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Draft Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
	ML16175A394
Person / Time
Site:	Technical Specifications Task Force
Issue date:	10/06/2016
From:	Hsueh K P; Licensing Processes Branch (DPR)
To:	; Technical Specifications Task Force
	Honcharik M C
Shared Package
ML16250A231	List: ML16175A394; ML16250A206;
References
	TAC MF3487
	Download: ML16175A394 (60)
	v • d • e

{{#Wiki_filter:October 6, 2016

Technical Specifications Task Force 11921 Rockville Pike, Suite 100

Rockville, MD 20852

SUBJECT:

DRAFT SAFETY EVALUATION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-542, REVISION 2, "REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL" (TAC NO. MF3487)

Dear Members of the Technical Specifications Task Force:

By letter dated March 14, 2016 (Agencywide Documents Access and Management System Accession No. ML16074A448), the Technical Specifications Task Force submitted to the U.S. Nuclear Regulatory Commission (NRC) for review and approval traveler TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The NRC staff's draft safety evaluation (SE) of the traveler and a draft model SE are enclosed. Thirty calendar days are provided to you to comment on any factual errors or clarity concerns contained in the draft SE. The final SE will be issued after making any necessary changes. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE. To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the draft SE showing proposed changes and provide a summary table of the proposed changes. If you have any questions, please contact Michelle Honcharik at 301-415-1774 or via e-mail at Michelle.Honcharik@nrc.gov. Sincerely, /RA/ Kevin Hsueh, Chief Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Project No. 753

Enclosures:

As stated

cc: See next page

Package: ML16250A231, Cover letter and draft traveler SE: ML16175A394, draft model SE: ML16250A206; *concurred via e-mail NRR-106 OFFICE DPR/PLPB* DPR/PLPB* DSS/SRXB* DSS/STSB* DE/EICB* DORL/BC* NAME MHoncharik DHarrison EOesterle AKlein MWaters DWrona DATE 6/27/16 6/27/16 9/23/16 9/19/16 9/23/16 9/23/16 OFFICE DRA/ARCB* DSS/SBPB* OGC* DPR/PLPB* DPR/PLPB NAME UShoop RDennig DRoth MHoncharik KHsueh DATE 9/23/16 9/22/16 9/21/16 9/26/16 10/6/16 Technical Specifications Task Force Project No. 753

cc: Technical Specifications Task Force c/o EXCEL Services Corporation 11921 Rockville Pike, Suite 100

Rockville, MD 20852

Attention: Brian D. Mann E-mail: brian.mann@excelservices.com

James R. Morris

Diablo Canyon Power Plant Building 104/5/21A P.O. Box 56 Avila Beach, CA 93424

E-mail: JY1E@pge.com

Lisa L. Williams Energy Northwest Columbia Generating Station PO Box 968

Mail Drop PE20 Richland, WA 99352-0968 E-mail: llwilliams@energy-northwest.com Otto W. Gustafson Entergy Nuclear Operations, Inc. Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, MI 49043 E-mail: ogustaf@entergy.com

Michael K. Leisure

Duke Energy

526 S. Church Street Mail Code EC2ZF Charlotte, NC 28202 E-mail: mike.leisure@duke-energy.com

Kelli A. Roberts Southern Nuclear Operating Company 42 Inverness Center Parkway BIN B237 Birmingham, AL 35242-4809 E-mail: kroberts@southernco.com

Enclosure 1 DRAFT SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 1 TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER 2 TSTF-542, REVISION 2 3 "REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL" 4 5

1.0 INTRODUCTION

6 7 By letter dated December 31, 2013 (Agencywide Document Access and Management System 8 (ADAMS) Accession No. ML14002A112), the Technical Specifications (TS) Task Force (TSTF) 9 submitted Change Traveler TSTF-542, "Reactor Pressure Vessel Water Inventory Control," 10 Revision 0, for U.S. Nuclear Regulatory Commission review and approval. By letter dated 11 September 15, 2015, the TSTF submitted Revision 1 to Change Traveler TSTF-542 (ADAMS 12 Accession No. ML15258A850), and by letter dated March 14, 2016, submitted Revision 2 to 13 Change Traveler TSTF 542 (ADAMS Accession No. ML16074A448). Traveler TSTF-542 14 proposes changes to the Standard Technical Specifications (STS) and Bases for boiling water 15 reactor (BWR) designs BWR/4 and BWR/6. 1 The changes would be incorporated into future 16 revisions of NUREG-1433, Volumes 1 and 2 and NUREG-1434, Volumes 1 and 2. 17 18 The proposed changes would replace the existing BWR/4 and BWR/6 Specifications related to 19 "operations with a potential for draining the reactor vessel" (OPDRVs) with revised 20 Specifications for Reactor Pressure Vessel Water Inventory Control (RPV WIC). 21 22 Throughout this safety evaluation (SE), items that are enclosed in square brackets signify 23 plant-specific nomenclature or values. Individual licensees would furnish site-specific 24 nomenclature or values for bracketed items when submitting a license amendment request 25 (LAR) to adopt the changes described in this SE. 26 27 1 U.S. Nuclear Regulatory Commission, "Standard Technical Specifications, General Electric BWR/4 Plants," NUREG-1433, Vol. 1, "Specifications," Rev. 4.0, April 2012, ADAMS Accession No. ML12104A192. U.S. Nuclear Regulatory Commission, "Standard Technical Specifications, General Electric BWR/4 Plants," NUREG-1433, Vol. 2, "Bases," Rev. 4.0, April 2012, ADAMS Accession No. ML12104A193. U.S. Nuclear Regulatory Commission, "Standard Technical Specifications, General Electric BWR/6 Plants," NUREG-1434, Vol. 1, "Specifications," Rev. 4.0, April 2012, ADAMS Accession No. ML12104A195. U.S. Nuclear Regulatory Commission, "Standard Technical Specifications, General Electric BWR/6 Plants," NUREG-1434, Vol. 2, "Bases," Rev. 4.0, April 2012, ADAMS Accession No. ML12104A196.

2.0 REGULATORY EVALUATION

1 2 2.1 TECHNICAL SPECIFICATIONS 3 4 Section IV, "The Commission Policy," of the Fi nal Policy Statement on Technical Specifications 5 Improvements for Nuclear Power Reactors (58 Federal Register 39132), dated July 22, 1993, 6 states in part: 7 8 9 The purpose of Technical Specifications is to impose those 10 conditions or limitations upon reactor operation necessary to 11 obviate the possibility of an abnormal situation or event giving rise 12 to an immediate threat to the public health and safety by 13 identifying those features that are of controlling importance to 14 safety and establishing on them certain conditions of operation 15 which cannot be changed without prior Commission approval. 16 [T]he Commission will also entertain requests to adopt portions of 17 the improved STS [(e.g., TSTF-542)], even if the licensee does 18 not adopt all STS improvements-19 The Commission encourages all licensees who submit Technical 20 Specification related submittals based on this Policy Statement to 21 emphasize human factors principles-22 In accordance with this Policy Statement, improved STS have 23 been developed and will be maintained for [the BWR/4 and 24 BWR/6 designs]. The Commission encourages licensees to use 25 the STS as the basis for plant-specific Technical Specifications-26 [I]t is the Commission intent that the wording and Bases of the 27 improved STS be used [] to the extent practicable. 28 29 30 2.2 SYSTEM DESCRIPTION 31 32 The BWR reactor pressure vessels have a number of penetrations located below the top of 33 active (TAF). These penetrations provide entry for control blades, recirculation flow, and 34 shutdown cooling. Since these penetrations are below the TAF, this gives potential to drain the 35 reactor vessel water inventory and thus lose effective core cooling. The loss of water inventory 36 and effective core cooling can potentially lead to fuel cladding failure and radioactive release. 37 38 During operation in Modes 1 (Power Operation with reactor mode switch position in run), 2 39 (Startup with reactor mode switch position in refuel or startup/hot standby) and 3 (Hot Standby 40 with reactor mode switch position in shutdown), the TS for instrumentation and emergency core 41 cooling systems (ECCS) require operability of sufficient equipment to ensure large quantities of 42 water can be injected into the vessel should level decrease below the preselected value. These 43 requirements are designed to mitigate the effects of a loss-of-coolant accident (LOCA), but also 44 provide protection for other accidents and transients that involve a water inventory loss. 45 46 During BWR operation in Mode 4 (Cold Shutdown with average reactor coolant temperature 1 200 °F), and Mode 5 (Refueling with one or more reactor vessel head closure bolts less than 2 fully tensioned), the pressures and temperatures that could cause a LOCA are not present. 3 During certain phases of refueling (Mode 5) a large volume of water is available above the RPV 4 (i.e., the RPV head is removed, the water level is [23 feet] over the top of the RPV flange, and 5 the spent fuel storage pool gates are removed for BWR/4 plants, or the upper containment pool 6 is connected to the RPV for BWR/6 plants. 7 8 The large volume of water available in and above the RPV (during much of the time when in 9 Mode 5) provides time for operator detection and manual operator action to stop and mitigate an 10 RPV draining event. However, typically at other times during a refueling outage, during cold 11 shutdown (Mode 4) or refueling (Mode 5), there may be a potential for significant drainage paths 12 from certain outage activities, human error, and other events when it is more likely to have some 13 normally available equipment, instrumentation, and systems inoperable due to maintenance and 14 outage activities. There may not be as much time for operator action as compared to times 15 when there are large volumes of water above the RPV. 16 17 In comparison to Modes 1, 2, and 3, with typical high temperatures and pressures (especially in 18 Modes 1 and 2), Modes 4 and 5 generally do not have the high pressure and temperature 19 considered necessary for a LOCA envisioned from a high energy pipe failure. Thus, while the 20 potential sudden loss of large volumes of water from a LOCA are not expected, operators 21 monitor for BWR RPV water level decrease from potential significant or even unexpected 22 drainage paths. These potential drainage paths in Modes 4 and 5 generally would require less 23 water replacement capability to maintain water above TAF. 24 25 To address the drain down potential during Modes 4 and 5, the current BWR STS contain 26 specifications that are applicable during an OPDRV, or require suspension of OPDRVs if certain 27 equipment is inoperable. The term OPDRV is not specifically defined in the TS and historically 28 has been subject to inconsistent application by licensees. The changes discussed in this SE 29 are intended to resolve any ambiguity by creating a new RPV water inventory control TS with 30 attendant equipment operability requirements, required actions and surveillance requirements 31 (SR) and deleting references to OPDRVs throughout the TS. 32 33 2.3 CHANGES TO THE STS 34 35 The proposed changes would (1) provide a definition of a new term, DRAIN TIME; (2) revise 36 and rename STS 3.5.2 as "Reactor Pressure Vessel Water Inventory Control;" (3) provide a new 37 TS 3.3.5.2, "Reactor Pressure Vessel Water Inventory Control Instrumentation;" and (4) delete 38 existing references to "operations with the potential to drain the reactor pressure vessel" 39 throughout the STS. The descriptions of the proposed changes are provided in this section. 40 41 Corresponding changes are proposed to the STS Bases. A summary of the revised STS Bases 42 and the staff's evaluation of the revised Bases are provided in an attachment of this SE. 43 44 2.3.1 Insertion of New Definition of DRAIN TIME 45 46 The following definition of "DRAIN TIME" would be added to Section 1.1, "Definitions" Section of 47 the STS: 48 49 1 The DRAIN TIME is the time it would take for the water inventory 2 in and above the Reactor Pressure Vessel (RPV) to drain to the 3 top of the active fuel (TAF) seated in the RPV assuming: 4 5 a) The water inventory above the TAF is divided by the limiting 6 drain rate; 7 8 b) The limiting drain rate is the larger of the drain rate through a 9 single penetration flow path with the highest flow rate, or the 10 sum of the drain rates through multiple penetration flow paths 11 susceptible to a common mode failure (e.g., seismic event, 12 loss of normal power, single human error), for all penetration 13 flow paths below the TAF except: 14 15 1. Penetration flow paths connected to an intact closed 16 system, or isolated by manual or automatic valves are 17 locked, sealed, or otherwise secured in the closed position, 18 blank flanges, or other devices that prevent flow or reactor 19 coolant through the penetration flow paths; 20 21 2. Penetration flow paths capable of being isolated by valves 22 that will close automatically without offsite power prior to 23 the RPV water level being equal to the TAF when actuated 24 by RPV water level isolation instrumentation; or 25 26 3. Penetration flow paths with isolation devices that can be 27 closed prior to the RPV water level being equal to the TAF 28 by a dedicated operator trained in the task, who is in 29 continuous communication with the control room, is 30 stationed at the controls, and is capable of closing the 31 penetration flow path isolation device without offsite power. 32 33 c) The penetration flow paths required to be evaluated per 34 paragraph b) are assumed to open instantaneously and are 35 not subsequently isolated, and no water is assumed to be 36 subsequently added to the RPV water inventory; 37 38 d) No additional draining events occur; and 39 40 e) Realistic cross-sectional areas and drain rates are used. 41 42 A bounding DRAIN TIME may be used in lieu of a calculated 43 value. 44 45 46 2.3.2 Changes to STS Section 3.5: 47 48 2.3.2.1 Title of TS 3.5 49 1 The title of Section 3.5 is being revised from "Emergency Core Cooling System (ECCS) and 2 Reactor Core Isolation Cooling System (RCIC)" to "Emergency Core Cooling Systems (ECCS), 3 RPV Water Inventory Control, and Reactor Core Isolation Cooling (RCIC) System." 4 5 2.3.2.2 Title of TS 3.5.2 6 7 The title of TS 3.5.2 is being revised from "ECCS - Shutdown" to "Reactor Pressure Vessel 8 (RPV) Water Inventory Control." 9 10 2.3.2.3 LCO 3.5.2 11 12 STS limiting condition for operation (LCO) 3.5.2 currently states "Two low pressure ECCS 13 injection/spray subsystems shall be OPERABLE." The LCO note currently states: "One LPCI 14 subsystem may be considered OPERABLE during alignment and operation for decay heat 15 removal if capable of being manually realigned and not otherwise inoperable." 16 17 STS LCO 3.5.2 for NUREG-1433 (BWR/4 STS) would be revised to state: 18 19 20 DRAIN TIME of RPV water inventory to the top of active fuel 21 (TAF) shall be 36 hours. 22 23 AND 24 25 One low pressure ECCS injection/spray subsystem shall be 26 OPERABLE. 27 28 29 The note for LCO 3.5.2 would be revised to state: 30 31 32 A Low Pressure Coolant Injection (LPCI) subsystem may be 33 considered OPERABLE during alignment and operation for decay 34 heat removal if capable of being manually realigned and not 35 otherwise inoperable. 36 37 38 For NUREG-1434 (BWR/6) STS, the phrase "low pressure" is omitted because the BWR/6 high 39 pressure core spray system may be used to satisfy this requirement. 40 41 2.3.2.4 Applicability of TS LCO 3.5.2 42 43 For NUREG-1433 (BWR/4), LCO 3.5.2 is currently applicable in MODE 4 and in MODE 5, 44 except with the spent fuel storage pool gates removed and water level [23 ft] over the top of 45 the reactor pressure vessel flange. 46 47 For NUREG-1434 (BWR/6), LCO 3.5.2 is currently applicable in Mode 4 and Mode 5 except 1 with the upper containment [cavity to dryer] pool [gate] removed and water level [22 ft 2 8 inches] over the top of the reactor pressure vessel flange. 3 4 The applicability would be revised to be MODES 4 and 5, with no exceptions. 5 6 2.3.2.5 Actions Table of TS 3.5.2 7 8 The existing Actions Table of TS 3.5.2 for NUREG-1433 (BWR/4) states: 9 10 CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCS injection/spray subsystem inoperable. A.1 Restore required ECCS injection/spray subsystem to OPERABLE status. 4 hours B. Required Action and associated Completion

Time of Condition A not met B.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). Immediately C. Two required ECCS injection/spray subsystems inoperable. C.1 Initiate action to suspend OPDRVs AND C.2 Restore one ECCS injection/spray subsystem to OPERABLE status Immediately

4 hours D. Required Action C.2 and associated Completion Time not met D.1 Initiate action to restore [secondary] containment to OPERABLE status.

AND D.2 [Initiate action to restore one standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to restore isolation capability in each required

[secondary] containment penetration flow path not isolated. Immediately

Immediately]

Immediately 11 The revised TS 3.5.2 Actions Table for NUREG-1433 (BWR/4) would state: 12 13 CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS injection/spray subsystem inoperable. A.1 Restore required ECCS injection/spray subsystem to OPERABLE status. 4 hours B. Required Action and associated Completion

Time of Condition A not met. B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power. Immediately C. DRAIN TIME < 36 hours and 8 hours. C.1 Verify [secondary] containment boundary is capable of being established in less than the DRAIN TIME.

AND C.2 Verify each [secondary] containment penetration flow path is capable of being isolated in less than the DRAIN TIME. AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME. 4 hours

4 hours

4 hours D. DRAIN TIME < 8 hours. D.1 --------------NOTE------------ Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power. ----------------------------------

Initiate action to establish an

additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.

AND D.2 Initiate action to establish [secondary] containment boundary AND D.3 Initiate action to isolate each [secondary] containment penetration flow path or verify it can be manually isolated from the

control room.

Immediately

AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.

Immediately E. Required Action and associated Completion

Time of Condition C or D not met. OR DRAIN TIME < 1 hour E.1 Initiate action to restore DRAIN TIME to 36 hours Immediately 1 The existing Actions Table of TS 3.5.2 for NUREG-1434 (BWR/6) states: 2 3 CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCS injection/spray subsystem inoperable. A.1 Restore required ECCS injection/spray subsystem to OPERABLE status. 4 hours B. Required Action and associated Completion Time of Condition A not met B.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). Immediately C. Two required ECCS injection/spray subsystems inoperable. C.1 Initiate action to suspend OPDRVs AND C.2 Restore one ECCS injection/spray subsystem to OPERABLE status Immediately

4 hours D. Required Action C.2 and associated Completion Time not met D.1 Initiate action to restore [secondary containment] to OPERABLE status. AND D.2 [Initiate action to restore one standby gas treatment subsystem to OPERABLE status. AND Immediately

Immediately]

Immediately D.3 Initiate action to restore isolation capability in each required [secondary containment] penetration flow path not isolated. 1 The revised TS 3.5.2 ACTIONS Table for NUREG-1434 (BWR/6) would state: 2 3 CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS injection/spray subsystem inoperable. A.1 Restore required ECCS injection/spray subsystem to OPERABLE status. 4 hours B. Required Action and associated Completion

Time of Condition A not met. B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.. Immediately C. DRAIN TIME < 36 hours and 8 hours. C.1 Verify [secondary containment] boundary is capable of being established in less than the DRAIN TIME.

AND C.2 Verify each [secondary containment] penetration flow path is capable of being isolated in less than the DRAIN TIME. AND C.3 [Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME. 4 hours

4 hours

4 hours] D. DRAIN TIME < 8 hours. D.1 --------------NOTE------------ Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.

Initiate action to establish an

additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.

Immediately

AND D.2 Initiate action to establish [secondary containment] boundary AND D.3 Initiate action to isolate each [secondary containment] penetration flow path or verify it can be manually isolated from the control room. AND D.4 [Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.

Immediately

Immediately] E. Required Action and associated Completion Time of Condition C or D

not met.

OR DRAIN TIME < 1 hour E.1 Initiate action to restore DRAIN TIME to 36 hours. Immediately 1 2.3.2.6 TS 3.5.2 Surveillance Requirements 2 3 The NUREG-1433 (BWR/4) TS 3.5.2 currently contains the following SRs: 4 5 SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure coolant injection (LPCI) subsystem, the suppression pool

water level is [12 ft 2 inches]. [12 hours

OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.2 Verify, for each required core spray (CS) subsystem, the:

a. Suppression pool water level is [12 ft 2 inches] or

[12 hours

OR In accordance with the Surveillance Frequency Control Program] b. ------------------------------NOTE-------------------------------------Only one required CS subsystem may take credit for this option during OPDRVs. Condensate storage tank water level is [12 ft].SR 3.5.2.3 Verify, for each required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. [31 days OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.4 Verify each required ECCS injection/spray subsystem 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. [31 days OR In accordance with the

Surveillance Frequency Control Program] 1 The revised SRs for NUREG-1433 (BWR/4) would be: 2 3 SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours. [12 hours OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.2 Verify, for a required low pressure ECCS injection/spray subsystem, the suppression pool water level is [12 ft 2 inches]. [12 hours OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.3 Verify, for a required Core Spray (CS) System, the:

a. Suppression pool water level is [12 ft 2 inches] or

b. Condensate storage tank water level is [12 ft].

[12 hours OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.4 Verify, for the required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. [31 days OR In accordance with the Surveillance Frequency Control Program] SR 3.5.2.5 Verify, for the required ECCS injection/spray subsystem each 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. [31 days OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.6 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes. [92 days OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal. [[18] months OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.8 --------------------------------------NOTE-----------------------Vessel injection/spray may be excluded. --------------------------------------------------------------------- Verify the required ECCS injection/spray subsystem actuates on a manual initiation signal. [[18] months OR In accordance with the

Surveillance Frequency Control Program ] 1 The corresponding NUREG-1434 (BWR/6) TS 3.5.2 currently contains the following SRs: 2 3 SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure ECCS injection/spray subsystem, the suppression pool water level is [12.67 ft]. [12 hours OR In accordance with the

Surveillance

Frequency Control Program] SR 3.5.2.2 Verify, for the required High Pressure Core Spray (HPCS) subsystem, the:

a. Suppression pool water level is [12.67 ft] or

[12 hours OR     b. Condensate storage tank water level is  [18 ft] In accordance with the Surveillance

Frequency Control Program] SR 3.5.2.3 Verify, for the required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. [31 days OR In accordance with the

Surveillance Frequency Control Program] SR 3.5.2.4 Verify each required ECCS injection/spray subsystem 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. [31 days OR In accordance with the Surveillance Frequency Control Program] SR 3.5.2.5 Verify each required ECCS pump develops the specified flow rate [against a system head corresponding to the specified reactor pressure] System Flow Rate [System Head Corresponding to A Reactor Pressure of] LPCS [7115]gpm [290]psig LPCI [7450]gpm [125]psig HPCS [7115]gpm [445]psig [In accordance with the Inservice Testing Program

OR [92 days]

OR In accordance with the Surveillance

Frequency Control Program] SR 3.5.2.6 ------------------------------------NOTE--------------------------- Vessel injection/spray may be excluded.

Verify each required ECCS injection /spray subsystem actuates on an actual or simulated automatic initiation signal. [18 months

OR In accordance with the

Surveillance

Frequency Control Program] 1 The revised SRs for NUREG-1434 (BWR/6) would be: 2 3 SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours. [12 hours OR In accordance with the Surveillance Frequency Control Program] SR 3.5.2.2 Verify, for a required low pressure ECCS injection/spray subsystem, the suppression pool

water level is [12.67 ft]. [12 hours

OR In accordance with the Surveillance

Frequency Control Program] SR 3.5.2.3 Verify, for a required High Pressure Core Spray (HPCS) System, the:

c. Suppression pool water level is [12.67 ft] or

d. Condensate storage tank water level is [18 ft].

[12 hours

OR In accordance with the

Surveillance

Frequency Control Program] SR 3.5.2.4 Verify, for the required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. [31 days OR In accordance with the

Surveillance

Frequency Control Program] SR 3.5.2.5 Verify, for the required ECCS injection/spray subsystem each 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. [31 days OR In accordance with the

Surveillance

Frequency Control Program] SR 3.5.2.6 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes. [92 days OR In accordance with the

Surveillance

Frequency Control Program] SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal. [[18] months

OR In accordance with the

Surveillance

Frequency Control Program] SR 3.5.2.8 --------------------------------------NOTE------------------------- Vessel injection/spray may be excluded. ----------------------------------------------------------------------- Verify the required ECCS injection/spray subsystem actuates on a manual initiation signal. [[18] months OR In accordance with the

Surveillance

Frequency Control Program] 1 2.3.3 Changes to STS Section 3.3 2 3 Both NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6) STS contain two versions of certain 4 specifications in Section 3.3, Instrumentation. One is applicable for licensees that have not 5 adopted a Setpoint Control Program (the "A" version) and the other is applicable for licensees 6 that have adopted a Setpoint Control Program (the "B" version). In the "A" version of the STS, 7 the Allowable Value column is retained in the Instrumentation Table, and the Instrumentation 8 Table contains footnotes that provide details regarding SRs. In the "B" version of the STS, the 9 Allowable Value has been relocated to the Setpoint Control Program, and this column does not 10 appear in the Instrumentation Table. Additionally, in the "B" version, the footnotes that provide 11 details regarding SRs are not necessary. This convention is retained in the revised STS LCOs 12 discussed in this section. 13 14 For simplicity, the description of changes in this section is presented with the A and B versions 15 combined. 16 17 2.3.3.1 Changes to STS LCOs 3.3.5.1A and 3.3.5.1B, Emergency Core Cooling System 18 (ECCS) Instrumentation (Without and With Setpoint Control Program), 19 respectively 20 21 The STS LCOs 3.3.5.1A and 3.3.5.1B state that "the ECCS instrumentation for each Function in 22 Table 3.3.5.1-1, [Emergency Core Cooling System Instrumentation,] shall be OPERABLE" with 23 the applicability as stated in the table. Table 3.3.5.1-1 currently contains requirements for 24 function operability during Modes 4 and 5 when associated ECCS subsystem(s) are required to 25 be operable per LCO 3.5.2, "ECCS - Shutdown." Throughout this table, the applicability in 26 Modes 4 and 5 is being deleted because the instrumentation requirements during shutdown are 27 being consolidated into the new STS 3.3.5.2. Conforming changes are made to the ACTIONS 28 Table of STS LCO 3.3.5.1A and 3.3.5.1B. 29 30 2.3.3.2 Insertion of new STS 3.3.5.2A and 3.3.5.2B, Reactor Pressure Vessel (RPV) 31 Water Inventory Control Instrumentation (Without and With Setpoint Control 32 Program), respectively 33 1 A new STS 3.3.5.2 is proposed to provide alternative instrumentation requirements to support 2 manual initiation of the ECCS injection/spray subsystem required in new STS 3.5.2 and 3 automatic isolation of penetration flow paths that may be credited in the determination of drain 4 time. The current TS contain instrumentation requirements related to OPDRVs in four TS. 5 These requirements are being consolidated into new STS 3.3.5.2. 6 7 The existing STS 3.3.5.2, "Reactor Core Isolation Cooling (RCIC) System Instrumentation," is 8 being renumbered to 3.3.5.3 in order to maintain the STS numbering conventions in the 9 NUREGs. 10 11 2.3.3.2.1 New TS 3.3.5.2A and B LCO and Applicability 12 13 The proposed LCO 3.3.5.2 states: 14 15 16 The RPV Water Inventory Control instrumentation for each 17 Function in Table 3.3.5.2-1 shall be OPERABLE. 18 19 20 The applicability states, "According to Table 3.3.5.2-1." 21 22 The following sections describe the instrumentation functions contained in the new 23 Table 3.3.5.2-1. 24 25 2.3.3.2.2 BWR/4 New Table 3.3.5.2-1, RPV Water Inventory Control Instrumentation 26 27 2.3.3.2.2.1 Function 1.a, Core Spray System, Reactor Steam Dome Pressure - Low 28 (Injection Permissive), and 29 Function 2.a, Low Pressure Coolant Injection (LPCI) System, Reactor Steam 30 Dome Pressure - Low (Injection Permissive) 31 32 These functions were moved from current STS 3.3.5.1, Function 1.c and Function 2.c. The 33 following changes are made: 34 35

The applicability is changed. The existing STS 3.3.5.1 applicability for these functions in 36 Modes 4 and 5 is modified by a note that limits the applicability to when the associated 37 ECCS subsystem(s) are required to be operable per LCO 3.5.2, "ECCS - Shutdown." The 38 revised applicability is Modes 4 and 5 without exception, to be consistent with the 39 applicability of new LCO 3.5.2, "RPV Water Inventory Control." 40 41
The number of required channels per function is unchanged.

42 43

In the new table, a Channel Check and Channel Functional Test are required at the existing 44 frequency. Calibration of the trip units, Channel Calibration, Logic System Functional Test, 45 and ECCS Response Time tests are no longer required in Modes 4 and 5.

46 47

In new LCO 3.3.5.2A, the Allowable Value is revised to eliminate the low pressure limit and 1 to retain the high pressure limit. The RPV is well below the lower limit in Modes 4 and 5, so 2 the low pressure limit is not needed.

3 4 2.3.3.2.2.2 Function 1.b, Core Spray Pump Discharge Flow - Low (Bypass) and 5 Function 2.b, Low Pressure Coolant Injection Pump Discharge Flow - Low 6 (Bypass) 7 8 These functions were moved from current STS 3.3.5.1, Function 1.d and Function 2.g, 9 respectively. The following changes are made: 10 11

The applicability is changed. The current STS 3.3.5.1 applicability for these functions in 12 Modes 4 and 5 is modified by a note that limits the applicability to when the associated 13 ECCS subsystem(s) are required to be operable per current LCO 3.5.2, "ECCS -

14 Shutdown." The revised applicability is Modes 4 and 5 without exception, to be consistent 15 with the applicability of new LCO 3.5.2, "RPV Water Inventory Control." 16 17

For Function 1.b, the number of required channels per function is changed from [2] or [1 per 18 pump], to [1 per pump]. For Function 2.b, the number of required channels per function is 19 changed from [4] or [1 per pump], to [1 per pump]. Both are modified by a note stating 20 "Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, 'Reactor 21 Pressure Vessel Water Inventory Control.'"

22 23

In the new table, a Channel Check and Channel Functional Test are required at the existing 24 frequency. A Channel Calibration and Logic System Functional Test are no longer required 25 in Modes 4 and 5.

26 27

In new LCO 3.3.5.2A, the allowable value is unchanged.

28 29 2.3.3.2.2.3 Function 1.c, Core Spray System, Manual Initiation, and 30 Function 2.c, Low Pressure Coolant Injection (LPCI) System, Manual Initiation 31 32 These functions were moved from current STS 3.3.5.1, Function 1.e and Function 2.h. The 33 following changes are made: 34 35

The applicability is changed. The current STS 3.3.5.1 applicability for these functions in 36 Modes 4 and 5 is modified by a note that limits the applicability to when the associated 37 ECCS subsystem(s) are required to be operable per current LCO 3.5.2, "ECCS -

38 Shutdown." The revised applicability is Modes 4 and 5 without exception, to be consistent 39 with the applicability of new LCO 3.5.2, "RPV Water Inventory Control." 40 41

The number of required channels per function is changed from [2] or [1 per subsystem], to 42 [1 per subsystem] and is modified by a note stating "Associated with an ECCS subsystem 43 required to be OPERABLE by LCO 3.5.2, 'Reactor Pressure Vessel Water Inventory 44 Control.'" New LCO 3.5.2 only requires a single ECCS subsystem and the change in 45 required channels reflects that requirement.

46 47

Both the existing STS 3.3.5.1 and the revised STS 3.3.5.2 require a Logic System 1 Functional Test on this function at the same frequency.

2 3

There is no allowable value for this function.

4 5 2.3.3.2.2.4 Function 3.a, RHR System Isolation, Reactor Vessel Water Level - Low, Level 3 6 7 This function was moved from current STS 3.3.6.1, Function 6.b. The following changes are 8 made: 9 10

The function name is changed from "Shutdown Cooling System Isolation Reactor Vessel 11 Water Level - Low, Level 3" to "Residual Heat Removal [RHR] System Isolation Reactor 12 Vessel Water Level - Low, Level 3." The current title is a misnomer in the STSs as the 13 Level 3 instruments isolate more than shutdown cooling isolation valves.

14 15

The applicability is changed. The existing STS 3.3.6.1 applicability for this function in 16 Modes 4 and 5 is being deleted. The revised applicability is "when automatic isolation of the 17 associated penetration flow path is credited in calculating Drain Time." 18 19
The number of required channels is changed from [2], with a column header that states 20 "Required Channels per Trip System," to [2 in one trip system]. This retains the requirement 21 that the two channels must be associated with the same trip system.

22 23

In the new table, a Channel Check and Channel Functional Test are required at the existing 24 frequency. A calibration of the trip unit, Channel Calibration, and Logic System Functional 25 Test are no longer required in Modes 4 and 5.

26 27

The allowable value is unchanged.

28 29 2.3.3.2.2.5 Function 4.a, Reactor Water Cleanup (RWCU) System Isolation, Reactor Vessel 30 Water Level - Low Low, Level 2 31 32 This function exists in the current STS 3.3.6.1 as Function 5.e. The function is inserted into 33 new STS 3.3.5.2 as follows: 34 35

The applicability of the current STS 3.3.6.1 for this function is Modes 1, 2, and 3. The 36 applicability in STS 3.3.5.2 is "when automatic isolation of the associated penetration flow 37 path is credited in calculating Drain Time." In other words, if the drain time calculation 38 assumes the RWCU system will be automatically isolated, this function must be operable to 39 perform that function. This is consistent with the definition of drain time and the TS 3.5.2 40 requirements.

41 42

The number of required channels is changed from [2], with a column header that states 43 "Required Channels per Trip System," to [2 in one trip system]. This retains the requirement 44 that the two channels must be associated with the same trip system. Only one trip system is 45 required to ensure that automatic isolation of one of the two isolation valves will occur on 46 low reactor vessel water level.

47 48

A Channel Check and Channel Functional Test are required at the existing frequency. A 1 calibration of the trip unit, Channel Calibration, Logic System Functional Test, and Isolation 2 System Response Time tests are no longer required in Modes 4 and 5.

3 4

The allowable value is unchanged.

5 6 2.2.3.2.3 BWR/6 New Table 3.3.5.2-1, RPV Water Inventory Control Instrumentation 7 8 2.3.3.2.3.1 Function 1.a, Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core 9 Spray (LPCS) Subsystems, Reactor Steam Dome Pressure - Low (Injection 10 Permissive) and 11 Function 2.a, LPCI B and LPCI C Subsystems, Reactor Steam Dome Pressure - 12 Low (Injection Permissive) 13 14 These functions were moved from current STS 3.3.5.1, Function 1.d and Function 2.d. The 15 following changes are made: 16 17

The applicability is changed. The current STS 3.3.5.1 applicability for these functions in 18 Modes 4 and 5 is modified by a note that limits the applicability to when the associated 19 ECCS subsystem(s) are required to be operable per current LCO 3.5.2, "ECCS -

20 Shutdown." The revised applicability is Modes 4 and 5 without exception, to be consistent 21 with the applicability of new LCO 3.5.2, "RPV Water Inventory Control." Note that the 22 BWR/6 STS does not include the Mode 4 and 5 applicability of this function. This apparently 23 was an oversight in development of the NUREG. 24 25

In the new table, the number of required channels per function remains [3] and is modified 26 by a note stating "Associated with an ECCS subsystem required to be OPERABLE by 27 LCO 3.5.2, 'Reactor Pressure Vessel Water Inventory Control.'" New STS 3.5.2 only 28 requires a single ECCS subsystem to be operable and the change reflects that requirement.

29 30

A Channel Check and Channel Functional Test are required at the existing frequency.

31 Calibration of the trip units, Channel Calibration, Logic System Functional Test, and ECCS 32 Response Time tests are no longer required in Modes 4 and 5. 33 34

In new LCO 3.3.5.2A, the allowable value is revised to eliminate the low pressure limit and 35 to retain the high pressure limit.

36 37 2.3.3.2.3.2 Functions 1.b and 1.c, Low Pressure Coolant Injection-A (LPCI) and Low 38 Pressure Core Spray (LPCS) Subsystems, LPCS Pump Discharge Flow - Low 39 (Bypass) and LPCI Pump A Discharge Flow - Low (Bypass), and 40 Function 2.b, LPCI B and LPCI C Subsystems, LPCI Pump B and LPCI Pump C 41 Discharge Flow - Low (Bypass) 42 43 These functions were moved from current STS 3.3.5.1, Function 1.e, 1.f, and 2.e. The following 44 changes are made: 45 46

The applicability is changed. The current STS 3.3.5.1 applicability for these functions is 47 Modes 4 and 5 when the associated ECCS subsystem(s) are required to be operable per 48 LCO 3.5.2, "ECCS - Shutdown." The revised Applicability is Modes 4 and 5 without 1 exception, to be consistent with the Applicability of new LCO 3.5.2, "RPV Water Inventory 2 Control." 3 4
The number of required channels per function is changed from [1] to [1 per pump] and is 5 modified by a note stating "Associated with an ECCS subsystem required to be OPERABLE 6 by LCO 3.5.2, 'Reactor Pressure Vessel Water Inventory Control'." New STS 3.5.2 only 7 requires a single ECCS subsystem and the change in required channels reflects that 8 requirement.

9 10

A Channel Check and Channel Functional Test are required at the existing frequency.

11 Calibrating the trip unit, Channel Calibration and Logic System Functional Test are no longer 12 required in Modes 4 and 5. 13 14

In new LCO 3.3.5.2A, the allowable value is unchanged.

15 16 2.3.3.2.3.3 Function 1.d, Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core 17 Spray (LPCS) Subsystems, Manual Initiation, and Function 2.c, LPCI B and LPCI 18 C Subsystems, Manual Initiation 19 20 These functions were moved from current STS 3.3.5.1, Function 1.g and Function 2.f. The 21 following changes are made: 22 23

The applicability is changed. The current STS 3.3.5.1 Applicability for these Functions in 24 Modes 4 and 5 is modified by a note that limits the applicability to when the associated 25 ECCS subsystem(s) are required to be operable per current LCO 3.5.2, "ECCS -

26 Shutdown." The revised applicability is Modes 4 and 5 without exception, to be consistent 27 with the applicability of new LCO 3.5.2, "RPV Water Inventory Control." 28 29

The number of required channels per function is changed from [1] to [1 per subsystem] and 30 is modified by a note stating "Associated with an ECCS subsystem required to be 31 OPERABLE by LCO 3.5.2, 'Reactor Pressure Vessel Water Inventory Control'." New 32 STS 3.5.2 only requires a single ECCS subsystem and the change in required channels 33 reflects that requirement.

34 35

Both the existing STS 3.3.5.1 and the revised STS 3.3.5.2 require a Logic System 36 Functional Test on this function at the same frequency.

37 38

There is no allowable value for this function.

39 40 2.3.3.2.3.4 Function 3.a, High Pressure Core Spray (HPCS) System, Reactor Vessel Water 41 Level - High, Level 8 42 43 This function was moved from current STS 3.3.5.1, Function 3.c. The following changes are 44 made: 45 46

The applicability is changed. The current STS 3.3.5.1 applicability for this function is 47 Modes 4 and 5 when the associated ECCS subsystem(s) are required to be operable per 48 existing LCO 3.5.2, "ECCS - Shutdown." The revised applicability is Modes 4 and 5 without 1 exception, to be consistent with the applicability of new LCO 3.5.2, "RPV Water Inventory 2 Control." 3 4
The number of required channels per function is changed from [2] to [1] and is modified by a 5 note stating "Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, 6 'Reactor Pressure Vessel Water Inventory Control'." New STS 3.5.2 only requires a single 7 ECCS subsystem and the change in required channels reflects that requirement.

8 9

A Channel Check and Channel Functional Test are required at the existing frequency.

10 Calibration of the trip units, Channel Calibration, and Logic System Functional Test tests are 11 no longer required in Modes 4 and 5. 12 13

The allowable value in new LCO 3.3.5.2A is unchanged.

14 15 2.3.3.2.3.5 Function 3.b, High Pressure Core Spray (HPCS) System, Condensate Storage 16 Tank Level - Low 17 18 This function was moved from current STS 3.3.5.1, Function 3.d. The following changes are 19 made: 20 21

The applicability is changed. The current STS 3.3.5.1 applicability for this function is 22 Modes 4 and 5 when the associated ECCS subsystem(s) are required to be operable per 23 current LCO 3.5.2, "ECCS - Shutdown." The revised applicability is Modes 4 and 5 when 24 HPCS is operable for compliance with new LCO 3.5.2 and aligned to the Condensate 25 Storage Tank. If HPCS is not being credited for meeting the new LCO 3.5.2 requirement for 26 an operable ECCS subsystem, or if HPCS is being credited but is aligned to the suppression 27 pool, this function is unneeded.

28 29

The number of required channels per function is changed from [2] to [1]. New STS 3.5.2 30 only requires a single ECCS subsystem to be operable, and the change in required 31 channels reflects that requirement.

32 33

A Channel Check and Channel Functional Test are required at the existing frequency.

34 Calibration of the trip units, Channel Calibration, and Logic System Functional Test are no 35 longer required in Modes 4 and 5. 36 37

The allowable value in new LCO 3.3.5.2A is unchanged.

38 39 2.3.3.2.3.6 Functions 3.c and 3.d, High Pressure Core Spray (HPCS) System, HPCS Pump 40 Discharge Pressure - High (Bypass) and HPCS System Flow Rate - Low 41 (Bypass) 42 43 These functions were moved from current STS 3.3.5.1, Function 3.f and 3.g. The following 44 changes are made: 45 46

The applicability is changed. The current STS 3.3.5.1 applicability for this function is 47 Modes 4 and 5 when the associated ECCS subsystem(s) are required to be operable per 48 current LCO 3.5.2, "ECCS - Shutdown." The revised applicability is Modes 4 and 5 without 1 exception, to be consistent with the applicability of new LCO 3.5.2, "RPV Water Inventory 2 Control." 3 4
The number of required channels per function is changed from [1] to [1 per pump] and is 5 modified by a note stating "Associated with an ECCS subsystem required to be OPERABLE 6 by LCO 3.5.2, 'Reactor Pressure Vessel Water Inventory Control'." New STS 3.5.2 only 7 requires a single ECCS subsystem and the change in required channels reflects that 8 requirement.

9 10

A Channel Check and Channel Functional Test are required at the existing frequency.

11 Calibration of the trip units, Channel Calibration, and Logic System Functional Test are no 12 longer required in Modes 4 and 5. 13 14

The allowable value is unchanged.

15 16 2.3.3.2.3.7 Function 3.e, High Pressure Core Spray (HPCS) System, Manual Initiation 17 18 This function is moved from current STS 3.3.5.1, Function 3.h. The following changes are 19 made: 20 21

The applicability is changed. The current STS 3.3.5.1 applicability for these functions in 22 Modes 4 and 5 is modified by a note that limits the applicability to when the associated 23 ECCS subsystem(s) are required to be operable per existing LCO 3.5.2, "ECCS -

24 Shutdown." The revised applicability is Modes 4 and 5 without exception, to be consistent 25 with the applicability of new LCO 3.5.2, "RPV Water Inventory Control." 26 27

The number of required channels per function is changed from [1] to [1 per subsystem] and 28 is modified by a note stating "Associated with an ECCS subsystem required to be 29 OPERABLE by LCO 3.5.2, 'Reactor Pressure Vessel Water Inventory Control'." New 30 STS 3.5.2 only requires a single ECCS subsystem and the change in required channels 31 reflects that requirement.

32

Both the existing STS 3.3.5.1 and the revised STS 3.3.5.2 require a Logic System 33 Functional Test on this function at the same frequency.

34 35

There is no allowable value for this function.

36 37 2.3.3.2.3.8 Function 4.a, RHR System Isolation Reactor Vessel Water Level - Low, Level 3 38 39 This function was moved from current STS 3.3.6.1, Function 5.c. The following changes are 40 made: 41 42

The function name is changed from "Shutdown Cooling System Isolation Reactor Vessel 43 Water Level - Low, Level 3" to "Residual Heat Removal System Isolation Reactor Vessel 44 Water Level - Low, Level 3." This is a misnomer in the STSs as the Level 3 instruments 45 isolate more than shutdown cooling isolation valves.

46 47

The applicability is changed. The current STS 3.3.6.1 applicability for this function is 1 Modes 4 and 5. The revised applicability is "when automatic isolation of the associated 2 penetration flow path is credited in calculating drain time.

3 4

The number of required channels is changed from [2], with a column header that states 5 "Required Channels per Trip System," to [2 in one trip system]. This retains the requirement 6 that the two channels must be associated with the same trip system. Only one trip system is 7 required to ensure automatic isolation of one of the two isolation valves will occur on low 8 reactor vessel water level.

9 10

A Channel Check and Channel Functional Test are required at the existing frequency. A 11 calibration of the trip unit, Channel Calibration, Logic System Functional Test, and Isolation 12 System Response Time tests are no longer required in Modes 4 and 5.

13 14

The existing allowable value is retained in new STS 3.3.5.2.

15 16 2.3.3.2.3.9 Function 5.a, Reactor Water Cleanup (RWCU) System Isolation, Reactor Vessel 17 Water Level - Low Low, Level 2 18 19 This function exists in the current STS 3.3.6.1 as Function 4.k. The function is inserted into 20 new STS 3.3.5.2 as follows: 21 22

The applicability of the current STS 3.3.6.1 Function 4.k is Modes 1, 2, and 3. The 23 applicability in STS 3.3.5.2 is "when automatic isolation of the associated penetration flow 24 path is credited in calculating Drain Time." In other words, if the drain time calculation 25 assumes the RWCU system would be automatically isolated, this function must be operable 26 to perform that function. This is consistent with the definition of drain time and the new 27 STS 3.5.2 requirements.

28 29

The number of required channels is changed from [2], with a column header that states 30 "Required Channels per Trip System," to [2 in one trip system]. This retains the requirement 31 that the two channels must be associated with the same trip system. Only one trip system is 32 required to ensure that automatic isolation of one of the two isolation valves will occur on 33 low reactor vessel water level.

34 35

A Channel Check and Channel Functional Test are required at the existing frequency. A 36 calibration of the trip unit, Channel Calibration, Logic System Functional Test, and Isolation 37 System Response Time tests are no longer required in Modes 4 and 5.

38 39

The existing allowable value is retained in LCO 3.3.5.2A.

40 41 2.3.3.2.4 New TS 3.3.5.2A and B ACTIONS Table 42 43 Condition A is applicable when one or more instrument channels are inoperable from 44 Table 3.3.5.2-1. Required Action A.1 directs immediate entry into the condition referenced in 45 Table 3.3.5.2-1 for that channel. 46 47 Condition B is entered when the RHR system isolation and RWCU system isolation functions 1 operability requirements are not met when automatic isolation of the associated penetration flow 2 path is credited in calculating drain time. If the instrumentation is inoperable, Required 3 Action B.1 directs an immediate declaration that the associated penetration flow path(s) are 4 incapable of automatic isolation. Required Action B.2 requires an immediate calculation of drain 5 time. 6 7 Condition C is entered when the Low Reactor Steam Dome Pressure Injection Permissive 8 Functions necessary for ECCS subsystem manual initiation operability requirements are not 9 met. The channel must be placed in the trip condition within one hour. 10 11 For BWR/4s, Condition D is entered when the operability requirements for the Core Spray Pump 12 Discharge Flow - Low Bypass, Low Pressure Coolant Injection Pump Discharge Flow - Low 13 Bypass, or manual initiation of these functions operability requirements are not met. The 14 Required Action is to restore the channel to operable status within 24 hours. 15 16 For BWR/6s, Condition D is entered when the Condensate Storage Tank Level -Low operability 17 requirements are not met. Required Action D requires declaring the HPCS inoperable and 18 aligning the HPCS pump suction to the suppression pool within one hour. 19 20 For BWR/4s, Condition E is entered if the required Action and associated Completion Time of 21 Condition C or D, are not met. Required Action E.1 requires the associated low pressure ECCS 22 injection/spray subsystem to be declared inoperable immediately. 23 24 For BWR/6s, Condition E is entered if the Reactor Vessel Water Level - High Level 8 25 instrumentation operability requirements are not met. Action E.1 requires declaring the HCPS 26 system inoperable in 1 hour and restoring the channel to Operable status within 24 hours. 27 28 For BWR/6s, Condition F is entered if the LPCS Pump Discharge Flow Low (Bypass), LPCI 29 Pump A Discharge Flow Low (Bypass), LPCI Pump B and LPCI Pump C Discharge Flow - Low 30 (Bypass), HPCS Pump Discharge Pressure - High (Bypass) HPCS System Flow Rate - Low - 31 (Bypass) or Manual Initiation associated with these Functions operability requirements are not 32 met. The required action is to restore the channel to OPERABLE status within 24 hours. 33 34 For BWR/6s, Condition G is entered if the required action and associated completion time of 35 Condition C, D, E, or F is not met. Required Action G.1 requires the associated ECCS 36 injection/spray subsystem to be declared inoperable immediately. 37 38 2.3.3.2.5 New Surveillance Requirements SR 3.3.5.2.1, 3.3.5.2.2 and 3.3.5.3 39 40 New Table 3.3.5.2-1 specifies which SRs apply for each ECCS function. 41 42 SR 3.3.5.2.1 requires the performance of a Channel Check at a Frequency of [12 hours or in 43 accordance with the Surveillance Frequency Control Program.] 44 45 SR 3.3.5.2.2 requires the performance of a Channel Functional Test at a Frequency of [[92] 46 days or in accordance with the Surveillance Frequency Control Program.] 47 48 SR 3.3.5.2.3 requires the performance of a Logic System Functional Test at a Frequency of 1 [[18] months or in accordance with the Surveillance Frequency Control Program.] 2 3 2.3.3.3 Changes to Containment, Containment Isolation Valve and Standby Gas 4 Treatment System Requirements 5 6 The following TS are applicable during OPDRVs and/or contain Actions to suspend OPDRVS 7 when the LCO is not met: 8 9 NUREG-1433 (BWR/4 plants) 10 3.6.1.3, Primary Containment Isolation Valves (PCIVs) 11 3.6.4.1, [Secondary] Containment 12 3.6.4.2, Secondary Containment Isolation Valves (SCIVs) 13 3.6.4.3, Standby Gas Treatment System 14 15 NUREG-1434 (BWR/6 plants) 16 3.6.1.3, Primary Containment Isolation Valves (PCIVs) 17 3.6.4.1, [Secondary] Containment 18 3.6.4.2, Secondary Containment Isolation Valves (SCIVs) 19 3.6.4.3, Standby Gas Treatment System 20 21 For each of these TS, the applicability and required action sections are being revised to delete 22 references to OPDRVs. 23 24 2.3.3.4 Changes to Control Room Habitability and Temperature Control Requirements 25 26 NUREG-1433 (BWR/4 plants) 27 3.7.4, [Main Control Room Environmental Control (MCREC)] System 28 3.7.5, [Control Room Air Conditioning (AC)] System 29 30 NUREG-1434 (BWR/6 plants) 31 3.7.3, [Control Room Fresh Air (CRFA)] System 32 3.7.4, [Control Room AC] System 33 34 These LCO's are currently applicable during OPDRVs and contain required actions to 35 immediately initiate action to suspend OPDRVs when certain conditions of the LCO are not met. 36 37 The references to OPDRVs are being deleted from the applicability and required actions of 38 these TS. 39 40 2.3.3.5 Changes to Electrical Sources Requirements 41 42 NUREG-1433 (BWR/4 plants) and NUREG-1434 (BWR/6 plants) 43 3.8.2, AC Sources - Shutdown 44 3.8.5, DC Sources - Shutdown 45 3.8.8, Inverters - Shutdown 46 3.8.10, Distribution Systems - Shutdown 47 48 These TS are applicable in Modes 4 and 5 and currently contain a required action to initiate 1 action to suspend operations with a potential for draining the reactor vessel immediately if 2 certain conditions are not met. 3 4 TS 3.8.2 currently requires, in part, with one required offsite circuit inoperable or one required 5 diesel generator inoperable, to initiate action to suspend operations with a potential for draining 6 the reactor vessel immediately. 7 8 TS 3.8.5 currently requires, in part, with one [or more] required DC electrical power 9 subsystem[s] inoperable for reasons other than an inoperable battery charger, to initiate action 10 to suspend operations with a potential for draining the reactor vessel immediately 11 12 TS 3.8.3 currently requires, in part, with one [or more] [required] inverter[s] inoperable, to initiate 13 action to suspend operations with a potential for draining the reactor vessel immediately. 14 15 TS 3.8.10 currently requires, in part, with one or more required AC, DC, [or AC vital bus] 16 electrical power distribution subsystems inoperable, to initiate action to suspend operations with 17 a potential for draining the reactor vessel immediately. 18 19 These required actions are being deleted. 20 21 2.4 APPLICABLE REGULATORY REQUIREMENTS 22 23 The regulation at 10 CFR Section 50.36(a)(1) requires an applicant for an operating license to 24 include in the application proposed technical specifications in accordance with the requirements 25 of 10 CFR 50.36. The applicant must include in the application, a "summary statement of the 26 bases or reasons for such specifications, other than those covering administrative controls." 27 However, per 10 CFR 50.36(a)(1), these technical specification bases "shall not become part of 28 the technical specifications." Per 10 CFR 50.90, whenever a holder of a license desires to 29 amend the license, application for an amendment must be filed with the Commission, fully 30 describing the changes desired, and following as far as applicable, the form prescribed for 31 original applications. 32 33 Additionally, 10 CFR 50.36(b) requires: 34 35 36 Each license authorizing operation of a - utilization facility - will 37 include technical specifications. The technical specifications will 38 be derived from the analyses and evaluation included in the safety 39 analysis report, and amendments thereto, submitted pursuant to 40 10 CFR 50.34 ["Contents of applications; technical information"]. 41 The Commission may include such additional technical 42 specifications as the Commission finds appropriate. 43 44 45 Per 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the 46 applicant, the Commission will be guided by the considerations which govern the issuance of 47 initial licenses to the extent applicable and appropriate. 48 49 The categories of items required to be in the TSs are provided in 10 CFR 50.36(c). As required 1 by 10 CFR 50.36(c)(2)(i), the TSs will include LCOs, which are the lowest functional capability 2 or performance levels of equipment required for safe operation of the facility. Per 10 CFR 3 50.36(c)(2)(i), when an LCO of a nuclear reactor is not met, the licensee shall shut down the 4 reactor or follow any remedial action permitted by the TSs until the condition can be met. 5 6 The regulations at 10 CFR 50.36(c)(2)(ii) state that LCO's must be established for each item 7 meeting one of four criteria: 8 9 10 Criterion 1. Installed instrumentation that is used to detect, and 11 indicate in the control room, a significant abnormal degradation of 12 the reactor coolant pressure boundary. 13 14 Criterion 2. A process variable, design feature, or operating 15 restriction that is an initial condition of a design basis accident or 16 transient analysis that either assumes the failure of or presents a 17 challenge to fission product barrier integrity. 18 19 Criterion 3. A structure, system, or component that is part of the 20 primary success path and which functions or actuates to mitigate a 21 design basis accident or transient that either assumes the failure of 22 or presents a challenge to the integrity of a fission product barrier. 23 24 Criterion 4. A structure, system, or component which operating 25 experience or probabilistic safety assessment has shown to be 26 significant to public health and safety. 27 28 29 The regulation at 10 CFR 50.36(c)(3) requires TSs to include items in the category of SRs, 30 which are requirements relating to test, calibration, or inspection to assure that the necessary 31 quality of systems and components is maintained, that facility operation will be within safety 32 limits, and that the LCOs will be met. Also, the regulation at 10 CFR 50.36(a)(1) states that a 33 summary statement of the bases or reasons for such specifications, other than those covering 34 administrative controls, shall also be included in the application, but shall not become part of the 35 TSs. 36 37 As described in the Commission's Final Policy Statement on Technical Specifications 38 Improvements for Nuclear Power Reactors, recommendations were made by NRC and industry 39 task groups for new STS that include greater emphasis on human factors principles in order to 40 add clarity and understanding to the text of the STS, and provide improvements to the Bases 41 Section of Technical Specifications, which provides the purpose for each requirement in the 42 specification. Subsequently, improved vendor-specific STS were developed and issued by the 43 NRC in September 1992. The improved STS were published as the following NRC Reports: 44 45 - NUREG-1430, "Standard Technical Specific ations, Babcock and Wilcox Plants" 46 47 - NUREG-1431, "Standard Technical Spec ifications, West inghouse Plants" 48 49 - NUREG-1432, "Standard Technical Specificat ions, Combustion Engineering Plants" 1 2 - NUREG-1433, "Standard Technical Specificati ons, General Electric Plants, BWR/4" 3 4 - NUREG-1434, "Standard Technical Specificati ons, General Electric Plants, BWR/6" 5 6 These improved STS were the result of extensive technical meetings and discussions among 7 the NRC staff, industry owners' groups, vendors, and NUMARC. The Commission recognizes 8 the advantages of improved technical specifications. Clarification of the scope and purpose of 9 technical specifications has provided useful guidance to both the NRC and industry and has 10 served as an important incentive for industry participation in a voluntary program to improve 11 technical specifications. It has resulted in improved STS that are intended to focus licensee and 12 plant operator attention on those plant conditions most important to safety. This should also 13 result in more efficient use of agency and industry resources. 14 15 The NRC staff's guidance for review of TSs is in Chapter 16, Technical Specifications , of 16 NUREG-0800, Revision 3, "Standard Review Plan for the Review of Safety Analysis Reports for 17 Nuclear Power Plants" (SRP), dated March 2010, (ADAMS Accession No. ML100351425). As 18 described therein, as part of the regulatory standardization effort, the NRC staff has prepared 19 STS for each of the light-water reactor nuclear designs. NUREG-1433, Revision 4, contains the 20 STS for BWR/4 plants and NUREG 1434, Revision 4, contains the STS for BWR/6 plants. 21 22

3.0 TECHNICAL EVALUATION

23 24 3.1 DRAIN TIME DEFINITION 25 26 The proposed drain time is the time it would take the RPV water inventory to drain from the 27 current level to the TAF assuming the most limiting of the RPV penetrations flow paths with the 28 largest flow rate, or a combination of penetration flow paths that could open due to a common 29 mode failure, were to open. 30 31 The NRC staff reviewed the proposed drain time definition from the traveler. For the purpose of 32 NRC staff considerations, the term "break" describes a pathway for water to drain from the RPV 33 that has not been prescribed in the "DRAIN TIME" definition proposed in TSTF-542. All RPV 34 penetrations below the TAF are included in the determination of drain time as potential 35 pathways. Attachment 2 to the RAI responses dated March 14, 2016 (ADAMS Accession 36 No. ML16074A448), provided an example bounding drain time calculations for three examples: 37 (1) water level at or below the reactor flange; (2) water level above RPV flange with fuel pool 38 gates installed, and; (3) water level above reactor flange with fuel pool gates removed. The 39 drain time is calculated by taking the water inventory above the break and dividing by the 40 limiting drain rate until the TAF is reached. The limiting drain rate is a variable parameter 41 depending on the break size and the reduction of elevation head above break location during 42 the drain down event. The discharge point will depend on the lowest potential drain point for 43 each RPV penetration flow path on a plant-specific basis. This calculation provides a 44 conservative approach to determining the drain time of the RPV. 45 46 Additionally, Attachment 2 to the RAI responses, provides a proposed example table to pair with 47 the drain time calculation. This table correlates the drain time (hours) to the penetration flow 48 path diameter (inches) and the reactor vessel water level (inches above the TAF). The 49 proposed example table is color coded to visually show if LCO 3.5.2 is met, or which LCO 1 condition the licensee would be in. This proposed example table provides operators with a 2 correlation to relate the calculated drain time to the RPV water level and where in the LCO the 3 operators should be. Based on these considerations, the NRC staff finds the proposed drain 4 time definition with supporting calculation and table to be acceptable. 5 6 3.2 WATER SOURCES 7 8 The proposed LCO 3.5.2 states that for BWR/4 TSs, one low pressure Emergency Core Cooling 9 System (ECCS) injection/spray subsystem shall be OPERABLE. For BWR/6 TSs, one ECCS 10 injection/spray subsystem shall be OPERABLE. It should be noted that the term "low pressure" 11 does not appear in the BWR/6 LCO because the BWR/6 High Pressure Core Spray (HPCS) 12 System may be used to satisfy the LCO. 13 14 The NRC staff reviewed the water sources that w ould be applicable to the proposed TS 3.5.2. 15 The ECCS pumps are high-capacity pumps, with flow rates of thousands of gallons per minute 16 (gpm). Most RPV penetration flow paths would have a drain rate on the order of tens or 17 hundreds of gpm. The automatic initiation of an ECCS pump would provide the necessary 18 water source to counter these expected drain rates. The LPCI subsystem is to be considered 19 operable during alignment and operation for decay heat removal if capable of being manually 20 realigned and not otherwise inoperable. Decay heat removal in MODEs 4 and 5 is not affected 21 by the proposed change in TSTF-542 as these requirements on the number of RHR shutdown 22 cooling subsystems that must be operable and in operation to ensure adequate decay heat 23 removal from the core are unchanged. These requirements can be found in the BWR/4 STS 24 TS 3.4.9, "Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown," 25 TS 3.9.8, "Residual Heat Removal (RHR) - High Water Level, " and TS 3.9.10, "Residual Heat 26 Removal (RHR) - Low Water Level." For the BWR/6 STS, the applicable TS are TS 3.4.10, 27 "Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown," TS 3.9.8, 28 "Residual Heat Removal (RHR) - High Water Level, and TS 3.9.10, "Residual Heat Removal 29 (RHR) - Low Water Level." Based on these considerations, the NRC staff finds the water 30 sources provide assurances that the lowest functional capability required for safe operation is 31 maintained and protecting the safety limit. 32 33 3.3 TS 3.5.2 - REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL 34 35 The proposed TS 3.5.2, "Reactor Pressure Vessel (RPV) Water Inventory Control," LCO 36 contains two parts. The first part states that DRAIN TIME of RPV water inventory to the top of 37 active (TAF) shall be 36 hours, and the second part states that for BWR/4, one low pressure 38 ECCS injection/spray subsystem shall be OPERABLE, and for BWR/6, one ECCS 39 injection/spray subsystem shall be OPERABLE. The proposed applicability for TS 3.5.2 is 40 MODEs 4 and 5. 41 42 The NRC staff reviewed the proposed STS 3.5.2, focusing on ensuring the fuel remains covered 43 with water and the changes made compared to the current STS. The proposed STS 3.5.2 44 contains Conditions A through E based on either required ECCS injection/spray subsystem 45 operability or drain time. 46 47 The current STS LCO for BWR/4 and BWR/6 plants state that two ECCS injection/spray 48 subsystems shall be operable, whereas the proposed LCO 3.5.2 states that only one ECCS 49 injection/spray subsystem shall be operable. This change is reflected in Condition A. The 1 change from two ECCS injection/spray subsystem to one ECCS injection/spray subsystem is 2 because this redundancy is not required. With one ECCS injection/spray subsystem and 3 non-safety related injection sources, defense-in-depth will be maintained. The defense-in-depth 4 measure is consistent with other events considered during shutdown with no additional single 5 failure assumed. The drain time controls, in addition to the required ECCS injection/spray 6 subsystem, provide reasonable assurance that an unexpected draining event can be prevented 7 or mitigated before the RPV water level would be lowered to the TAF. 8 9 The proposed Condition A states that if the required ECCS injection/spray subsystem is 10 inoperable, it is to be restored to operable status within 4 hours. Proposed Condition B states 11 that if Condition A is not met, a method of water injection capable of operating without offsite 12 electrical power should be established immediately. The proposed Condition B for TS 3.5.2 is 13 different from the STS, which states to initiate action to suspend OPDRVs. The proposed 14 Condition B provides adequate assurance of an av ailable water source should Condition A not 15 be met within the 4-hour completion time. 16 17 The proposed Condition C states that for a drain time < 36 hours and 8 hours, to (1) verify 18 [secondary containment] boundary is capable of being established in less than 4 hours, and 19 (2) verify each [secondary containment] penetration flow path is capable of being isolated in less 20 than 4 hours, and (3) verify one standby gas treatment subsystem is capable of being placed in 21 operation in less than 4 hours. The current STS Condition C states if two ECCS injection/spray 22 subsystem are inoperable then restore one to operable status within 4 hours. The proposed 23 Condition C provides adequate protection should the DRAIN TIME be < 36 hours and 8 hours 24 because of the ability to establish secondary containment, isolate additional flow paths, and 25 have the standby gas treatment subsystem operable. 26 27 The proposed Condition D states that when drain time < 8 hours to (1) immediately initiate 28 action to establish an additional method of water injection with water sources capable of 29 maintaining RPV water level > TAF for 36 hours, (2) immediately initiate action to establish 30 [secondary] containment boundary, (3) immediately initiate action to isolate each [secondary] 31 containment penetration flow path or verify it can be manually isolated from the control room, 32 and (4) immediately initiate action to verify one standby gas treatment subsystem is capable of 33 being placed in operation. Additionally, there is a note stating that required ECCS 34 injection/spray subsystem or additional method of water injection shall be capable of operating 35 without offsite electrical power, which is similar to proposed Condition B. The current STS for 36 Condition D are similar to the proposed for when Required Action C.2 is not met. The proposed 37 Condition D provides adequate protection should the DRAIN TIME be < 8 hours because of the 38 ability to establish secondary containment, isolate additional flow paths, and have the standby 39 gas treatment subsystem operable. 40 41 The proposed Condition E states that when the required action and associated completion time 42 of Condition C or D is not met, or the drain time is < 1 hour, then initiate action to restore drain 43 time to 36 hours immediately. The proposed Condition E is new, as it is not present in the 44 current BWR/4 or BWR/6 STS. The proposed Condition E is acceptable as it provides the 45 necessary step to restore the drain time to 36 hours should the other conditions not be met, or 46 if the drain time is < 1 hour. 47 48 Based on the NRC staff's review, the proposed changes to TS 3.5.2 are acceptable based on 1 the actions taken to mitigate the water level reaching the TAF with the water sources available 2 and maintaining drain time 36 hours. The LCO correctly specifies the lowest functional 3 capability or performance levels of equipment required for safe operation of the facility. There is 4 reasonable assurance that the required actions to be taken when the LCO is not met can be 5 conducted without endangering the health and safety of the public. 6 7 The existing TS 3.3.5.2, "RCIC System Instrumentation," is renumbered as TS 3.3.5.3. This 8 increases consistency within the BWR TS as the Reactor Core Isolation Cooling (RCIC) System 9 is discussed in the section on TS 3.5.3. 10 11 3.4 STS 3.3.5.2, REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL 12 INSTRUMENTATION 13 14 The proposed TS and associated LCO in TS Section 3.3, "Instrumentation," contains A and B 15 versions of TS 3.3.5.2. The A version is for TS without a Setpoint Control Program and 16 Table 3.3.5.2-1 has a column for listing Allowable Value. The B version is for TS with a Setpoint 17 Control Program and Table 3.3.5.2-1 has no allowable value column, because the Setpoint 18 Control Program dictates the setpoint value. In a like manner the associated LCO 3.3.5.2 has A 19 and B versions. The actions and SRs for both versions A and B are the same for BWR/4 and 20 BWR/6. 21 22 The purpose of the RPV Water Inventory Control Instrumentation is to support the requirements 23 of new STS LCO 3.5.2, and the definition of drain time. There are instrumentation and controls 24 and their signal functions that are required for manual initiation or required as a permissive or 25 operational controls on the equipment of the systems that provide water injection capability, 26 certain start commands, and isolation functions. These instruments are required to be operable 27 if the systems that provide water injection and isolation functions are to be considered operable 28 as described in the safety evaluation of new STS 3.5.2. In some cases the reactor operators 29 have alternate, often more complex means, of starting and injecting water than the preferred 30 simple push button start. 31 32 Specifically, the BWR/4 the RPV Water Inventory Control Instrumentation supports operation of 33 the Core Spray and LPCI including manual initiation when needed as well as the system 34 isolation of the RHR system and the RWCU system. The equipment involved with each of 35 these systems is described in the safety evaluation of TS 3.5.2 and the Bases for LCO 3.5.2. 36 37 Specifically, the BWR/6 the RPV Water Inventory Control Instrumentation supports operation of 38 the LPCI with subsystems LPCI A, LPCI B, and LPCI C, LPCS, and HPCS, including manual 39 initiation when needed as well as the system isolation of the RHR system and the RWCU 40 system. The equipment involved with each of these systems is described in the safety 41 evaluation of TS 3.5.2 and the Bases for LCO 3.5.2. 42 43 TSTF-542, Section 3.3, "Proposed TS 3.3.5.2, Reactor Pressure Vessel Water Inventory 44 Control Instrumentation," describes and justifies the instrumentation requirements associated 45 with and needed to support TS 3.5.2 and LCO 3.5.2, "Reactor Pressure Vessel Water Inventory 46 Control." Section 3.3.1 addresses the proposed TS 3.3.5.2 LCO and applicability. Section 3.3.2 47 discusses the proposed actions of TS 3.3.5.2. Section 3.3.3, addresses the proposed TS 48 3.3.5.2 surveillances. Section 3.3.4 discusses the proposed Table 3.3.5.2-1. The NRC staff 49 finds the instrumentation and actions required to support TS 3.3.2, as presented in Section 3.3, 1 sufficient and necessary as discussed below. 2 3 3.4.1 Proposed TS 3.3.5.2 LCO and Applicability 4 5 The proposed LCO 3.3.5.2 states, "The RPV Water Inventory Control instrumentation for each 6 Function in Table 3.3.5.2-1 shall be OPERABLE." 7 8 The applicability states, "According to Table 3.3.5.2-1." 9 10 Section 3.3.1 of TSTF-542, states: 11 12 13 Table 3.3.5.2-1 contains those instrumentation Functions needed 14 to support manual initiation of the ECCS injection/spray 15 subsystem required by LCO 3.5.2, and automatic isolation of 16 penetration flow paths that may be credited in a calculation of 17 Drain Time. The Functions in Table 3.3.5.2-1 are moved from 18 existing TS 3.3.5.1, "ECCS Instrumentation," and TS 3.3.6.1, 19 "Primary Containment Isolation Instrumentation" Functions that 20 are required in Modes 4 or 5 or during OPDRVs. Creation of 21 TS 3.3.5.2 places these Functions in a single location with 22 requirements appropriate to support the safety function for 23 TS 3.5.2. 24 25 If plant-specific design and TS require different functions to 26 support manual initiation of an ECCS subsystem, those functions 27 should be included in TS 3.3.5.2. 28 29 30 3.4.2 Proposed TS 3.3.5.2 Actions for BWR/4 and BWR/6 31 32 TS 3.3.5.2 contains actions to be followed when the LCO is not met. 33 34 Section 3.3.2, "Proposed TS 3.3.5.2 Actions," of TSTF-542 discusses the actions of TS 3.3.5.2 35 and LCO 3.3.5.2. The NRC staff finds these actions are sufficient and necessary, because 36 when one or more instrument channels are inoperable the equipment and function controlled by 37 these instruments cannot complete the required function in the normal manner and these 38 actions direct the licensee to take appropriate actions as necessary and enter immediately into 39 the Conditions referenced in Table 3.3.5.2-1. These actions satisfy the requirements of 10 CFR 40 50.36(c)(2)(i) by providing a remedial action permitted by the TS until the LCO can be met. The 41 remedial actions provide reasonable assurance that an unexpected draining event can be 42 prevented or mitigated before the RPV water level would be lowered to the TAF. 43 44 3.4.3 Proposed TS 3.3.5.2 Actions for BWR/4 45 46 The following summarizes the proposed actions of Section 3.3.2 for BWR/4. 47 48 Section 3.3.2, "Proposed TS 3.3.5.2 Actions," of TSTF-542, Revision 2, discusses the actions of 1 TS 3.3.5.2 and LCO 3.3.5.2. The NRC staff finds these actions are sufficient and necessary, 2 because when one or more instrument channels are inoperable the equipment and function 3 controlled by these instruments cannot complete the required function in the normal way, and 4 these actions direct the licensee to take appropriate actions as required. The actions provide 5 reasonable assurance that an unexpected draining event can be prevented or mitigated before 6 the RPV water level would be lowered to the TAF. 7 8 Action A is applicable when one or more instrument channels are inoperable from 9 Table 3.3.5.2-1 and directs the licensee to immediately enter the Condition referenced in 10 Table 3.3.5.2-1 for that channel. 11 12 Action B (concerning the RHR system Isolation and RWCU system Isolation functions) are 13 applicable when automatic isolation of the associated penetration flow path is credited as not 14 having to be considered as a path for potential drainage in calculating drain time. If the 15 instrumentation is inoperable, Required Action B.1 directs an immediate declaration that the 16 associated penetration flow path(s) are incapable of automatic isolation. Required Action B.2 17 requires a re-calculation of drain time, but automatic isolation of the affected penetration flow 18 paths cannot be credited. 19 20 Action C (concerning low reactor steam dome pressure permissive Functions necessary for 21 ECCS subsystem manual initiation) addresses an event in which the permissive is inoperable 22 and manual initiation of ECCS using the control board pushbuttons is prevented. The function 23 must be placed in the trip condition within one hour. With the permissive function instrument in 24 the trip condition, manual initiation may now be performed using the preferred control board 25 pushbuttons. This one-hour completion time is acceptable, because despite the preferred start 26 method being prevented, the reactor operator can take manual control of the pump and the 27 injection valve to inject water into the RPV and achieve the safety function. The time of one 28 hour also provides reasonable time for evaluation and placing the channel in trip. 29 30 Action D (concerning pump discharge flow bypass Functions and the manual initiation 31 Functions) addresses actions when the bypass is inoperable and then there is a risk that the 32 associated ECCS pump could overheat when the pump is operating and the associated 33 injection valve is not fully open. In this condition, the operator can take manual control of the 34 pump and the injection. Similar to justification in Action C, while this is not the preferred 35 method, if a manual initiation function is inoperable, the ECCS subsystem pumps can be started 36 manually and the valves can be opened manually. The 24-hour completion time is acceptable, 37 because the functions can be performed manually and it allows time for the operator to evaluate 38 and have necessary repairs completed. Unlike the failure of a pushbutton that may concern 39 electronic component repairs, mechanical components may be involved in repairs, testing, and 40 return to service of pumps and valves. This further justifies a 24-hour completion time as 41 appropriate. 42 43 Action E is needed and becomes necessary, if the required action and associated completion 44 time of Condition C or D, are not met. If they are not met, then the associated low pressure 45 ECCS injection/spray subsystem may be incapable of performing the intended function, and the 46 ECCS subsystem must be declared inoperable immediately. 47 48 3.4.4 Proposed TS 3.3.5.2 Actions for BWR/6 49 1 TS 3.3.5.2 contains proposed actions to be followed when the LCO is not met for a BWR/6. 2 3 Section 3.3.2, "Proposed TS 3.3.5.2 Actions," of TSTF-542, Revision 2, discusses the Actions of 4 TS 3.3.5.2 and LCO 3.3.5.2. The NRC staff finds these actions are sufficient and necessary, 5 because when one or more instrument channels are inoperable the equipment and function 6 controlled by these instruments cannot complete the required function in the normal way and 7 these actions direct the licensee to take appropriate actions as required. The actions provide 8 reasonable assurance that an unexpected draining event can be prevented or mitigated before 9 the RPV water level would be lowered to the TAF. 10 11 Action A is applicable when one or more instrument channels are inoperable from Table 3.3.5.2 12 and directs the licensee to immediately enter the condition referenced in Table 3.3.5.2-1 for that 13 channel. 14 15 Action B (concerning the RHR system isolation and RWCU system isolation functions) are 16 applicable when automatic isolation of the associated penetration flow path is credited as not 17 having to be considered as a path for potential drainage in calculating drain time. If the 18 instrumentation is inoperable, Required Action B.1 directs an immediate declaration that the 19 associated penetration flow path(s) are incapable of automatic isolation. Required Action B.2 20 requires a re-calculation of drain time, but automatic isolation of the affected penetration flow 21 paths cannot be credited. 22 23 Action C (concerning low reactor steam dome pressure permissive Functions necessary for 24 ECCS subsystem manual initiation) addresses an event in which the permissive is inoperable 25 and manual initiation of ECCS using the control board pushbuttons is prevented. The function 26 must be placed in the trip condition within one hour. With the permissive function instrument in 27 the trip condition, manual initiation may now be performed using the preferred control board 28 pushbuttons. This one hour completion time is acceptable, because despite the preferred start 29 method being prevented, the reactor operator can take manual control of the pump and the 30 injection valve to inject water into the RPV and achieve the safety function. The time of one 31 hour also provides reasonable time for evaluation and placing the channel in trip. 32 33 Action D (concerning loss of adequate water supply for the HPCS System), addresses an event 34 in which there is an inadequate water supply. The instrumentation functions have the ability to 35 detect low-water setpoint in the Condensate Storage Tank and actuate valves to realign HPCS 36 suction water source to the Suppression Pool. The Condensate Storage Tank Level - Low 37 Function indicates multiple, inoperable channels within the same Function resulting in a loss of 38 the automatic ability to swap suction to the Suppression Pool. The HPCS system must be 39 declared inoperable within one hour or the HPCS pump suction must be realigned to the 40 Suppression Pool, since, if realigned, the Function is already performed. This one hour is 41 acceptable, because it provides sufficient time to take the action in order to minimize the risk of 42 HPCS being needed without an adequate water source by allowing time for restoration or 43 alignment of the HPCS pump suction to the suppression pool. 44 45 Action E (concerning HPCS high water level Function in the RPV) addresses actions when this 46 instrument function is inoperable. HPCS Reactor Vessel Water Level - High, Level 8 function 47 ensures that appropriate actions are taken if the HPCS Reactor Vessel Water Level - High, 48 Level 8 Function is inoperable. If the inoperability results in the channel being tripped, the 49 HPCS pump discharge valve will not open and HPCS injection is prevented. In that case the 1 HPCS System must be declared inoperable within one hour, and the function must be restored 2 to operable status within 24 hours. The one hour completion time is acceptable, because of the 3 ability to manually start the HPCS pumps and open the discharge valve. The 24-hour 4 completion time is acceptable, because it allows time for the operator to evaluate and arrange 5 for repairs. 6 7 Action F (concerning pump discharge flow bypass Functions and the manual initiation 8 Functions) addresses an event in which the bypass is inoperable and there is a risk that the 9 associated ECCS pump could overheat when the pump is operating and the associated 10 injection valve is not fully open. In this condition, the operator can take manual control of the 11 pump and the injection. Similar to justification in Action C, while this is not the preferred 12 method, if a manual initiation function is inoperable, the ECCS subsystem pumps can be started 13 manually and the valves can be opened manually. The 24-hour completion time is acceptable, 14 because the functions can be performed manually and it allows time for the operator to evaluate 15 and have necessary repairs completed. Unlike the failure of a pushbutton that may concern 16 electronic component repairs, mechanical components may be involved in repairs, testing, and 17 return to service of pumps and valves further justifying a 24-hour completion time as 18 appropriate. 19 20 Action G is needed and becomes necessary, if the required action and associated completion 21 time of Condition C, D, E, or F are not met. If they are not met, then the associated low 22 pressure ECCS injection/spray subsystem may be incapable of performing the intended 23 function, and the ECCS subsystem must be declared inoperable immediately. 24 25 3.4.5 Proposed TS 3.3.5.2 Surveillances for BWR/4 and BWR/6 26 27 Section 3.3.3, "Proposed TS 3.3.5.2 Surveillances," of TSTF-542 discusses the SR of TS 28 3.3.5.2. The TS 3.3.5.2 SR include Channel Checks, Channel Functional Tests, and Logic 29 System Functional Tests. There are three SRs numbered SR 3.3.5.2.1, SR 3.3.5.2.2, and SR 30 3.3.5.2.3. The NRC staff finds these tests are sufficient and adequate, because they are 31 essential to ensure the Functions of TS 3.3.5.2 are operable (i.e., capable of performing the 32 specified safety function in support of TS 3.5.2, Drain Time, and the protection from a potential 33 drain down of the RPV in Modes 4 and 5). The NRC staff finds the proposed TS 3.3.5.2 34 surveillances of LCO 3.5.2 as described in Section 3.3.3 satisfies 10 CFR 50.36(c)(3) by 35 providing the specific SRs relating to test, calibration, or inspection to assure that the necessary 36 quality of systems and components is maintained. 37 38 The following summarizes the notable characteristics of the surveillances described in 39 Section 3.3.3 of TSTF-542, which were reviewed by the NRC staff. 40 41 SR 3.3.5.2.1 requires a Channel Check and is applied to all functions except manual initiation. 42 Performance of the Channel Check ensures that a gross failure of instrumentation has not 43 occurred. A Channel Check is normally a comparison of the parameter indicated on one 44 channel to a similar parameter on other related channels. A Channel Check is significant in 45 assuring that there is a low probability of an undetected complete channel failure and is a key 46 safety practice to verifying the instrumentation continues to operate properly between each 47 Channel Functional Test. The frequency of 12 hours, or in accordance with the Surveillance 48 Frequency Control Program, is consistent with the existing requirements and supports operating 1 shift situational awareness. 2 3 SR 3.3.5.2.2 requires a Channel Functional Test and is applied to all functions except manual 4 initiation. A Channel Functional Test is the injection of a simulated or actual signal into the 5 channel as close to the sensor as practicable to verify operability of all devices in the channel 6 required for channel operability. It is performed on each required channel to ensure that the 7 entire channel will perform the intended function. The frequency is in accordance with the 8 Surveillance Frequency Control Program or 92 days. The applicant states, "This is acceptable 9 because it is consistent with the existing requirements for these Functions and is based upon 10 operating experience that demonstrates channel failure is rare." Since periods in MODEs 4 and 11 5 as refueling outages are often in the order of 30 days or less, licensees could include this SR, 12 if desired, as part of a refueling activity. 13 14 SR 3.3.5.2.3 requires a Logic System Functional Test and is only applied to the manual initiation 15 functions. The Logic System Functional Test is a test of all logic components required for 16 operability of a logic circuit, from as close to the sensor as practicable up to, but not including, 17 the actuated device, and demonstrates the operability of the required manual initiation logic for 18 a specific channel. The ECCS subsystem functional testing performed in proposed SR 3.5.2.7 19 overlaps this surveillance to complete testing of the assumed safety function. The traveler 20 states: 21 22 23 The Frequency of [18] months, or in accordance with the 24 Surveillance Frequency Control Program, is consistent with the 25 existing requirements, and is based upon operating experience 26 that that has shown that these components usually pass the 27 Surveillance when performed at this Frequency. 28 29 30 There are no SRs included to verify or adjust the instrument setpoint derived from the allowable 31 value using a Channel Calibration or a surveillance to calibrate the trip unit. The traveler states, 32 33 34 A draining event in Mode 4 or 5 is not an analyzed accident and, 35 therefore, there is no accident analysis on which to base the 36 calculation of a setpoint. The purpose of the Functions is to allow 37 ECCS manual initiation or to automatically isolate a penetration 38 flow path, but no specific RPV water level is assumed for those 39 actions. Therefore, the Mode 3 Allowable Value was chosen for 40 use in Modes 4 and 5 as it will perform the desired function. 41 Calibrating the Functions in Modes 4 and 5 is not necessary, as 42 TS 3.3.5.1 and TS 3.3.6.1 continue to require the Functions to be 43 calibrated on an [18] month Frequency. 44 45 And: 46 47 A draining event in Mode 4 or 5 is not an analyzed accident and, 1 therefore, there are no accident analysis assumptions on 2 response time. 3 4 5 This is acceptable, because this is adequate to ensure the channel responds with the required 6 pumping systems to inject water when needed and isolation equipment to perform when 7 commanded. 8 9 ECCS Response Time and Isolation System Response Time testing ensure that the individual 10 channel response times are less than or equal to the maximum values assumed in the accident 11 analysis. TS 3.3.5.2 does not include SRs to participate in any ECCS Response Time testing 12 and Isolation System Response Time testing. This is acceptable because the purpose of these 13 tests are to ensure that the individual channel response times are less than or equal to the 14 maximum values assumed in the accident analysis, but a draining event in Mode 4 or 5 is not an 15 analyzed accident and, therefore, there are no accident analysis assumptions on response time 16 and there are alternate manual methods for achieving the safety function. A potential draining 17 event in MODEs 4 and 5 is a slower event than a LOCA. More significant protective actions are 18 required as the calculated drain time decreases. 19 20 3.4.6 Conclusion of NRC Staff Review of TS 3.3.5.2 21 22 The NRC staff finds that proposed TS 3.3.5.2 and LCO 3.3.5.2 satisfies Criterion 4 of 23 10 CFR 50.36(c)(3), because specific instrumentation is provided that helps prevent or mitigate 24 a potential RPV drain down event. Operating experience highlights that RPV draining events 25 are potentially significant to public health and safety, as established in the following NRC 26 documents: 27 28 1. Information Notice 84-81 "Inadvertent Reduction in Primary Coolant Inventory in 29 Boiling Water Reactors During Shutdown and Startup," November 1984. 30 2. Information Notice 86-74, "Reduction of Reactor Coolant Inventory Because of 31 Misalignment of RHR Valves," August 1986. 32 3. Generic Letter 92-04, "Resolution of the Issues Related to Reactor Vessel Water 33 Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f)," August 1992. 34 4. NRC Bulletin 93-03, "Resolution of Issues Related to Reactor Vessel Water Level 35 draining event in Mode 4 Instrumentation in BWRs," May 1993. 36 37 The NRC staff finds that proposed LCO 3.3.5.2 co rrectly specifies the lowest functional 38 capability or performance levels of equipment required for safe operation of the facility. There is 39 reasonable assurance that the required actions to be taken when the LCO is not met can be 40 conducted without endangering the health and safety of the public. 41 42 3.5 TABLE 3.3.5.2-1, "RPV WATER INVENTORY CONTROL INSTRUMENTATION" 43 44 In order to support the requirements of TS 3.5.2, and LCO 3.5.2, "Reactor Pressure Vessel 45 (RPV) Water Inventory Control," and the definition of "DRAIN TIME"; the instrumentation 46 requirements are designated in Table 3.3.5.2-1. These instruments are required to be operable 47 if the systems that provide water injection and isolation functions are to be considered operable 48 as described in the NRC staff's safety evaluation of TS 3.5.2. 49 1 Table 3.3.5.2-1 specifies the instrumentation that shall be operable for each function in the table 2 for Modes 4 and 5 (or other specified conditions), the required number of channels per function, 3 conditions referenced from required action A.1, SR for the functions, the allowable value (if 4 version A), and footnotes concerning items of the table. 5 6 Table 3.3.5.2-1 for BWR/4 and BWR/6 differ only in that version A has a column for the 7 allowable value and B does not. Version A has a potential or generic allowable value in 8 brackets. The brackets indicate that a plant-specific value should be used in the LAR to adopt 9 TSTF-542. 10 11 Section 3.3.4, "Proposed Table TS 3.3.5.2-1, 'RPV Water Inventory Control Instrumentation'" of 12 TSTF-542, presents details on the functions required to support the equipment and functions of 13 TS 3.5.2 for BWR/4 and BWR/6. The NRC staff finds the presentation in this table acceptable, 14 because this section sufficiently discusses the purpose of the functions, the applicability, the 15 number of required channels, the references to the Condition to be entered by letter (e.g., A, B, 16 C) if the function is inoperable, the applicable SRs, the selection of the allowable value, if 17 applicable, and justification of differences between the existing and proposed TS functions. 18 This RPV Water Inventory Control Instrumentation set is acceptable, because it is adequate to 19 ensure the instruments of the channels responds with the required accuracy permitting pumps 20 systems to operate to inject water when needed and isolation of equipment when commanded 21 to support the prevention of or mitigate a potential RPV draining event. 22 23 Each of the ECCS subsystems in the BWR/4 and BWR/6 in MODEs 4 and 5 are initiated by 24 manual pushbutton. The traveler states, "- automatic initiation of an ECCS injection/spray 25 subsystem, with injection rates of thousands of gpm, may be undesirable as it can lead to 26 overflowing the RPV cavity." Thus, there is adequate time to take manual actions (e.g., hours 27 versus minutes). Considering the action statements as the drain time decreases (the proposed 28 TS 3.5.2, Action E, prohibits plant conditions that could result in drain times less than one hour), 29 therefore, there is sufficient time for the reactor operators to take manual action to stop the 30 draining event, and to manually start an ECCS injection/spray subsystem or the additional 31 method of water injection as needed. Consequently, there is no need for automatic initiation of 32 ECCS to respond to an unexpected draining event. This is acceptable, because a draining 33 event is a slow evolution when compared to a design basis LOCA assumed to occur at a 34 significant power level. 35 36 3.5.1 Proposed Table 3.3.5.2-1 Functions for BWR/4 37 38 The following summarizes notable characteristics of the RPV Water Inventory Control 39 Instrumentation as discussed in Section 3.3.4 of TSTF-542, Revision 2. 40 41 For the Table 3.3.5.2-1 Functions 1.a and 2.a, BWR/4 CS and LPCI Systems, Reactor Steam 42 Dome Pressure - Low (Injection Permissive), these signals are used as permissives and 43 protection for these low pressure ECCS injection/spray subsystem manual initiation functions. 44 This function ensures that the reactor pressure has fallen to a value below these subsystems' 45 maximum design pressure before permitting the operator to open the injection valves of the low 46 pressure ECCS subsystems. Even though during MODEs 4 and 5 the reactor steam dome 47 pressure is expected to virtually always be below the ECCS maximum design pumping 48 pressure, the Reactor Steam Dome Pressure - Low signals are required to be operable and 1 capable of permitting initiation of the ECCS. 2 3 For the Table 3.3.5.2-1 Functions 1.b and 2.b, BWR/4 CS and LPCI Systems, Pump Discharge 4 Flow - Low (Bypass), these minimum flow instruments are provided to protect the associated 5 low pressure ECCS pumps from overheating when the pump is operating and the associated 6 injection valve is not fully open. The minimum flow line valve is opened when low flow is 7 sensed, and the valve is automatically closed when the flow rate is adequate to protect the 8 pump. Where applicable, allowable values (version A) specified are high enough to ensure that 9 the pump flow rate is sufficient to protect the pump, yet low enough to ensure that the closure of 10 the minimum flow valve is initiated to allow full flow into the core. Brackets around allowable 11 value indicate the actual value is to be plant-specific and dependent on actual equipment. The 12 LPCI minimum flow valves are time delayed such that the valves will not open for 10 seconds 13 after the switches detect low flow. This time delay is acceptable, because it is provided to limit 14 reactor vessel inventory loss during the st artup of the RHR shutdown cooling mode. 15 16 For the Table 3.3.5.2-1 Functions 1.c and 2.c, BWR/4 CS System Manual Initiation and LPCI, 17 System Manual Initiation, the manual initiation pushbutton channels introduce signals into the 18 appropriate ECCS logic to provide manual initiation capability. There is one push button for 19 each of the CS and LPCI subsystems (i.e., two for CS and two for LPCI). There is no allowable 20 value for this Function since the channels are mechanically actuated based solely on the 21 position of the push buttons. An instrument channel of the Manual Initiation Function (one 22 channel per subsystem) is required to be Operable in MODEs 4 and 5 when the associated 23 ECCS subsystems are required to be Operable per LCO 3.5.2. 24 25 For the Table 3.3.5.2-1 Function 3.a, BWR/4 RHR System Isolation, Reactor Vessel Water 26 Level - Low, Level 3, the function is only required to be operable when automatic isolation of the 27 associated penetration flow path is credited in the drain time calculation. The number of 28 required instrument channels is [2 in one trip system], which retains the requirement that the two 29 instrument channels must be associated with the same trip system. Each trip system isolates 30 one of two redundant isolation valves, and only one trip system is required to be operable to 31 ensure that automatic isolation of one of the two isolation valves will occur on low reactor vessel 32 water level indication. The allowable value (version A) was chosen to be the same as the 33 Primary Containment Isolation Instrumentation Reactor Vessel Water Level - Low, Level 3 34 Allowable Value from LCO 3.3.6.1. 35 36 For the Table 3.3.5.2-1 Function 4.a, BWR/4 RWCU, System Isolation, Reactor Vessel Water 37 Level - Low Low, Level 2, the function is only required to be operable when automatic isolation 38 of the associated penetration flow path is credited in the drain time calculation. The number of 39 required channels is [2 in one trip system], which retains the requirement that the two instrument 40 channels must be associated with the same trip sy stem. Only one trip system is required to be 41 operable to ensure that automatic isolation of one of the two isolation valves will occur on low 42 reactor vessel water level. Allowable value (version A) was chosen to be the same as the 43 ECCS Reactor Vessel Water Level - Low Low, Level 2 Allowable Value from LCO 3.3.5.1. 44 45 3.5.2 Proposed Table 3.3.5.2.-1 Functions for BWR/6 46 47 The following summarizes notable characteristics of the RPV Water Inventory Control 48 Instrumentation as discussed in Section 3.3.4 of TSTF-542, Revision 2. 49 1 For the Table 3.3.5.2-1 Functions 1.a and 2.a, BWR/6 LPCS and LPCI Systems, Reactor Steam 2 Dome Pressure - Low (Injection Permissive), these signals are used as permissives and 3 protection for these low pressure ECCS injection/spray subsystem manual initiation functions. 4 This function ensures that the reactor pressure has fallen to a value below these subsystems' 5 maximum design pressure before permitting the operator from opening the injection valves of 6 the low pressure ECCS subsystems. Even though during MODEs 4 and 5 the reactor steam 7 dome pressure is expected to virtually always be below the ECCS maximum design pumping 8 pressure, the Reactor Steam Dome Pressure - Low signals are required to be operable and 9 capable of permitting initiation of the ECCS. 10 11 For the Table 3.3.5.2-1 Functions 1.b, 1.c, and 2.b, BWR/6 LPCS and LPCI Systems Low 12 Pressure Coolant Injection and Low Pressure Core Spray Pump Discharge Flow - Low 13 (Bypass), these instruments are provided to protect the associated low pressure ECCS pump 14 from overheating when the pump is operating and the associated injection valve is not fully 15 open. The minimum flow line valve is opened when low flow is sensed, and the valve is 16 automatically closed when the flow rate is adequate to protect the pump. Where applicable 17 allowable values (version A) specified are high enough to ensure that the pump flow rate is 18 sufficient to protect the pump, yet low enough to ensure that the closure of the minimum flow 19 valve is initiated to allow full flow into the core. Brackets around allowable value indicate the 20 actual value is to be plant-specific and dependent on actual equipment. 21 22 For the Table 3.3.5.2-1 Functions 1.d and 2.c, BWR/6 LPCS and LPCI Systems, Manual 23 Initiation, the manual initiation pushbutton channels introduce signals into the appropriate ECCS 24 logic to provide manual initiation capability. There is one pushbutton for each subsystem in the 25 two divisions of low pressure ECCS (i.e., Division 1 ECCS, LPCS and LPCI A; Division 2 ECCS, 26 LPCI B and LPCI C). There are four subsystems, thus four pushbuttons for the low pressure 27 ECCS. The only manual initiation function required to be operable is that associated with the 28 ECCS subsystem that is required to be operable by LCO 3.5.2. Since the channels are 29 mechanically actuated based solely on the position of the pushbuttons, there is no allowable 30 value (version A) for this function. When this instrument function is inoperable, manual initiation 31 with the control board push buttons is inoperable. However, the ECCS pumps can be started 32 manually and valves can be opened manually by the reactor operator. This is not the preferred 33 condition. 34 35 For the Table 3.3.5.2-1 Functions 3.a, BWR/6 HPCS System Reactor Vessel Water Level - 36 High, Level 8, the High RPV water level, Level 8 signal, is used to close the HPCS injection 37 valve to prevent overflow into the main steam lines (MSLs). One instrument channel associated 38 with the HPCS system is required to be operable to support LCO 3.5.2. The LCO 3.3.5.2 39 allowable value (version A) is chosen to isolate flow from the HPCS system prior to water 40 overflowing into the MSLs. 41 42 For the Table 3.3.5.2-1 Functions 3.b, BWR/6 HPCS System, Condensate Storage Tank 43 Level - Low, the low level signal in the Condensate Storage Tank (CST) indicates the lack of an 44 adequate supply of makeup water from this primary source for HPCS. Normally, the water 45 source for the suction for HPCS is the CST. If the water level in the CST falls below a 46 preselected level, instrumentation logic controls valves so suction is then pulled from the 47 Suppression Pool. First the Suppression Pool suction valve is automatically opened and then 48 the CST suction valve is automatically closed in a manner to ensure that an adequate supply of 49 makeup water is available to the HPCS pump. The Condensate Storage Tank Level - Low 1 signals are initiated from two level transmitters. The Condensate Storage Tank Level - Low 2 Function Allowable Value is high enough to ensure adequate pump suction head while water is 3 being taken from the CST. 4 5 For the Table 3.3.5.2-1 Functions 3.c and 3.d, BWR/6 HPCS System, HPCS Pump Discharge 6 Pressure - High (Bypass) and HPCS System Fl ow Rate - Low (Bypass), the minimum flow 7 instruments are provided to protect the HPCS pump from overheating when the pump is 8 operating and the associated injection valve is not fully open. The minimum flow line valve is 9 opened when low flow and high pump discharge pressure are sensed, and the valve is 10 automatically closed when the flow rate is adequate to protect the pump or the discharge 11 pressure is low (indicating the HPCS pump is not operating). 12 13 For the Table 3.3.5.2-1 Function 3.e, BWR/6 HPCS System, Manual Initiation, the Manual 14 Initiation push button channel introduces a signal into the HPCS logic to provide manual 15 initiation capability. There is one pushbutton for the HPCS system. 16 17 For the Table 3.3.5.2-1 Function 4.a, BWR/6 RHR System Isolation, Reactor Vessel Water 18 Level - Low, Level 3, the Function is only required to be operable when automatic isolation of 19 the associated RHR system penetration flow path is credited in calculating drain time. The 20 definition of drain time allows crediting the closing of penetration flow paths that are capable of 21 being automatically isolated by RPV water level isolation instrumentation prior to the RPV water 22 level dropping below the TAF, but if the instrument function is inoperable, a closed path cannot 23 be credited and a drain time calculation must be re-performed. 24 25 For the Table 3.3.5.2-1 Function 5.a, BWR/6 RWCU System Isolation, Reactor Vessel Water 26 Level - Low Low, Level 2, the Function is only required to be Operable when automatic isolation 27 of the associated RWCU system penetration flow path is credited in calculating drain time. The 28 definition of drain time allows crediting the closing of penetration flow paths that are capable of 29 being automatically isolated by RPV water level isolation instrumentation prior to the RPV water 30 level dropping below the TAF, but if the instrument function is inoperable, a closed path cannot 31 be credited and a drain time calculation must be re-performed. This function is not applicable in 32 MODEs 4 or 5 in TS 3.3.6.1, but is being added to TS 3.3.5.2 to support crediting the automatic 33 isolation of the RWCU system in calculating drain time. 34 35 3.6 OTHER DIFFERENCES BETWEEN THE CURRENT AND PROPOSED TS 36 37 Section 3.4., "Evaluation of other Differences between the Current and Proposed TS," of TSTF-38 542, presents and discusses other differences between the current TS requirements related to 39 OPDRVs and the proposed TS requirements for RPV WIC. The current STS contain 40 requirements related to instrumentation that are applicable during OPDRVs and are applicable 41 when the existing LCO 3.5.2 is applicable. They do not specifically impact the focus on TS 42 3.3.5.2 and the associated LCO 3.5.2 and Table 3.3.5.2-1. 43 44 3.7 STS 3.5.2 - REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL 45 46 The categories of items required to be in the TSs are provided in 10 CFR 50.36(c). As required 47 by 10 CFR 50.36(c)(2)(i), the TSs will include LCOs, which are the lowest functional capability 48 or performance levels of equipment required for safe operation of the facility. Per 10 CFR 49 50.36(c)(2)(i), when an LCO of a nuclear reactor is not met, the licensee shall shut down the 1 reactor or follow any remedial action permitted by the TSs until the condition can be met. 2 3 The regulations at 10 CFR 50.36(c)(2)(ii) state that LCOs must be established for each item 4 meeting one of four criteria: 5 6 7 Criterion 1. Installed instrumentation that is used to detect, and 8 indicate in the control room, a significant abnormal degradation of 9 the reactor coolant pressure boundary. 10 11 Criterion 2. A process variable, design feature, or operating 12 restriction that is an initial condition of a design basis accident or 13 transient analysis that either assumes the failure of or presents a 14 challenge to fission product barrier integrity. 15 16 Criterion 3. A structure, system, or component that is part of the 17 primary success path and which functions or actuates to mitigate 18 a design basis accident or transient that either assumes the failure 19 of or presents a challenge to the integrity of a fission product 20 barrier. 21 22 Criterion 4. A structure, system, or component which operating 23 experience or probabilistic safety assessment has shown to be 24 significant to public health and safety. 25 26 27 Technical Specification Safety Limit 2.1.1.3 requires that reactor vessel water level shall be 28 greater than the top of active irradiated fuel. Maintaining water level above the TAF ensures 29 that the fuel cladding fission product barrier is protected during shutdown conditions. The 30 changes to the STS described in traveler TSTF-542 establish specifications for equipment and 31 associated instrumentation that ensure the reactor vessel water level is maintained above the 32 TAF during MODE 4 and 5 operations. 33 34 NUREG-0800, Revision 3, Standard Review Plan (March 2010) (ADAMS Accession 35 No. ML100351425), describes LOCAs as postulated accidents that would result from the loss of 36 reactor coolant, at a rate in excess of the capability of the normal reactor coolant makeup 37 system, from piping breaks in the reactor coolant pressure boundary. During operation in 38 MODEs 4 and 5, the reactor coolant system is at a low operating temperature (<200 ° 39 Fahrenheit) and is depressurized. An event involving a loss of inventory while in the shutdown 40 condition is judged to not exceed the capacity of one ECCS subsystem. The accidents that are 41 postulated to occur during shutdown conditions, the Fuel Handling Accident and the Waste Gas 42 Decay Tank Rupture, do not involve a loss of inventory. The equipment and instrumentation 43 associated with the Reactor Vessel Water Inventory Control TS do not provide detection or 44 mitigation related to these design basis accidents. 45 46 The revised STS LCO 3.5.2 contains requirements for operability of one ECCS subsystem 47 along with requirements to maintain a sufficiently long drain time that plant operators would 48 have time to diagnose and mitigate an unplanned draining event. The NRC staff has 49 determined that the LCO 3.5.2 and 3.3.5.2 provide alternatives for the lowest functional 1 capability or performance levels of equipment required for safe operation of the facility. On this 2 basis, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(2)(i) are met. 3 4 Additionally, the revised STS LCOs 3.5.2 and 3.3.5.2 provide remedial actions to be taken in the 5 event the LCO is not satisfied, therefore meeting the requirements of 10 CFR 50.36(c)(2)(i). 6 The NRC staff has found that the remedial ac tions provide reasonable assurance that an 7 unexpected draining event can be prevented or mitigated before the RPV water level would be 8 lowered to the TAF. 9 10 The regulation at 10 CFR 50.36(c)(3) requires TSs to include items in the category of SRs, 11 which are requirements relating to test, calibration, or inspection to assure that the necessary 12 quality of systems and components is maintained, that facility operation will be within safety 13 limits, and that the LCOs will be met. The NRC staff reviewed the SRs associated with the 14 revised LCOs 3.5.2 and 3.3.5.2. The NRC staff reviewed the new SRs and determined that 15 they are appropriate for ensuring the operability of the equipment and instrumentation specified 16 in LCOs 3.5.2. Therefore, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(3) 17 are met. 18 19 The regulation at 10 CFR 50.36(a)(1) states that a summary statement of the bases or reasons 20 for such specifications, other than those covering administrative controls, shall also be included 21 in the application, but shall not become part of the TSs. Traveler TSTF-542 contains TS Bases 22 changes that describe the basis for the affected TS. A summary of the NRC staff's evaluation of 23 the TS Bases changes is provided in an attachment to this SE. 24 25 The NRC staff's guidance for review of TSs is in Chapter 16, Technical Specifications , of 26 NUREG-0800, Revision 3, Standard Review Plan (March 2010) (ADAMS Accession 27 No. ML100351425). As described therein, as part of the regulatory standardization effort, the 28 NRC staff has prepared STS for each of the light-water reactor nuclear designs. NUREG-1433, 29 Revision 4, contains the STS for BWR/4 plants and NUREG 1434, Revision 4, contains the STS 30 for BWR/6 plants. The changes to the STS were reviewed for technical clarity and consistency 31 with customary terminology and format with the existing requirements. The NRC staff found 32 that the proposed changes were consistent with the existing framework. 33 34

4.0 CONCLUSION

35 36 The NRC staff reviewed traveler TSTF-542, Revision 2, "Reactor Pressure Vessel Water 37 Inventory Control," which proposed changes to NUREG-1433, Volumes 1 (STS for BWR/4) and 38 2 (Bases) and NUREG-1434 Volumes 1 (STS for BWR/6) and 2 (Bases). The NRC staff 39 determined that the proposed changes to the STS for BWR/4 and the STS for BWR/6 met the 40 standards for TS in 10 CFR 50.36(b). The proposed LCOs appropriately specify the lowest 41 functional capability or performance levels of equipment required for safe operation of the 42 facility, as required by 10 CFR 50.36(c)(2)(i). The remedial actions to be taken when an LCO is 43 not met action statements provide adequate protection to the health and safety of the public, 44 thereby satisfy the Act and 10 CFR 50.36(c)(2)(i). The proposed surveillance requirements 45 assure that the necessary quality of systems and components is maintained, that facility 46 operation will be within safety limits, and that the LCOs will be met, and satisfy 10 CFR 47 50.36(c)(3). 48 49 The proposed bases, which will be added to future revisions to NUREG-1433, Volume 2, and 1 NUREG-1434, Volume 2, satisfy the Commission's Policy Statement by addressing the 2 questions specified in the policy statement, and cite references to appropriate licensing 3 documentation to support the Bases. 4 5 Technical contacts: Matt Ha rdgrove, NRR/DSS/SRXB 6 Eugene Eagle, NRR/DE/EICB 7 8

Attachment:

Basis for Accepting the Proposed Changes to the Standard Technical 9 Specification Bases, Volume 2 of NUREGs 1433 and 1434 10 11 Date: October 6, 2016 12 ATTACHMENT ATTACHMENT 1 2 BASIS FOR ACCEPTING THE PROPOSED CHANGES TO THE STANDARD TECHNICAL 3 SPECIFICATION BASES, VOLUME 2 OF NUREGS 1433 AND 1434 4 5

1.0 INTRODUCTION

6 7 Traveler TSTF-542 proposes changes to "Standard Technical Specifications, General Electric 8 BWR/4 Plants, BWR/4" NUREG-1433, Volume 2, "Bases," Revision 4.0, April 2012, ADAMS 9 Accession No. ML12104A193 and "Standard Technical Specifications, General Electric BWR/6 10 Plants, BWR/6" NUREG-1434, Volume 2, "Bases," Revision 4.0, April 2012, ADAMS Accession 11 No. ML12104A196. The changes would be incorporated into future revisions of NUREG-1433, 12 Volume 2, and NUREG-1434, Volume 2. A summary of the changes and the staff's evaluation 13 of those changes are presented in this Attachment. 14 15

2.0 REGULATORY EVALUATION

16 17 2.1 Applicable Regulations and Guidance 18 19 The regulation at 10 CFR 50.36(a)(1) states that each applicant for a license authorizing 20 operation of a production or utilization facility shall include in his application proposed technical 21 specifications in accordance with the requirements of this section. A summary statement of the 22 bases or reasons for such specifications, other than those covering administrative controls, shall 23 also be included in the application, but shall not become part of the technical specifications. 24 25 In its Final Policy Statement on Technical Specifications Improvements for Nuclear Power 26 Reactors, the Commission presented its policy on the scope and purpose of the Technical 27 Specifications. The Commission explained how implementation of the policy statement through 28 implementation of the improved STS is expected to produce an improvement in the safety of 29 nuclear power plants through the use of more operator-oriented TS, improved TS Bases, 30 reduced action-statement-induced plant transients, and more efficient use of NRC and industry 31 resources. 32 33 The Final Policy Statement provides the following description of the scope and the purpose of 34 the Technical Specification Bases: 35 36 Appropriate Surveillance Requirements and Actions should be 37 retained for each LCO which remains or is included in the 38 Technical Specifications. Each LCO, Action, and Surveillance 39 Requirement should have supporting Bases. The Bases should at 40 a minimum address the following questions and cite references to 41 appropriate licensing documentation (e.g., FSAR, Topical Report) 42 to support the Bases. 43 44 1. What is the justification for the Technical Specification, i.e., which 1 Policy Statement criterion requires it to be in the Technical 2 Specifications? 3 4 2. What are the Bases for each LCO, i.e., why was it determined to 5 be the lowest functional capability or performance level for the 6 system or component in question necessary for safe operation of 7 the facility and, what are the reasons for the Applicability of the 8 LCO? 9 10 3. What are the Bases for each Action, i.e., why should this remedial 11 action be taken if the associated LCO cannot be met; how does 12 this Action relate to other Actions associated with the LCO; and 13 what justifies continued operation of the system or component at 14 the reduced state from the state specified in the LCO for the 15 allowed time period? 16 17 4. What are the Bases for each Safety Limit? 18 19 5. What are the Bases for each Surveillance Requirement and 20 Surveillance Frequency; i.e., what specific functional requirement 21 is the surveillance designed to verify? Why is this surveillance 22 necessary at the specified frequency to assure that the system or 23 component function is maintained, that facility operation will be 24 within the Safety Limits, and that the LCO will be met? 25 26 Note: In answering these questions the Bases for each number 27 (e.g., Allowable Value, Response Time, Completion Time, 28 Surveillance Frequency), state, condition, and definition (e.g., 29 operability) should be clearly specified. As an example, a number 30 might be based on engineering judgment, past experience, or 31 PSA insights; but this should be clearly stated. 32 33 The NRC staff used the guidance contained in the Final Policy Statement during its review of 34 the proposed changes to the Bases. 35 36 2.2 Description of Changes 37 38 Volume 2 NUREGs-1433 and -1434 contain the Bases for each Safety Limit and each LCO 39 contained in Volume 1. The Bases for each LCO is organized into sections: 40 41 Background 42 Applicable Safety Analyses, LCO, and Applicability 1 Actions 2 Surveillance Requirements 3 References 4 5 The Bases for LCOs 3.3.5.2 (A and B) and 3.5.2 were rewritten in their entirety to reflect the 6 changes in the associated LCOs. The Bases for the remainder of the affected LCOs were 7 modified to reflect the deletion of OPDRVs. 8 9 In the following sections, the discussion is applicable to both NUREG 1433 (for BWR/4 plants) 10 and NUREG 1434 (for BWR/6 plants) unless otherwise noted. The discussion provides a 11 summary of the revised Bases, followed by the NRC staff's evaluation of the revised Bases. 12 13

3.0 TECHNICAL EVALUATION

14 15 3.1 Evaluation of B 3.3.5.2 (A) and B 3.3.5.2 (B) 16 17 B 3.3.5.2(A) is applicable in the absence of a Setpoint Control Program, and B 3.3.5.2(B) is 18 applicable if a Setpoint Control Program is used. For simplicity in presentation, the description 19 provided below applies to both the (A) and (B) versions, unless otherwise stated. 20 21 The Background section provides: 22 23

a description of the reactor pressure vessel (RPV) design, which includes penetrations 24 below the top of active fuel.

25

a description of Safety Limit 2.1.1.3, which requires the RPV water level to be above the 26 top of active fuel.

27

an explanation of the purpose of the RPV water Inventory Control Instrumentation, which 28 is to support the requirements of LCO 3.5.2, Reactor Pressure Vessel Water Inventory 29 Control by ensuring that the functions required for manual initiation of required 30 Emergency Core Cooling System (ECCS) injection/spray subsystem are available and 31 that other functions supporting isolation of flowpath(s) on low RPV level are available.

32 33 The Applicable Safety Analyses, LCO and Applicability section provides: 34 35

a statement that indicates that water inventory control is required in Modes 4 and 5 to 36 protect Safety Limit 2.1.1.3 and a discussion that due to the reduced Reactor Coolant 37 System (RCS) pressure in the shutdown condition, a very large break in the RCS is not 38 postulated in the shutdown condition.

39

an explanation that this LCO is applicable in Modes 4 and 5 to support operability of 40 subsystems required to be operable in Modes 4 and 5 as specified in LCO 3.5.2.

41

a description of why the LCO meets Criterion 4 specified in 10 CFR 50.36(c)(2(ii) as a 1 structure, system or component which operating experience has shown to be significant 2 to public health and safety.

3

a detailed discussion regarding each function contained in LCO 3.3.5.2.

4 5 o Core Spray and Low Pressure Coolant Injection Systems: 6 Function 1.a, 2.a Reactor Steam Dome Pressure - Low (Injection 7 Permissive) is required to be Operable to ensure the capability of initiating 8 ECCS when pressure is below the injection subsystems design pressure. 9 The actuation logic is one out of two taken twice, four channels are 10 required to be operable. 11 For BWR/4s, Function 1.b, 2.b Core Spray and Low Pressure Coolant 12 Injection Pump Discharge Flow - Low (Bypass) is required to be operable 13 to ensure minimum flow line is available to protect the associated low 14 pressure ECCS pump from overheating on low discharge and to ensure 15 closure of the minimum flow valve is initiated at the proper point to ensure 16 full injection flow when required. One channel per required pump is 17 required to be operable. 18 For BWR/6s, Function 1.b, 1.c, 2.b Low Pressure Coolant Injection and 19 Low Pressure Core Spray pump Discharge Flow - Low (Bypass) is 20 required to be operable to ensure minimum flow line is available to protect 21 the associated low pressure ECCS pump from overheating on low 22 discharge and to ensure closure of the minimum flow valve is initiated at 23 the proper point to ensure full injection flow when required. One channel 24 per required pump is required to be operable. 25 Function 1.c (for BWR/4), 1.d (for BWR/6) 2.c, Manual Initiation, is 26 required to be operable to provide manual initiation capability. One 27 channel (pushbutton) per required subsystem is required to be operable 28 per ECCS subsystem required to be operable. 29 30 o For BWR/6, High Pressure Core Spray System: 31 Function 3.a, Reactor Vessel Water Level - High, Level 8 is used to close 32 the HPCS injection valve to prevent overflow into the main steam lines. 33 One channel associated with the HPCS system required by LCO 3.5.2 is 34 required to be operable. The allowable value is chosen to ensure no 35 overflow into the main steam lines. 36 Function 3.b, Condensate Storage Tank (CST) Level, Low indicates low 37 supply of makeup water from this source. HPCS is normally aligned to 38 take suction on the CST. On low CST level, the HPCS pump suction 39 valves from the suppression pool open and then the suction valves from 40 the CST close. One channel is required to be operable when HPCS is 41 required per LCO 3.5.2 and the HPCS is aligned to the CST. The 1 allowable value is selected to ensure adequate pump suction head. 2 Function 3.c., 3.d HPCS Pump Discharge Pressure - High (Bypass) and 3 HPCS System Flow Rate - Low (Bypass) is required to be operable to 4 ensure minimum flow line is available to protect the associated HPCS 5 pump from overheating on low discharge. The allowable value is set to 6 ensure the flow is sufficient to protect the pump, but closes when a 7 minimum flow is reached to ensure full injection flow into the core. One 8 channel is required when HPCS is required to be operable per LOC 3.5.2. 9 Function 3.e, Manual Initiation, is required to be operable to ensure 10 manual initiation capability. One channel is required when the associated 11 ECCS subsystem is required by LCO 3.5.2. 12 13 o RHR System Isolation: 14 Function 3.a (for BWR/4) and 4.a (for BWR/6), Reactor Vessel Water 15 Level - Low Level 3 may be credited for automatic isolation of penetration 16 flow paths associated with the RHR system. The function is required to 17 be operable when automatic isolation of the associated penetration flow 18 path is assumed in the calculated Drain Time. Two channels in the same 19 trip system are required to be operable. 20 21 o Reactor Water Cleanup (RWCU) System Isolation: 22 Function 4.a (for BWR/4) and 5.a (for BWR/6), Reactor Vessel Water 23 level - Low Low, Level 2 may be credited for automatic isolation of 24 penetration flow paths associated with the RWCU System. This function 25 is required to be operable when automat ic isolation of the associated 26 penetration flow path is assumed in the calculated Drain Time. Two 27 channels in the same trip system are required to be operable. 28 The Allowable Value selected is the same as the Allowable Value during 29 Power Operation. 30 31

an explanation of each Required Action and Completion Time contained in the Actions 32 Table. 33 34 o For BWR/4s:

35 Condition A is entered when a channel is declared inoperable and 36 Required Action A.1 directs entry into the Appropriate Condition. 37 Condition B is entered when Functions 1.a, 2.a, 1.b or 2.b are inoperable. 38 The Required Action is to declare the associated penetration flow path 39 incapable of automatic isolation and to recalculate the Drain Time without 40 taking credit for the automatic isolation of the affect pathway. 41 Condition C is entered when the steam dome pressure signal permissive 1 is inoperable. Inoperability of the permissive means that the injection 2 function cannot be manually initiated. The Required Action is to place the 3 permissive in the tripped condition within one hour. This enables manual 4 initiation of the injection function. The one hour allowance provides 5 sufficient time for the operator to place the channel in trip. 6 Condition D is entered when the Core Spray or Low Pressure Coolant 7 Injection Pump Discharge Flow - Low bypass functions are unavailable. 8 In this condition, the Required Action is to restore the channel to operable 9 status within 24 hours. The 24 hour is judged to be appropriate because 10 manual operation of the pumps and the minimum flow valves is still 11 available, but this is not the preferred condition. 12 Condition E is entered when the Required Action and associated 13 Completion Time for Condition C or D is not met. In this case, the 14 associated ECCS subsystem may not be capable of performing its 15 intended function, and is declared inoperable immediately. 16 17 o For BWR/6s: 18 Condition A is entered when a channel is declared inoperable and 19 Required Action A.1 directs entry into the Appropriate Condition. 20 Condition B is entered when the RHR System Isolation or RWCU System 21 Isolation functions are inoperable. The Required Action is to declare the 22 associated penetration flow path incapable of automatic isolation and to 23 recalculate the Drain Time without taking credit for the automatic isolation 24 of the affect pathway. 25 Condition C is entered when the Steam Dome Low Pressure Signal 26 (Injection Permissive) is inoperable. Inoperability of the permissive 27 means that the injection function cannot be manually initiated. The 28 Required Action is to place the permissive in the tripped condition within 29 one hour. This enables manual initiation of the injection function. The 30 one hour allowance provides sufficient time for the operator to place the 31 channel in trip. 32 Condition D is entered when the CST Level - Low function is inoperable. 33 The Required Action is to declare HPCS system inoperable and to align 34 the HPCS pump suction to the suppression pool within 1 hour. 35 Condition E is entered when the Reactor Vessel Water Level - High - 36 Level 8 function is inoperable. The Required Action is to declare HPCS 37 system inoperable within 1 hour and to restore the channel to operable 38 status within 24 hours. 39 Condition F is entered when the LPCS Pump Discharge Flow - Low 40 (Bypass), LPCI Pump A Discharge Flow - Low (Bypass), LPCI Pump B 41 and LPCI pump C Discharge Flow - Low (Bypass), HPCS Pump 42 Discharge Pressure - High (Bypass), HPCS System Flow rate - Low 1 (Bypass) or any of the required Manual functions are inoperable. The 2 Required Action is to restore the channel to operable status within 24 3 hours. The 24 hour is judged to be appropriate because manual 4 operation of the pumps and the minimum flow valves is still available, but 5 this is not the preferred condition. 6 Condition G is entered when the Required Action and associated 7 Completion Time for Condition C, D, E or F is not met. In this case, the 8 associated ECCS subsystem may not be capable of performing its 9 intended function, and is declared inoperable immediately. 10 11 The Surveillance Requirements section provides: 12 13

a description of the purpose of each Surveillance Requirement and the basis for the 14 surveillance frequency selected. For each function.

15 o A channel check is performed to verify that a gross failure of an instrument 16 channel has not occurred. Agreement criteria is established based on channel 17 instrument uncertainties and readability. The surveillance is performed once per 18 12 hours or in accordance with the Surveillance Frequency Control Program. 19 The frequency was selected based on operating experience that indicates 20 channel failure is rare. 21 o A channel functional test is performed to verify the channel is capable of 22 performing its intended function. The surveillance is performed once per 92 days 23 or in accordance with the Surveillance Frequency Control Program. The 24 frequency was selected based on operating experience that indicates channel 25 failure is rare. 26 o A logic system functional test is performed to verify proper functioning of the 27 required initiation logic for a channel. The surveillance is performed once per 18 28 months or in accordance with the Surveillance Frequency Control Program. The 29 frequency was selected because of the preference to perform the surveillance 30 under shutdown conditions. 31 32 The References section provides lists Regulatory Guide 1.105, "Setpoints for Safety-Related 33 Instrumentation," and NEDE-770-06-2, "Addendum to Bases for Changes to Surveillance Test 34 Intervals and Allowed Out-of-Service Times for Selected instrumentation Technical 35 Specifications." 36 37 The staff reviewed the revised bases to ensure the applicable criteria from 10 CFR 50.36 is 38 identified and justified. The revised bases state that the proposed LCO meets the Criterion 4 39 specified in 10 CFR 50.36(c)(2(ii) and provides a discussion of why this Criterion applies. The 40 reasons for the selection of each instrument function and required number of channels in the 41 LCO is described and the reason for the applicable modes is stated. Each instrument function 42 is necessary to support operability of the equipment required by LCO 3.5.2, and the applicable 1 modes are consistent with those in LCO 3.5.2. The purpose of each required action is 2 described. The purpose of each instrument surveillance and the basis for the performance 3 frequency is addressed, and appropriate references are cited. The staff concluded that each of 4 the elements of the Final Policy Statement were satisfactorily addressed. Therefore, the staff 5 determined that the revised Bases adhere to the guidance provided in the Final Policy 6 Statement. 7 8 3.2 EVALUATION OF B 3.5.2 9 10 The Background section provides: 11 12

a description of the reactor pressure vessel (RPV) design, which includes penetrations 13 below the top of active fuel.

14

a description of Safety Limit 2.1.1.3, which requires the RPV water level to be above the 15 top of active fuel.

16 17 The Applicable Safety Analyses, LCO and Applicability section provides: 18 19

a statement that indicates that water inventory control is required in Modes 4 and 5 to 20 protect Safety Limit 2.1.1.3 and a discussion that due to the reduced RCS pressure in 21 the shutdown condition, a very large break in the RCS is not postulated in the shutdown 22 condition.

23

an explanation that one low pressure ECCS injection/spray subsystem can maintain 24 adequate RPV level (explanation retained from previous Bases for LCO 3.5.2).

25

a description of why the LCO meets Criterion 4 specified in 10 CFR 50.36(c)(2(ii) as a 26 structure, system or component which operating experience has shown to be significant 27 to public health and safety.

28

an explanation that a Drain Time of 36 hours was selected for the LCO because this 29 time period is reasonable for the operator to identify and initiate remedial measures.

30

an explanation that the LCO also requires one low pressure ECCS injection/spray 31 subsystem to be operable and capable of being manually started so that it is available 32 should an unexpected drain event occur. The ECCS injection/spray subsystem may be 33 considered operable during alignment for decay heat removal because the restriction on 34 drain time ensures sufficient time is available to initiate LPCI operation to maintain 35 inventory if required.

36

an explanation of each Required Action and Completion Time contained in the Actions 37 Table 38 o Condition A is entered if the required ECCS injection/spray subsystem is 39 inoperable. The Required Action is to restore it to Operable status within 4 40 hours. The 4 hour Completion Time is judged to be appropriate because of the 41 controls on Drain Time and the low probably of a drain event occurring.

42 o Condition B is entered if the Required Action and Completion Time of Condition 1 A is not met. Condition B requires establishing an alternate method of water 2 injection capable of injecting without the use of offsite power, with attendant 3 necessary support equipment, and access to water inventory capable of 4 maintaining the RPV water level above TAF for 36 hours. The Completion Time 5 is immediately. 6 o Condition C is entered if the drain time is less than 36 hours but greater than or 7 equal to 8 hours. The Required Actions associated with this Condition ensure 8 the availability of compensatory actions should an unexpected drain event occur. 9 The Required Actions include actions to ensure the secondary containment 10 boundary can be restored in less than the Drain Time to provide a volume to 11 contain, dilute and process radioactive materials if an unexpected drain event 12 were to occur. The Actions also include verification of the ability to place the 13 Standby Gas Treatment System in service within the Drain Time to provide a 14 means to maintain the secondary containment volume at a negative pressure 15 and to filter the contents prior to release. A Completion Time of 4 hours was 16 selected for these verifications because this ensures that the actions are 17 completed well within the minimum Drain Time of 8 hours. 18 o Condition D is entered if the drain time is less than 8 hours. When the Drain 19 Time is this short, mitigating actions as well as compensatory actions are 20 needed. The Required Actions include an immediate action to establish an 21 additional method of water injection. This method is in addition to the injection 22 method required by the LCO. The Required Actions include the compensatory 23 actions of immediately establishing the secondary containment boundary, 24 verifying secondary containment penetrations can be isolated, and verifying that 25 at least one Standby Gas Treatment subsystem can be placed into operation. 26 These Actions are performed immediately because of the short Drain Time. 27 o Condition E is also applicable when Drain Time is less than 1 hour. The 28 Required Action is to immediately restore the Drain Time to greater than 36 29 hours. Restoration of the Drain Time to 36 hours is necessary to ensure there is 30 adequate time to perform mitigating actions should an unexpected drain event 31 occur. 32 33 The Surveillance Requirements section provides: 34 35

a description of the purpose of each Surveillance Requirement and the basis for the 36 surveillance frequency selected.

37 o The Drain Time is required to be verified to be 36 hours once per 12 hours or in 38 accordance with the Surveillance Frequency Control Program. This Surveillance 39 verifies the LCO for Drain Time is met. The frequency is selected based on the 40 fact that numerous indications of changes in RPV level are available to the 41 operator. Changes in RPV level would necessitate recalculation of the Drain 1 Time. 2 o The suppression pool water level for a required LPCI subsystem, or suppression 3 pool water level or Condensate Storage Tank level for a required core spray 4 subsystem is required to be verified to ensure net positive suction head is 5 available for the ECCS injection/spray subsystem required to be operable by the 6 LCO. This Surveillance is required to be performed once per 12 hours or in 7 accordance with the Surveillance Frequency Control Program. The frequency 8 was chosen based on the availability of other indications available in the Control 9 Room regarding suppression pool water level and Condensate Storage Tank 10 level. 11 o The surveillance requirements to verify the piping is full of water and to verify 12 correct valve alignment was retained from the existing TS 3.5.2. 13 o The required ECCS injection/spray subsystem is required to be operated through 14 its recirculation line for 10 minutes every 92 days or in accordance with the 15 Surveillance Frequency Control Program. This demonstrates that the subsystem 16 is capable for operation. The time limit is based on engineering judgement. The 17 frequency is consistent with other at-power testing. 18 o Verification that valves credited for automatically isolating a penetration flow path 19 actuate to a simulated actuation signal is required every 18 months or 20 accordance with the Surveillance Frequency Control Program. The frequency 21 was selected because it is desirable to perform the surveillance during shutdown 22 conditions to avoid operational transients. 23 o Verification that the required ECCS injection/spray subsystem actuate on a 24 manual actuation signal is required every 18 months or accordance with the 25 Surveillance Frequency Control Program. The frequency was selected because 26 it is desirable to perform the surveillance during shutdown conditions to avoid 27 operational transients. 28 29 The References section cites the applicable operating generic correspondence describing 30 operating experience related to inventory control during shutdown conditions. It lists Information 31 Notice 84-81 "Inadvertent Reduction in Primary Coolant Inventory in Boiling Water Reactors 32 During Shutdown and Startup," November 1984; Information Notice 86-74, "Reduction of 33 Reactor Coolant Inventory Because of Misalignment of RHR Valves," August 1986; Generic 34 Letter 92-04, "Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation 35 in BWRs Pursuant to 10 CFR 50.54(F), " August 1992; NRC Bulletin 93-03, "Resolution of 36 Issues Related to Reactor Vessel Water Level Instrumentation in BWRs," May 1993; 37 Information Notice 94-52, "Inadvertent Containment Spray and Reactor Vessel Draindown at 38 Millstone 1," July 1994; and General Electric Service Information Letter No. 388, "RHR Valve 39 Misalignment During Shutdown Cooling Operation for BWR 3/4/5/6," February 1983. 40 41 The revised Bases (Volume 2 of NUREG 1434) for TS 3.5.2 for the BWR/6 differ from the 1 revised Bases for the BWR/4 TS. The major difference is that the LCO requires one ECCS 2 injection/spray subsystem to be operable. The ECCS injection/spray subsystem is either one of 3 the three Low Pressure Coolant Injection subsystems, one Low Pressure Core Spray System, 4 or one High Pressure Core Spray System. This difference is reflected throughout the Bases for 5 TS 3.5.2 in NUREG 1434, Volume 2. 6 7 The staff reviewed the revised bases to ensure the applicable criterion from 10 CFR 50.36 is 8 identified and justified, the reasons for the selection of each instrument function and required 9 number of channels in the LCO is described, the reason for the applicable modes is stated, the 10 purpose of each required action is described, and the purpose of each surveillance and the 11 basis for the performance frequency is addressed, and appropriate references are cited. The 12 staff concluded that each of the elements of the Final Policy Statement were satisfactorily 13 addressed. Therefore, the staff determined that the revised Bases adheres to the guidance 14 provided in the Final Policy Statement. 15 16 3.3 EVALUATION OF ADDITIONAL BASES CHANGES 17 18 3.3.1 B 3.3.5.1, ECCS Instrumentation 19 20 The Bases for several instrument functions related to automatic ECCS initiation were revised to 21 reflect a revised Applicability. The functions would no longer be required during Modes 4 and 5 22 because of the relatively slow transient of unexpected drain events. It is judged that sufficient 23 time is permitted for operators to mitigate such a transient. The instrumentation affected for 24 BWR/4s are Reactor Vessel Water Level - Low Low Low, Level 1; Low Pressure Coolant 25 Injection (LPCI) System Reactor Vessel Water Level - Low Low Low, Level 1; and Low 26 Pressure Coolant Injection Pump Start - Time Delay Relay. For BWR/6's, the affected 27 functions are LPCI A and LPCS: Reactor Vessel Water Level - Low Low Low, Level 1; LPCI 28 Pump A Start - Time Delay Relay; LPCI B and C: Reactor Vessel Water Level - Low Low Low, 29 Level 1; LPCI Pump B Start - Time Delay Relay; and HPCS Reactor Vessel Water Level Lo 30 Low, Level 2. 31 32 The remainder of the changes to the Bases for this LCO reflect the relocation of instrumentation 33 function requirements to the LCO 3.3.5.2. 34 35 3.3.2 B 3.3.6.1, Primary Containment Isolation Instrumentation 36 37 The Bases for the Shutdown Cooling Isolation, Reactor Vessel Water Level - Low, Level 3 were 38 revised to reflect the relocation of this requirement to LCO 3.3.5.2. 39 40 For BWR/6's, the function for Primary Containment Isolation, Containment and Drywell 41 Ventilation Exhaust Radiation - High is revised to reflect the deletion of this requirement. 42 1 3.3.3 B 3.5.3, RCIC System 2 3 The Applicability was revised to state that in Modes 4 and 5, RPV water inventory control is 4 provided by LCO 3.5.2. 5 6 3.3.4 B 3.6.1.3, PCIVs [Primary Containment Isolation Valves] 7 8 The Applicability was changed to replace the statement that certain valves are required to be 9 operable to prevent inadvertent drain down to state that certain valves are required to be 10 operable when the associated instrumentation is required to be operable. 11 12 The description of the Applicability and Actions is revised to delete the discussion of OPDRVs. 13 14 3.3.5 Other Affected Bases 15 16 The description of the Applicability, Actions and Applicable Safety Analyses Sections are 17 revised to delete the discussion of OPDRVs or inadvertent drain down of the vessel for the 18 following LCOs: 19 20

3.3.6.1 Primary Containment Isolation Instrumentation 21
3.5.1 ECCS - Operating 22
3.6.2.2 Suppression Pool Water Level 23
3.6.4.1 [Secondary] Containment 24
3.6.4.2 SCIVs [Secondary Containment Isolation Valves]

25

3.6.4.3 SGT System [Standby Gas Treatment]

26

3.7.4 MCREC [Main Control Room Environmental Control] System 27
3.7.5 Control Room AC [Air Conditioning] System 28
3.8.2 AC Sources - Shutdown 29
3.8.5 DC Sources - Shutdown 30
3.8.8 Inverters - Shutdown 31
3.8.10 Distribution Systems - Shutdown 32
3.10.1 Inservice Leak and Hydrostatic Testing Operation 33 34 The NRC staff reviewed the revised Bases sections and concluded that the revisions accurately 35 reflect the changes contained in the associated LCO's. The Applicability, Actions and 36 Applicable Safety Analyses sections continue to contain information regarding the reasons for 37 each of the LCO requirements. The staff determined that the Bases for the LCO's continue to 38 satisfy the guidance in the Final Policy Statement.

39 40

4.0 CONCLUSION

41 42 The NRC staff determined that TS Bases changes are consistent with the proposed TS changes 1 and provide an explanation and supporting information for each requirement in the specification. 2 Therefore, the staff determined that the revised Bases are consistent with the Commission's 3 Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, 4 dated July 2, 1993 (58 FR 39132). 5 6}}

@@ Line 2: / Line 2: @@
 | number = ML16175A394
 | issue date = 10/06/2016
-| title = Draft Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (TAC No. MF3487)
+| title = Draft Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
 | author name = Hsueh K P
 | author affiliation = NRC/NRR/DPR/PLPB

v t e Letter Sequence Draft Approval
TAC:MF3487, Reactor Pressure Vessel Water Inventory Control (Approved, Closed)
Initiation Request Acceptance Administration Meeting Questions 8 December 2015 Answers 15 September 2015 14 March 2016 Results Approval, Approval Other:
MONTHYEAR2015-09-15 [Table View]

ML16175A394: Difference between revisions

Revision as of 21:01, 6 February 2019

Text

SUBJECT:

Dear Members of the Technical Specifications Task Force:

Enclosures:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

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ML16175A394: Difference between revisions

Revision as of 21:01, 6 February 2019

Text

SUBJECT:

Dear Members of the Technical Specifications Task Force:

Enclosures:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

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