NMP2L2667, Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2

Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2

ML18037A131
Person / Time
Site:	Nine Mile Point
Issue date:	02/06/2018
From:	Jim Barstow Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP2L2667
Download: ML18037A131 (5)

Text

Exelon Generation© NMP2L2667 February 6, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRG Docket No. 50-410 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90

Subject:

Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control,"

Revision 2

References:

1. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,' Revision 2," dated February 28, 2017

2. Letter form J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,' Revision 2," dated January 12, 2018 By letter dated February 28, 2017 (Reference 1 ), Exelon Generation Company, LLC (Exelon) requested to change the Nine Mile Point Nuclear Station, Unit 2 (NMP2) Technical Specifications (TS). The proposed amendment request would revise NMP2 TS by replacing the existing specifications related to Operations with a Potential for Draining the Reactor Vessel with revised requirements for Reactor Pressure Vessel Water Inventory Control to protect Safety Limit 2.1.1.3.

By letter dated January 12, 2017 (Reference 2), Exelon submitted supplemental information to address changes to Section 3.3.5.2. to this letter provides two proposed TS marked-up pages that clarifies specific information previously provided in References 1 and 2. For TS page 3.3.5.2-5, Attachment 1 includes a markup showing note (d) removed from Function 3.b, HPCS Pump Discharge Pressure High (Bypass), from TS Table 3.3.5.2-1 (page 2 of 2). Also, note (d) is removed in

Supplemental Information No.3 TSTF-542, Reactor Pressure Vessel Water Inventory Control Docket No. 50-41 O February 6, 2018 Page 2 its entirety from the bottom of the table. This Supplement Information No. 3 supersedes the markup provided in Reference 2. The updated clean page for TS page 3.3.5.2-5 will be provided upon NRC request to support the Safety Evaluation.

In addition, Attachment 1 includes a markup showing note (d) deleted from Function 5.b, Reactor Vessel Water Level - Low, Level 3 and from the bottom of TS page 3.3.6.1-10, TS Table 3.3.6.1-1, page 5 of 5. This Supplement Information No. 3 supersedes the markup provided in Reference 1. The clean page provided in Reference 1 for this TS page correctly shows note (d) removed and no further clarification is needed.

Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The supplemental information provided in this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.

Furthermore, the supplemental information provided in this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

With the supplemental information provided in Attachment 1 to this letter, Exelon requests approval of the proposed amendment by March 1, 2018. The requested approval date supports the implementation of TSTF-542 prior to the start of the refueling outage. Once approved, the amendment shall be implemented no later than the start of the NMP2 2018 refueling outage.

There are no commitments contained in this response.

If you should have any questions regarding this submittal, please contact Ron Reynolds at 610-765-5247.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 61h day of February 2018.

~.VcJ/.4-Jyv- ~

James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC : Proposed Technical Specification Marked-Up Pages cc:

USNRC Region I Regional Administrator USN RC Senior Resident Inspector - NMP USNRC Project Manager, NRR - NMP A. L. Peterson, NYSERDA w/attachments

ATTACHMENT 1 Supplemental Information No.3 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License NPF-69 Docket No. 50-41 o PROPOSED TECHNICAL SPECIFICATION MARKED-UP PAGE TS Pages 3.3.5.2-5 3.3.6.1-10

Supplement No. 3 (a)

(b) 3 FUNCTION HPCS Pump Discharge Pressure-High (Bypass)~

HPCS System Flow Rate Low (Bypass) e MaA~al IA1ha1teA ( ~ l RHR System Isolation a

Reactor Vessel Water Level Low Level3 5

Reactor Water Cleanup (RWCU) System lsolatton a

Reactor Vessel Water Level Low Low Level 2 NMP2 RCIC ~ys&eFflRPV Water Inventory Control Instrumentation 3.3.5.2 Table 3 3 5 2 1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS CONDITIONS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A 1 Delete 4.s 1 per pump (a)

Delete per Supplement No. 3 4 5 (c)

(c) 2 In one Tnp system 2 1n one Tnp system B

B Delete note (d) per Supplement No. 3 3.3.5.2-5 SURVEILLANCE REQUIREMENTS SR33521 SR 3 3 5 2 2 SR 3 3 5 2 1 SR 3 3 52 2 ALLOWABLE VALUE

~ 220 ps1g

~ 157 8 inches

~ 101 8 inches Amendment

Supplement No. 3 FUNCTION

5.

RHR SOC System Isolation (continued)

b.

Reactor Vessel Water Level - Low, Level 3

c.

Reactor Vessel Pressure - High

d.

Reactor Building Pipe Chase Area Temperature - High El." 319 ft.

El." 292 ft.

El." 266 ft.

El." 227 ft.

e.

Reactor Building General Area Temperature - High

f.

Manual Initiation NMP2 Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 5)

Primary Containment Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 3,-4';5 1,2,3 3

3 1,2,3 REQUIRED CHANNELS PER TRIP SYSTEM 21"7 2

1 per area 1 per area 4

CONDITIONS REFERENCED FROM REQUIRED SURVEILLANCE ALLOWABLE ACTION C.1 REQUIREMENTS VALUE Delete per Supplement No. 3 J

SR 3.3.6.1.1

> 157.8 inches SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 F

SR 3.3.6.1.1

> 148 psig SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6 F

SR 3.3.6.1.1 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

> 144.5°F

> 140.5°F

> 140.5°F

> 140.5°F F

SR 3.3.6.1.1 s 134°F SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 G

SR 3.3.6.1.6 NA Delete per Supplement No. 3 3.3.6.1-10 Amendment 91