PLA-7979, Supplement to License Amendment to Revise Reactor Steam Dome Pressure Low Instrumentation Function Allowable Value

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Supplement to License Amendment to Revise Reactor Steam Dome Pressure Low Instrumentation Function Allowable Value
ML21350A265
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 12/16/2021
From: Cimorelli K
Susquehanna, Talen Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7979
Download: ML21350A265 (17)
v • d • e


Text

Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com December 16, 2021 Attn: Document Control Desk 10 CFR 50.90 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUPPLEMENT TO LICENSE AMENDMENT TO REVISE REACTOR STEAM DOME PRESSURE -

LOW INSTRUMENTATION FUNCTION ALLOWABLE VALUE Docket No. 50-387 PLA-7979 and 50-388

References:

1) Susquehanna letter to NRC, Proposed Amendment to Licenses NPF-14 and NPF-22: Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-7950), dated October 5, 2021 (ADAMS Accession No. ML21279A026).
2) NRC letter to Susquehanna, Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Emergency Core Cooling Technical Specifications (EPID L-2021-LLA-0184), dated November 18, 2021 (ADAMS Accession No. ML21316A124).

Pursuant to 10 CFR 50.90, Susquehanna Nuclear, LLC (Susquehanna), submitted, in Reference 1, a request for an amendment to the Technical Specifications (TS) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2, Facility Operating License numbers NPF-14 and NPF-22. The proposed amendment would modify TS 3.3.5.1, Emergency Core Cooling Systems (ECCS) Instrumentation. Specifically, the proposed amendment would modify the TS Allowable Values (AVs) for the ECCS Instrumentation, Core Spray and Low Pressure Coolant Injection Reactor Steam Dome Pressure - Low Instrumentation Functions 1.c, 1.d, 2.c, and 2.d, in TS Table 3.3.5.1-1.

The NRC notified Susquehanna in Reference 2 that additional information was required to complete its acceptance review of the application submitted in Reference 1. Enclosure 1 to this letter provides the requested information. As a result of the information provided in Enclosure 1 to this submittal, Susquehanna determined it was necessary to revise the TS changes requested

Document Control Desk PLA-7979 in Reference 1. Enclosures 2 and 3 provide the revised TS pages necessary to support the information provided in Enclosure 1 to this letter. Enclosures 2 and 3 of this letter supersede Enclosures 2 and 3 of Reference 1, respectively, in their entirety.

Based on the revised TS changes provided in Enclosures 2 and 3 to this letter, Susquehanna determined that no TS Bases changes are required to support the requested license amendment.

Therefore, Susquehanna withdraws the marked-up TS Bases pages provided in Enclosure 4 to Reference 1 and will not provide a replacement Enclosure in this letter.

Susquehanna has reviewed the information supporting a finding of No Significant Hazards Consideration and the Environmental Consideration provided to the NRC in Reference 1 and detennined the information provided herein does not impact the original conclusions in Reference 1.

There are no new or revised regulatory commitments contained in this submittal.

Should you have any questions regarding this submittal, please contact Ms. Melisa Krick, Manager-Nuclear Regulatory Affairs, at (570) 542-1818.

I declare under penalty of pe1jury that the foregoing is true and correct.

Executed on December 16, 2021.

~

K. Cimorelli

Enclosures:

1. Supplemental Information
2. Marked-Up Technical Specification Pages
3. Revised (Clean) Technical Specification Pages Copy: NRC Region I Mr. C. Highley, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP

Enclosure 1 to PLA-7979 Supplemental Information

Enclosure 1 to PLA-7979 Page 1 of 4 Supplemental Information On October 5, 2021, Susquehanna Nuclear, LLC (Susquehanna) submitted a license amendment request (LAR) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2 in Reference 1.

Specifically, Susquehanna requested a revision to Technical Specification (TS) 3.3.5.1, Emergency Core Cooling Systems (ECCS) Instrumentation. The proposed amendment would modify the TS Allowable Values (AVs) for the ECCS Instrumentation, Core Spray and Low Pressure Coolant Injection (LPCI) Reactor Steam Dome Pressure - Low Instrumentation Functions 1.c, 1.d, 2.c, and 2.d, in TS Table 3.3.5.1-1. In Reference 2, the NRC identified that additional information is required to complete its acceptance review of the LAR. The supplemental information requested by the NRC is provided below.

NRC Question 1 The core spray (CS) and low-pressure core injection (LPCI) subsystems are part of the ECCS.

At Susquehanna, one check valve and one power-operated pressure isolation valve (PIV) are available on the discharge side in each applicable piping of the CS and LPCI subsystems to isolate the subsystems from the RCS. The PIVs are normally closed and would open on a low reactor steam dome pressure signal, which is limited by a lower allowable value (AV) and an upper AV in TS Table 3.3.5.1-1, Functions 1.c, 1.d, 2.c, and 2.d. The incorporation of the lower AV in the TSs provides reasonable assurance that the CS and LPCI provide coolant to the RCS during a loss-of-coolant accident and satisfy the ECCS performance criteria in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46. The upper AV in the TSs provides reasonable assurance of RCS isolation. The proposed TS changes would delete the upper AV from the TSs.

NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition, Branch Technical Position (BTP) 5-4, Design Requirements of the Residual Heat Removal System, Revision 4 (ADAMS Accession No. ML070850123), Section B.2.B.ii describes an acceptable approach for isolating the discharge side of the residual heat removal system from the RCS (i.e., that one or more check valves in series with a normally power-operated PIV shall be provided on the discharge side of the residual heat removal and LPCI subsystems to isolate them from the RCS.

Therefore, the NRC staff needs additional information to evaluate the impact of removing the TS requirement for the upper AV on the ability to isolate the RCS. The NRC staff needs additional information that would allow the NRC staff to determine if there is reasonable assurance that the PIVs would remain closed above the upper AV value.

Enclosure 1 to PLA-7979 Page 2 of 4 Susquehanna Response In order to demonstrate reasonable assurance that the PIVs would remain closed above the upper AV, Susquehanna proposes to re-establish the upper AV for SSES, Unit 1 and 2, TS Table 3.3.5.1-1, Functions 1.c, 1.d, 2.c, and 2.d. The Upper Analytical Limit (AL) will be increased from the current value of 440 psig to 445 psig. As stated in Reference 1, the design pressure is 450 psig for the Residual Heat Removal (RHR) System low pressure piping and 500 psig for the Core Spray (CS) System low pressure piping. NRC Safety Evaluations for Unit 1 TS Amendment 181 (Reference 3) and Unit 2 TS Amendment 155 (Reference 4) state:

The CS system and LPCI system initiation logic has a low-pressure permissive function which prevents the CS system injection valves HV-252-F005A/B and the LPCI system injection valves HV-251-F017A/B from opening until reactor pressure has decreased to the system's design pressure.

The selected upper AL meets the requirement stated in the Safety Evaluations which is also consistent with the SSES Updated Final Safety Analysis Report, Section 7.6.1a.3.3.1.

The lower AL remains the same as stated in Reference 1; i.e., 380 psig.

The upper and lower AVs and Nominal Trip Setpoints (NTSPs) were calculated using the NRC approved General Electric topical report NEDC-31336P-A. As stated in Reference 1, the pressure switches were replaced with Cameron-Barton 288A switches in 2017. The revised evaluations use the reported vendor accuracy for the newly installed switches in the calculation of the upper and lower AV and NTSP. The new values are shown in Table 1. Note that Table 1 below provides the currently approved values, the originally proposed values in Reference 1, and the revised proposed values as calculated for this supplement.

Table 1 - Changes to Calculated Parameters Original Revised Current Parameter Proposed Proposed (psig)

(psig) (psig)

Upper Analytical Limit 440 NONE 445 Upper Allowable Value 433 NONE 443 Upper Nominal Trip Setpoint 427 NONE 428.5 Setpoint 420 420 412.5 Lower Nominal Trip Setpoint 413 393 396.5 Lower Allowable Value 407 387 382 Lower Analytical Limit 400 380 380

Enclosure 1 to PLA-7979 Page 3 of 4 Re-establishing the upper AV for SSES Unit 1 and 2 TS Table 3.3.5.1-1, Functions 1.c, 1.d, 2.c, and 2.d will provide reasonable assurance that the PIVs will remain closed above the upper AV.

As a result of re-establishing the upper AV, Susquehanna proposes to lower the revised lower AV from 387 psig (as proposed in Reference 1) to 382 psig. This change utilizes some of the existing margin between the lower AV and the lower AL while still ensuring the fuel peak clad temperature will not exceed 2200°F during a postulated accident.

Susquehanna has revised the TS markups to reflect re-establishment of the upper AV, and revision of the lower AV from what was provided in Enclosures 2 and 3 of Reference 1.

Enclosures 2 and 3 to this letter provide the revised TS pages, and supersede Enclosures 2 and 3 of Reference 1, respectively, in their entirety. Further, based on re-establishment of the upper AV, Susquehanna has determined that no TS Bases changes are required to support the proposed license amendment. Therefore, Susquehanna hereby withdraws the marked-up TS Bases pages provided in Enclosure 4 to Reference 1 in their entirety; a replacement enclosure is not necessary and is not being provided with this letter.

NRC Question 2 The submittal indicated that pressure relief valves (PRVs) are available for protecting the CS and LPCI systems from over-pressurization. However, the submittal does not describe the adequacy of the PRVs capability to prevent over-pressurization of the low pressure piping from a loss of isolation between the RCS and low pressure piping.

If the licensee cannot show that the PIVs would remain closed above the upper AV value, then the NRC staff needs additional information for determining if there is reasonable assurance that the PRVs would protect the low pressure piping from over-pressurization when the PIVs and check valves cannot be closed.

Susquehanna Response As described in the response to Question 1, the PIVs are ensured to remain closed by retaining a revised upper AV within the TS. Therefore, additional information regarding the reasonable assurance that PRVs would protect the low pressure piping from over-pressurization when the PIVs and check valves cannot be closed is not required.

Enclosure 1 to PLA-7979 Page 4 of 4 References

1. Susquehanna letter to NRC, Proposed Amendment to Licenses NPF-14 and NPF-22: Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-7950), dated October 5, 2021 (ADAMS Accession No. ML21279A026).
2. NRC letter to Susquehanna, Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Emergency Core Cooling Technical Specifications (EPID L-2021-LLA-0184), dated November 18, 2021 (ADAMS Accession No. ML21316A124).
3. NRC letter to Susquehanna, Susquehanna Steam Electric Station, Unit 1 - Issuance of Amendment Re: Technical Specification Changes on Reactor Steam Dome Pressure - Low Allowable Value (TAC No. MA4982), dated May 25, 1999 (ADAMS Accession No. ML010160341).
4. NRC letter to Susquehanna, Susquehanna Steam Electric Station, Unit 2, Technical Specification Changes on Reactor Steam Dome Pressure - Low Allowable Value (TAC No.

MA2447), dated March 4, 1999 (ADAMS Accession No. ML010160354).

Enclosure 2 of PLA-7979 Marked-Up Technical Specification Pages Revised Technical Specifications Pages Unit 1 TS Pages 3.3-42 and 3.3-43 Unit 2 TS Pages 3.3-43 and 3.3-44

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System
a. Reactor Vessel 1, 2, 3 4(a) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5
b. Drywell Pressure - 1, 2, 3 4(a) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 407 382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (initiation) SR 3.3.5.1.5 433 443 psig (upper)

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 407 382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (injection SR 3.3.5.1.5 433 443 psig permissive) (upper)

e. Manual Initiation 1, 2, 3 2 C SR 3.3.5.1.5 NA 1 per Subsystem
2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel 1, 2, 3 4(b) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5 (a) Also required to initiate the associated diesel generator (DG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

(b) Also required to initiate the associated DGs, ESW Pump timer reset and Turbine Building and Reactor Building Chillers trip.

SUSQUEHANNA - UNIT 1 3.3-42 Amendment 178, 181, 271, XXX

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System (continued)
b. Drywell Pressure - 1, 2, 3 4(b) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 407382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (initiation) SR 3.3.5.1.5 433443 psig (upper)

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 407382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (injection SR 3.3.5.1.5 433443 psig permissive) (upper)

e. Reactor Steam 1(c), 2(c), 3(c) 4 C SR 3.3.5.1.2 216 psig Dome Pressure - SR 3.3.5.1.3 Low (Recirculation SR 3.3.5.1.5 Discharge Valve Permissive)

(b) Also required to initiate the associated DGs, ESW pump timer reset and Turbine Building and Reactor Building Chiller trip.

(c) With either associated recirculation pump discharge or bypass valves open.

SUSQUEHANNA - UNIT 1 3.3-43 Amendment 178, 181, 271, XXX

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System
a. Reactor Vessel 1, 2, 3 4(a) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5
b. Drywell Pressure - 1, 2, 3 4(a) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 407382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (initiation) SR 3.3.5.1.5 433443 psig (upper)

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 407382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (injection SR 3.3.5.1.5 433443 psig permissive) (upper)

e. Manual Initiation 1, 2, 3 2 C SR 3.3.5.1.5 NA 1 per Subsystem
2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel 1, 2, 3 4(b) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5 (a) Also required to initiate the associated diesel generator (DG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

(b) Also required to initiate the associated DGs, ESW Pump timer reset and Turbine Building and Reactor Building Chillers trip.

SUSQUEHANNA - UNIT 2 3.3-43 Amendment 151, 155, 253, XXX

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System (continued)
b. Drywell Pressure - 1, 2, 3 4(b) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 407382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (initiation) SR 3.3.5.1.5 433443 psig (upper)

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 407382 psig Dome Pressure - SR 3.3.5.1.3 (lower)

Low (injection SR 3.3.5.1.5 433443 psig permissive) (upper)

e. Reactor Steam 1(c), 2(c), 3(c) 4 C SR 3.3.5.1.2 216 psig Dome Pressure - SR 3.3.5.1.3 Low (Recirculation SR 3.3.5.1.5 Discharge Valve Permissive)
f. Manual Initiation 1, 2, 3 2 C SR 3.3.5.1.5 NA 1 per Subsystem (b) Also required to initiate the associated DGs, ESW pump timer reset and Turbine Building and Reactor Building Chiller trip.

(c) With either associated recirculation pump discharge or bypass valves open.

SUSQUEHANNA - UNIT 2 3.3-44 Amendment 151, 155, 253, XXX

Enclosure 3 of PLA-7979 Revised (Clean) Technical Specification Pages Revised Technical Specifications Pages Unit 1 TS Pages 3.3-42 and 3.3-43 Unit 2 TS Pages 3.3-43 and 3.3-44

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System
a. Reactor Vessel 1, 2, 3 4(a) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5
b. Drywell Pressure - 1, 2, 3 4(a) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (initiation) SR 3.3.5.1.5

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (injection SR 3.3.5.1.5 permissive)

e. Manual Initiation 1, 2, 3 2 C SR 3.3.5.1.5 NA 1 per Subsystem
2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel 1, 2, 3 4(b) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5 (a) Also required to initiate the associated diesel generator (DG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

(b) Also required to initiate the associated DGs, ESW Pump timer reset and Turbine Building and Reactor Building Chillers trip.

SUSQUEHANNA - UNIT 1 3.3-42 Amendment 178, 181, 271, XXX

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System (continued)
b. Drywell Pressure - 1, 2, 3 4(b) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (initiation) SR 3.3.5.1.5

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (injection SR 3.3.5.1.5 permissive)

e. Reactor Steam 1(c), 2(c), 3(c) 4 C SR 3.3.5.1.2 216 psig Dome Pressure - SR 3.3.5.1.3 Low (Recirculation SR 3.3.5.1.5 Discharge Valve Permissive)

(b) Also required to initiate the associated DGs, ESW pump timer reset and Turbine Building and Reactor Building Chiller trip.

(c) With either associated recirculation pump discharge or bypass valves open.

SUSQUEHANNA - UNIT 1 3.3-43 Amendment 178, 181, 271, XXX

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System
a. Reactor Vessel 1, 2, 3 4(a) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5
b. Drywell Pressure - 1, 2, 3 4(a) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (initiation) SR 3.3.5.1.5

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (injection SR 3.3.5.1.5 permissive)

e. Manual Initiation 1, 2, 3 2 C SR 3.3.5.1.5 NA 1 per Subsystem
2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel 1, 2, 3 4(b) B SR 3.3.5.1.1 -136 inches Water Level - Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.5 (a) Also required to initiate the associated diesel generator (DG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

(b) Also required to initiate the associated DGs, ESW Pump timer reset and Turbine Building and Reactor Building Chillers trip.

SUSQUEHANNA - UNIT 2 3.3-43 Amendment 151, 155, 253, XXX

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System (continued)
b. Drywell Pressure - 1, 2, 3 4(b) B SR 3.3.5.1.2 1.88 psig High SR 3.3.5.1.3 SR 3.3.5.1.5
c. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (initiation) SR 3.3.5.1.5

d. Reactor Steam 1, 2, 3 4 C SR 3.3.5.1.2 382 psig (lower)

Dome Pressure - SR 3.3.5.1.3 443 psig (upper)

Low (injection SR 3.3.5.1.5 permissive)

e. Reactor Steam 1(c), 2(c), 3(c) 4 C SR 3.3.5.1.2 216 psig Dome Pressure - SR 3.3.5.1.3 Low (Recirculation SR 3.3.5.1.5 Discharge Valve Permissive)
f. Manual Initiation 1, 2, 3 2 C SR 3.3.5.1.5 NA 1 per Subsystem (b) Also required to initiate the associated DGs, ESW pump timer reset and Turbine Building and Reactor Building Chiller trip.

(c) With either associated recirculation pump discharge or bypass valves open.

SUSQUEHANNA - UNIT 2 3.3-44 Amendment 151, 155, 253, XXX

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