View source for 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

{{Adams
| number = ML18037A131
| issue date = 02/06/2018
| title = Supplemental Information No.3 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
| author name = Barstow J
| author affiliation = Exelon Generation Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000410
| license number = NPF-069
| contact person = 
| case reference number = NMP2L2667
| document type = Letter type:NMP
| page count = 5
| project = 
| stage = Supplement
}}

=Text=
{{#Wiki_filter:Exelon Generation &#xa9; 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 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

==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.
Attachment 1 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 Attachment 1: Proposed Technical Specification Marked-Up Pages cc:     USNRC Region I Regional Administrator                        w/attachments USN RC Senior Resident Inspector - NMP USNRC Project Manager, NRR - NMP A. L. Peterson, NYSERDA

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                                       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                          CONDITIONS MODES OR                          REFERENCED OTHER           REQUIRED              FROM SPECIFIED     CHANNELS PER           REQUIRED   SURVEILLANCE    ALLOWABLE FUNCTION                     CONDITIONS        FUNCTION           ACTION A 1  REQUIREMENTS       VALUE 3
Delete HPCS Pump                    4.s           1 per pump                                ~  220 ps1g Discharge                                       (a )
Pressure-High (Bypass)~               Delete per Supplement No. 3 HPCS System Flow             4  5 Rate Low (Bypass) e      MaA~al IA1ha1teA ( ~l RHR System Isolation a     Reactor Vessel              (c)            2 In one            B     SR33521        ~  157 8 inches Water Level Low                          Tnp system                  SR 3 3 5 2 2 Level3 5  Reactor Water Cleanup (RWCU) System lsolatton a     Reactor Vessel              (c)            2 1n one            B     SR 3 3 5 2 1   ~  101 8 inches Water Level Low                          Tnp system                  SR 3 3 52 2 Low Level 2 (a)
(b)
Delete note (d) per Supplement No. 3 NMP2                                                    3.3.5.2-5                                    Amendment

Supplement No. 3                                        Primary Containment Isolation Instrumentation Attachment 1                                                                                          3.3.6.1 Table 3.3.6.1-1 (page 5 of 5)
Primary Containment Isolation Instrumentation APPLICABLE                       CONDITIONS MODES OR        REQUIRED       REFERENCED OTHER          CHANNELS           FROM SPECIFIED        PER TRIP        REQUIRED      SURVEILLANCE        ALLOWABLE FUNCTION           CONDITIONS        SYSTEM         ACTION C.1     REQUIREMENTS           VALUE
: 5. RHR SOC System Isolation                                             Delete per (continued)
Supplement No . 3
: b. Reactor Vessel Water      3,-4';5           21"7             J         SR 3.3.6.1.1  > 157.8 inches Level - Low, Level 3                                                   SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.6
: c. Reactor Vessel            1,2,3              2              F          SR 3.3.6.1.1  :> 148 psig Pressure - High                                                        SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1 .5 SR 3.3.6.1 .6
: d. Reactor Building Pipe        3          1 per area           F         SR 3.3.6.1.1 Chase Area                                                             SR 3.3.6.1 .3 Temperature - High                                                     SR 3.3.6.1 .5 SR 3.3.6.1 .6 El." 319 ft.                                                                    :> 144.5&deg;F El." 292 ft.                                                                    :> 140.5&deg;F El." 266 ft.                                                                    :> 140.5&deg;F El." 227 ft.                                                                    :> 140.5&deg;F
: e. Reactor Building             3          1 per area           F         SR 3.3.6.1.1   s 134&deg;F General Area                                                          SR 3.3.6.1.3 Temperature - High                                                     SR 3.3.6.1.5 SR 3.3.6.1.6
: f. Manual Initiation        1,2,3              4               G         SR 3.3.6.1.6   NA Delete per Supplement No. 3 NMP2                                             3.3.6.1-10                                    Amendment 91}}