPCS Pump 4, 5 1(a) Ii SR 3.3.5.2.1 ~ 275 psig Discharge Pressure SR 3.3.5.2.2

- High (Bypass)

c. HPCS System Flow 4, 5 1(a) SR 3.3.5.2.1 2710 gpm Rate- Low SR 3.3.5.2.2 (Bypass)
4. RHR System Isolation Reactor Vessel (c) 2 in one trip B SR 3.3.5.2.1 ~ 8.7 inches Water Level- Low system SR 3.3.5.2.2 (Level 3)
5. Reactor Water Cleanup (RWCU ) System Isolation
a. Reactor Water Level (c) 2 in one trip B SR 3.3.5.2.1 ~ -47 inches

- Low, Low (Level system SR 3.3.5.2.2 2)

(a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reacto, ,",esso,e Vessel'oVate, IlivelitOly Co"tlol."

(b) Wh en HPCS is OPERABLE for compliance with LCO 3.5.2, "RPV Water Inventory Control" and aligned to th storage tank.

(c) When automatic isolation of th e associated penetration flow path(s) is credited in calcu lating DRAIN TIME.

"Reactor Pressure Vessel (RPV) Water Inventory Control."

RIVER BEND 3.3-43e Amendment No.xxx

RBG-47854 Enclosure 3 Responses to phone call Clarification Request UFSAR pages 1.2-24 & 6.3-13 (LPCS LPCI & HPCS)

RBS USAR

2. Automatic Depressurization Svstem (ADS) - The automatic dep ressurizati on system rapidly reduces reactor vessel pressure in a LOCA situation in which the HPCS system fails to maintain the reactor vessel water level. The depressurization provided by the system enables the low pres sure ECCS to deliver cooling water to the reactor vessel. The ADS uses some of the relief valves that are part of the nuclear system pressure relief system.

The automatic relief valves are arranged to open on conditions indicating both that a break in the RCPB has occurred and that the HPCS system is not delivering sufficient cooling water to the reactor vessel to maintain the water level above a preselected value.

The ADS is not activated unless either the LPCS or LPCI pumps are operating. This is to ensure that adequate coolant is available to maintain reactor water level after the depressurization .

3. Low Pressure Core Spray (LPCS) - The LPCS system consists of one independent pump and the valves and piping to deliver cooling water to a spray sparger over the core. The system is actuated by conditions indicating that a breach exists in the RCPB but water is delivered to the core only after reactor vessel pressure is reduced. This system provides the capability to cool the fuel by spraying water into each fuel channel. The LPCS loop functioning in conjunction with the ADS or HPCS can provide sufficient fuel cladding cooling following a LOCA.
4. Low Pressure Coolant In; ection (LPCI) Low pressure coolant injection is an operating mode of the residual heat removal (RHR) system, but is discussed here because the LPCI mode acts as an engineered safety feature in conjunction with the other emergency core cooling systems. LPCI uses the pump loops of the RHR to inject cooling water into the pressure vessel. LPCI is actuated by conditions indicating a breach in the RCPB, but water is delivered to the core only after reactor vessel pressure is reduced. LPCI operation provides the capability of core reflooding, following a LOCA, in time to maintain the fuel cladding below the prescribed temperature limit.
1. 2-24 August 1987

RES USAR the pump manufacturer. The comparison table below demonstrates that all the ECCS pumps have adequate margin of NPSH available over actual NPSH required:

NPSH Margin NPSH Required 3 Ft Adjusted to a Above Pump Mounting Reference Elevation Flange Based on 3 Ft Above Pump Performance Test Pump Mounting Flange (ft) by Pump Vendor (ft) e ~10 HPCS >5 1. 00 LPCS >5 0.30 RHR (LPCI) >5 0.30 10f-e 6.3.2.2.1 High Pressure Core Spray (HPCS) System e ~10 The HPCS system consists of a single motor-driven centrifugal pump located outside the primary containment, a spray sparger in the reactor vessel located above the core (separate from the LPCS sparger), and associated system piping , valves, controls, and instrumentation. The system is designed to operate from normal offsite auxiliary power or from a diesel generator supply if offsite power is not available. The P&ID, Fig. 6.3 - 1 for the HPCS, shows the system components and their arrangement.

10f-e e ~12 The principal active HPCS equipment is located outside the primary containment. Suction piping is provided from the condensate storage tank and the suppression pool. Such an arrangement provides the capability to use reactor grade water from the condensate storage tank when the HPCS system functions to back up the RCIC system. In the event that the condensate storage water supply becomes exhausted or is not available, automatic switchover to the suppression pool water source assures a closed cooling water supply for continuous operation of the HPCS system. HPCS pump suction is also automatically transferred to the suppression pool if the suppression pool water level exceeds a prescribed value. The condensate storage tank reserves a maximum of 125,000 gal of water just for use by the HPCS and RCIC.

12f-e After the HPCS injection piping enters the vessel, it divides and enters the shroud at two points near the top of the shroud. A semicircular sparger is attached to each outlet. Nozzles are spaced around the spargers to spray the water radially over the core and into the fuel assemblies.

Revision 12 6.3-13 December 1999

RBG-47854 Enclosure 4 Responses to phone call Clarification Request SR 3.5.2.5 Rev 1

~) EGGS Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2 .~ Verify, for the required High Pressure Core Spray 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (HPCS) System, the:

~ a.

b.

Suppression pool water level is :> 13 ft 3 inches; or Condensate storage tank water level is :> 11 ft 1 inch.

SR 3.5 .2.J Verify, for eaffi required ECCS injection/spray 31 days E!

subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

o SR 3.5 .2.4 ------------------------------ ~JOTE------------------------------

1. GRe low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal , if capable of being manually realigned and not otherwise inoperable.
2. Not required to be met for system t,V",.' '; flow paths opened und tive control.

, for the ------------------------------

~ Verifyeaffi required ECCS injection/spray subsystem 31 days

~---->~ manual, power operated , and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

RIVER BEND 3.5-8 Amendment No. 8+, H~~

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