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PBAPS MELLLA License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications
	ML15299A084
Person / Time
Site:	Peach Bottom
Issue date:	10/26/2015
From:	Borton K; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML15299A084 (5)
	v • d • e

10 CFR 50.4 October 26, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Unit 2 and Unit 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

PBAPS MELLLA+ License Amendment Request - Supplement 7 Revision Regarding Proposed Technical Specifications

Reference:

1. Exelon letter to the NRC, "License Amendment Request - Maximum Extended Load Line Limit Analysis Plus," dated September 4, 2014 (ADAMS Accession No. ML14247A503)

In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (EGC) requested amendments to Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3, respectively (Reference 1). Specifically, the proposed changes would revise the Renewed Operating Licenses to allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain and the use of the Detect and Suppress - Confirmation Density (DSS-CD) stability solution.

This letter provides an update to the proposed Technical Specifications (TS) supporting the PBAPS MELLLA+ amendment request (Reference 1). Attachment 1, Page 8, Table 1, of the EGC license amendment request (Reference 1) identifies the proposed deletion of surveillance requirement (SR) 3.3.1.1.8 to calibrate the local power range monitors (LPRM), from TS Table 3.3.1.1-1 "Reactor Protection System Instrumentation," function 2f, Average Power Range Monitors (APRM) - Operating Power Range Monitor (OPRM)

Upscale. A subsequent review of the SRs for the OPRM Upscale function, determined that SR 3.3.1.1.8 should be retained for MELLLA+ at PBAPS Units 2 and 3. Although the LPRM calibration would have been performed within its required periodicity through other APRM functions, the calibration is necessary to ensure the LPRM reading match actual core conditions for the OPRM Upscale function.

U.S. Nuclear Regulatory Commission MELLLA+ License Amendment Request - Supplement 7 October 26, 2015 Page 2 Therefore, the requested deletion of SR 3.3.1.1.8 from the OPRM Upscale function 2f is withdrawn, and the SR will be retained in the Unit 2 and Unit 3 TS following MELLLA+

implementation. Attachment 1 of this letter provides the affected markup Unit 2 and Unit 3 TS Page 3.3-7.

There are no regulatory commitments contained in this letter.

Should you have any questions concerning this letter, please call me at (610) 765-5528.

Respectfully, Kevin F. Borton Manager, Power Uprate Licensing Exelon Generation Company, LLC

Attachment:

1. Markup of Proposed Unit 2 and Unit 3 Technical Specifications Page 3.3-7 cc: USNRC Region I, Regional Administrator w/attachment USNRC Senior Resident Inspector, PBAPS w/attachment USNRC Project Manager, PBAPS w/attachment R. R. Janati, Commonwealth of Pennsylvania w/attachment S. T. Gray, State of Maryland w/attachment

Attachment 1 Peach Bottom Atomic Power Station Unit 2 and Unit 3 NRC Docket Nos. 50-277 and 50-278 Markup of Proposed Unit 2 and Unit 3 Technical Specifications Page 3.3-7

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Wide Range Neutron Monitors

a. Period-Short 2 3 G SR 3.3.1.1.1 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5(a) 3 H SR 3.3.1.1.1 13 seconds SR 3.3.1.1.6 See Insert B for SR 3.3.1.1.12 SR 3.3.1.1.17 Note (g) SR 3.3.1.1.18

b. Inop 2 3 G SR 3.3.1.1.5 NA SR 3.3.1.1.17 5(a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17

2. Average Power Range 0.61W + 67.1%

Monitors

a. Neutron Flux-High 2 (c) G SR 3.3.1.1.1 15.0% RTP 3

(Setdown) SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12

b. Simulated Thermal 1 (c) F SR 3.3.1.1.1 3 0.55 W (g)

Power-High SR 3.3.1.1.2 + 63.3% RTP(b) and 118.0%

RTP SR 3.3.1.1.8 SR 3.3.1.1.11 See Insert B for SR 3.3.1.1.12(e),(f)

(c)

c. Note (h)

Neutron Flux-High 1 3 F SR 3.3.1.1.1 119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12

d. Inop 1,2 (c) G SR 3.3.1.1.11 NA 3

e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 SR 3.3.1.1.17 18% (h)

SR 3.3.1.1.18

f. OPRM Upscale 23% (c) I SR 3.3.1.1.1 (d) 3 NA RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.55 (W - W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

(c) Each APRM channel provides inputs to both trip systems.

Deleted (d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.

(e) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(f) The instrument channel set point shall be reset to a value that is within the Leave Alone Zone (LAZ) around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found tolerance and LAZ apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP methodologies used to determine the as-found tolerance and the LAZ are specified in the Bases associated with the specified function.

PBAPS UNIT 2 3.3-7 Amendment No. 273

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Wide Range Neutron Monitors

a. Period-Short 2 3 G SR 3.3.1.1.1 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5(a) 3 H SR 3.3.1.1.1 13 seconds SR 3.3.1.1.6 See Insert B for SR 3.3.1.1.12 SR 3.3.1.1.17 Note (g) SR 3.3.1.1.18

b. Inop 2 3 G SR 3.3.1.1.5 NA SR 3.3.1.1.17 5(a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17

2. Average Power Range 0.61W + 67.1%

Monitors

a. Neutron Flux-High 2 3(c) G SR 3.3.1.1.1 15.0% RTP (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12

b. Simulated Thermal 1 3(c) F SR 3.3.1.1.1 0.55 W Power-High SR 3.3.1.1.2 (g)

+ 63.3% RTP(b) and 118.0%

RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 (e),(f)

c. Neutron Flux-High 1 3(c) F SR 3.3.1.1.1 119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 See Inset B for SR 3.3.1.1.11 Note (h) SR 3.3.1.1.12

d. Inop 1,2 3(c) G SR 3.3.1.1.11 NA

e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 18%(h) SR 3.3.1.1.17 SR 3.3.1.1.18

f. OPRM Upscale 23% 3(c) I SR 3.3.1.1.1 (d) NA RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.55 (W - W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

(c) Each APRM channel provides inputs to both trip systems.

Deleted (d) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.

(e) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(f) The instrument channel set point shall be reset to a value that is within the Leave Alone Zone (LAZ) around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found tolerance and LAZ apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP methodologies used to determine the as-found tolerance and the LAZ are specified in the Bases associated with the specified function.

PBAPS UNIT 3 3.3-7 Amendment No. 277