PLA-8025, Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value

From kanterella
(Redirected from ML22222A137)
Jump to navigation Jump to search

Supplement to License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value
ML22222A137
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 08/10/2022
From: Cimorelli K
Susquehanna, Talen Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-8025
Download: ML22222A137 (9)
v • d • e


Text

Kevin Cimorelli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, P A 18603 Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@Ta1enEnergy.com TALEN~

ENERGY August 10, 2022 Attn: Document Control Desk 10 CFR50.90 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 and 50-388 PLA-8025

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 (EP ID L-2021-LLA -0 184), " dated November 18,2021 (ADAMS Accession No. ML21316A124).
3) Susquehanna letter to NRC, "Supplement to License Amendment to Revise Reactor Steam Dome Pressure -Low Instrumentation Function Allowable Value (PLA-7979), "dated December 16, 2021 (ADAMS Accession No. ML21350A265).
4) NRC email to Susquehanna, "NRC Request for Additional Information -

Susquehanna License Amendment Request (EPID L-2021-LLA-0184);" dated Apri/21, 2022 (ADAMS Accession No. ML22111A313).

5) Susquehanna letter to NRC, "Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure -Low Instrumentation Function Allowable Value (PLA-8005)," dated May 23, 2022 (ADAMS Accession No. ML22144A003).

Document Control Desk PLA-8025 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 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. In response to Reference 2, Susquehanna provided supplemental information in Reference 3, including revised TS markups which superseded those provided in Reference 1 in their entirety. Reference 5 responded to the Request for Additional Information documented in Reference 4; this response did not impact the previously provided TS markups.

Susquehanna is supplementing these responses to editorially revise the Unit 2 TS markups provided in Reference 3; the enclosed markups will supersede those provided for Unit 2 in Reference 3. The enclosed markups shift the entirety of Function 2, Low Pressure Coolant Injection (LPCI) System, to page 2 of TS Table 3.3.5.1-1. No other changes were made to the markups provided in Reference 3. The intent of the change is to align the format of Unit 1 and Unit 2 TS Table 3.3.5.1-1.

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 determined 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 perjury that the foregoing is true and correct.

Executed on August 10, 2022.

K. Cimorelli

Enclosures:

1. Marked-Up Technical Specification Pages
2. 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, PADEP/BRP Document Control Desk PLA-8025

to PLA-8025 Marked-Up Technical Specification Pages Revised Technical Specifications Pages Unit 2 TS Pages 3.3-43 and 3.3-44

ECCS Instrumentation 3.3.5.1 SUSQUEHANNA - UNIT 2 3.3-43 Amendment 151, 155, 253, XXX Table 3.3.5.1-1 (page 1 of 5)

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

1. Core Spray System
a. Reactor Vessel Water Level Low Low Low, Level 1 1, 2, 3 4(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

-136 inches

b. Drywell Pressure High 1, 2, 3 4(a)

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 1.88 psig

c. Reactor Steam Dome Pressure Low (initiation) 1, 2, 3 4

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 407 382 psig (lower) 433 443 psig (upper)

d. Reactor Steam Dome Pressure Low (injection permissive) 1, 2, 3 4

C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 407 382 psig (lower) 433 443 psig (upper)

e. Manual Initiation 1, 2, 3 2

1 per subsystem C

SR 3.3.5.1.5 NA (a) Also required to initiate the associated diesel generator (DG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

Add page break to move Function 2 to page 2.

ECCS Instrumentation 3.3.5.1 SUSQUEHANNA - UNIT 2 3.3-44 Amendment 151, 155, 256, XXX Table 3.3.5.1-1 (page 2 of 5)

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

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water Level Low Low Low, Level 1 1, 2, 3 4(b)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

-136 inches

b. Drywell Pressure High 1, 2, 3 4(b)

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 1.88 psig

c. Reactor Steam Dome Pressure Low (initiation) 1, 2, 3 4

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 407 382 psig (lower) 433 443 psig (upper)

d. Reactor Steam Dome Pressure Low (injection permissive) 1, 2, 3 4

C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 407 382 psig (lower) 433 443 psig (upper)

e. Reactor Steam Dome Pressure Low (Recirculation Discharge Valve Permissive) 1(c), 2(c), 3(c) 4 C

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 216 psig

f.

Manual Initiation 1, 2, 3 2

1 per subsystem C

SR 3.3.5.1.5 NA (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.

of PLA-8025 Revised (Clean) Technical Specification Pages Revised Technical Specifications Pages Unit 2 TS Pages 3.3-43 and 3.3-44

ECCS Instrumentation 3.3.5.1 SUSQUEHANNA - UNIT 2 3.3-43 Amendment 151, 155, 253, XXX Table 3.3.5.1-1 (page 1 of 5)

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

1. Core Spray System
a. Reactor Vessel Water Level Low Low Low, Level 1 1, 2, 3 4(a)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

-136 inches

b. Drywell Pressure High 1, 2, 3 4(a)

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 1.88 psig

c. Reactor Steam Dome Pressure Low (initiation) 1, 2, 3 4

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 382 psig (lower) 443 psig (upper)

d. Reactor Steam Dome Pressure Low (injection permissive) 1, 2, 3 4

C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 382 psig (lower) 443 psig (upper)

e. Manual Initiation 1, 2, 3 2

1 per subsystem C

SR 3.3.5.1.5 NA (a) Also required to initiate the associated diesel generator (DG), initiate Drywell Cooling Equipment Trip, and Emergency Service Water (ESW) Pump timer reset.

ECCS Instrumentation 3.3.5.1 SUSQUEHANNA - UNIT 2 3.3-44 Amendment 151, 155, 256, XXX Table 3.3.5.1-1 (page 2 of 5)

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

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water Level Low Low Low, Level 1 1, 2, 3 4(b)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

-136 inches

b. Drywell Pressure High 1, 2, 3 4(b)

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 1.88 psig

c. Reactor Steam Dome Pressure Low (initiation) 1, 2, 3 4

B SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 382 psig (lower) 443 psig (upper)

d. Reactor Steam Dome Pressure Low (injection permissive) 1, 2, 3 4

C SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 382 psig (lower) 443 psig (upper)

e. Reactor Steam Dome Pressure Low (Recirculation Discharge Valve Permissive) 1(c), 2(c), 3(c) 4 C

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 216 psig

f.

Manual Initiation 1, 2, 3 2

1 per subsystem C

SR 3.3.5.1.5 NA (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.

Retrieved from "https://kanterella.com/w/index.php?title=PLA-8025,_Supplement_to_License_Amendment_to_Revise_Reactor_Steam_Dome_Pressure_-_Low_Instrumentation_Function_Allowable_Value&oldid=3792274"