RS-19-085, Additional Information Regarding Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control for R.E. Ginna Nuclear Power Plant

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Additional Information Regarding Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control for R.E. Ginna Nuclear Power Plant
ML19234A153
Person / Time
Site: Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Quad Cities, FitzPatrick, LaSalle  Constellation icon.png
Issue date: 08/22/2019
From: Simpson P
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-19-085
Download: ML19234A153 (8)
v • d • e


Text

4300 Winfield Road Warrenville , IL 60555 Exelon Generation 630 657 2000 Office RS-19-085 10 CFR 50.90 August22,2019 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Limerick Generating Station , Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

August22, 2019 U.S . Nuclear Regulatory Commission Page 2

Subject:

Additional Information Regarding Application to Remove the Table of Contents from Technical Specifications And Place it Under Licensee Control for R.E. Ginna Nuclear Power Plant Reference : Letter from Patrick Simpson (Exelon Generation Company, LLC) to U.S NRC, "Application to Remove the Table of Contents from Technical Specifications And Place it Under Licensee Control ," dated June 14, 2019 By letter dated June 14, 2019 (Reference) , Exelon Generation Company, LLC (EGC) requested an amendment to Renewed Facility Operating Licenses (FOL) Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, Renewed FOL Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station ,

Units 2 and 3, Renewed FOL No. DPR-59 for James A. FitzPatrick Nuclear Power Plant, Renewed FOL No. DPR-18 for R.E. Ginna Nuclear Power Plant, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed FOL Nos. NPF-39 and NPF-85 for Limerick Generating Station , Units 1 and 2 , Renewed FOL Nos. DPR-63 and NPF-69 for Nine Mile Point Nuclear Station, Units 1 and 2, Renewed FOL Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2 . The proposed amendment would remove the Table of Contents (TOC) from the Technical Specifications (TS) and place it under licensee control.

The NRC identified a discrepancy between the markup provided for R.E . Ginna Nuclear Power Plant (Ginna) and the current NRC authority file. Specifically, the TOC markup provided for Ginna was marked as Amendment 100, and the NRC authority file is marked as Amendment 80. The purpose of this letter is to provide a revised markup that matches what is the current NRC authority file. Additionally, the discrepancy was documented in the Corrective Action Program (CAP). provides the revised markup of proposed TOC TS pages for Ginna .

EGC has reviewed the information supporting the No Significant Hazards Consideration and the Environmental Consideration that was previously provided to the NRC in the Reference . The additional information provided in the submittal does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration. This additional information also does not affect the conclusion that neither an environmental impact statement nor an environmental assessment need be prepared in support of the proposed amendment.

In accordance with 10 CFR 50.91 , "Notice for public comment; State consultation,"

paragraph (b), EGC is notifying the State of Illinois, State of New York, State of Pennsylvania, and the State of Maryland of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.

August 22, 2019 U.S. Nuclear Regulatory Commission Page 3 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mrs. Linda M. Palutsis at (630) 657-2821.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 22nd day of August 2019.

R~(Z Patrick R. Simpson Sr. Manager Licensing Exelon Generation Company, LLC

Attachment:

Revised Markup of Proposed Technical Specifications Pages for R.E. Ginna Nuclear Power Plant cc: NRC Regional Administrator, Region I NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - R. E. Ginna Nuclear Power Plant

ATTACHMENT Revised Markup of Proposed Technical Specifications Pages for R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 Revised Technical Specifications Pages ii iii iv

TABLE OF GO~JTE~JTS 4-4 USE A~m APPLIGAT IO~J

~ DefiAitioAs .. ... ............. ... ... ............. ... ................ ... ................ ... ............. ... ... ............. ... . .... 1.1 1

~ Logioal GoAAeotoFs ..................................................................................................... 1 .2 1

~ GoFApletioA TiFA es ................................................... ........................................................ 1.a 1

4 FFequeAoy .................................................................................................................. 1. 4 1 SAFETY LIMI TS (SLs)

SLs ....................................................................................................................... 2.0 1 SL ViolatioAs .... ........ ...... ......... ....... ...... ...... ...... ...... ... ...... ...... ...... ...... ........ 2.0 1 W LIMITl~JG GONDITIO~J FOR OPERATION (LGO) AND SURVEILLM JGE REQUIRE:ME~H (SR) APPLICABILITY

~ LiFAitiAg GoAditioA foF OpemtioA (LGO) Applieability ............................................ a.O 1 a.-0 SurveillaAGe RequiFeFAeAt(SR) Applieability ....................................................... a.a 4

&4- REACTIVITY cmH ROL SYSTEMS

-d-:44 Sl=IUT DO'.Al ~J M/\RGl~J (SOM) ........ ........ ........ ........ ........ ........ ........ ........ ........ ... .. a.1.1 1

~ GoFC Reaoti'lity ....... ........ ........ ........ ........ ........ ........ ........ ........ ........ ........ ........ ... .. a.1.2 1

~ ModemtoFTeFApemtuFe Goe#ioieAt (MTG) ..... ........ ........ ........ ........ ........ ........ ... .. a.1.a 1

~ Rod GFoup /\lig AFAeAt LiR'lits ...................................................................................... a.1.4 1

~ ShutdowA BaAk IAsertioA LiR'lit ...... ........ ........ ........ ........ ........ ........ ........ ........ ...... a.1.6 1

~ GoAtFOI BaAI( IAsertioA LiR'lits ..................................................................................... a.1.6 1

~ Rod PositiOA IAdioatiOA ........................................................................................ a.1.7 1

&4-:-8 Pl=IYSIGS T ESTS E>wepti oAs MODE 2 ... ...... ... ...... ...... ... ... ....... ...... .. .. a.1.8 1

~ POWER DISTRIBUTlmJ LIMITS

~ l=leat Flux l=lot GhaAAel FaetoF(Fo(Z)) .................................................................. a.2.1 1

~ ~J uol eaF EAthalpy Ri se l=l ot GhaAAel FaotoF(FNa11)................................................ a.2.2 1

~ AXIAL FLUX DIFFERE~JGE (/\FD) ....................................................................... a.2.a 1

~ QUADRA~H POWER TILT RATIO (QPTR) ... ........ ........ ........ ........ ........ ........ ....... a.2.4 1

&3 l~JSTRUME~HATIO~J

~ ReaotoF TFipSysteR'l (RTS) IAStFUR'leAtatiOA ...................................................... .... a.a.1 1

~ EAgi Aeered Safety FeatuFeAotuatio A SysteR'l (ESFAS)

IAstruR'leAtatioA ... ...... ... ... ...... ... ...... ... ...... ... ...... ... ...... ... ...... ... ...... ... a.a.2 1

~ Post /\ooideAt MoAitoriAg (PAM) IAStFUR'leAtatioA ............................................... ... . a.a.a 1

~ Loss of Power (LOP) Diesel GeAemtor (DG) Start IAstFuR'leAtatioA .............................................................................. a.a.4 1

~ GoAtaiAFAeAt VeAtilatioA lsolatioA IAStFUFAeAtatioA .................................................. ..... a.a.6 1

~ GoAtFOI RooFA EFAeFgeAey AiF TmatFAeAt SysteFA (GREATS) IAStFUR'leAtatioA AotuatiOA .......................................................... ... a.a.6 1 RE. Ginna ~Juelea r Power Plant Amendment 80

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                          • a.7.a 1 RE. Ginna ~Ju e1ear Power

" Plant n/\ mendment 80

TABLE! OF GO~JTE~ffS

&7 PLANT SYSTE:MS (oontinued)

~

~

A tm ospheFio Relief Valves (A RV s)

Awcilia ry Feedw ate F (A FW) *st s ************************************************* .4 a 7 1

Condensate Stomge Tanks (bs~~ ................. ****************************** a .7 .6 1

~

Component Cooling WateF (GG'N) S*y~t~~- .. ...... ..... ************************ a .7 .6 1

&7-:+ SeFVioe ""ateF 1 £ 1111\ s ' t ... ... ...... ...... ... ... ...... ...... . a .7 .7 1

~ ** ~ o M? J oyStem Gontrnl Room emeFgenoy Ai~ -T~~~-t~~~t **************************************** a .7 .8 1

~

_ ~ ys.te m_ (<?REATS_) .. _. ...... ...... ... ............ ...... ... ... ...... ... ...... ... ... a79 1

(\

> 1u><1 1 1ary Bu1ldmg Vent1lat1on System (ABVS) *

  • Spent Fuel Pool (SFP) Wate F Lev I .... *****************************a .7 .10 1 Spent Fuel Pool (SFP) B G e .. ******.**....................... ************** a .7 .11 1 Spent Fuel Pool (SFP) StoF - onoentmt1on .................................. a .7 .12 1 o r- OFon S eoonda ~
  • Speoifi o Aoti .. *t , ag e ... ... ...... ... ...... ... ...... ... ...... ... ...... ..... a .7 .1 a 1 f v i y ... ...... ... ... ...... ... ...... ... ...... ........ ...... ...... a .7 .14 1

~ E:LE:GTRIGAL PGIJIJE:R SYSTE:MS

~ AG A G Sou SouFCes FOes MODES MODES 61 ' a~d 2 aG and 4 ............................................. a .8 .1 1

~ Diesel Fuel Oil ...... ... ......... ... ******************************** a .8 .2 1

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De s ouFOes Mc>"oEs*1*:*2:*a-,* ~~~j *4********************************************** ~-:*:  :

DC SouFOes MODES 6 and 6 . . .. . . . . .. . . . . . . . .. . . . . . . . .. . . . . . . . .. . . . . . . . . . .

~ Battery Gell PammeteFS ............................................ ********* a .8 .6 1

~

AG lnstFUment Bus souF~~~ ** * *MOD~*s**1 -,

  • 2 * *3***~~d
  • 4**************** * * * * * *** a .9 .6 1

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A~ lnstFUment Bus SouFOes MODES 6 a ~d G ...... ... ............. a .8 .7 1 D1stFibution Systems MODES 1 2 a and 4 ... .... ....... ... . ************* a .8 .8 1 DistFibution Syste m s MODES 6 ' a~d G ................................. a .8 .9 1

~

~ ......................................... a .8 .10 1 REFUELl~JG OPERATIO~JS Bornn

~JuoleaFGonoentm ti on lnstFumentati~~ ************************************************************** ... a .9 .1 1 Contain m ent Penetmtion*~ * ...... ................... ..... ******************************* a .9 .2 1 Residual l=l eat Removal (R~*R) *~*~*d

  • G*~-~i~~*t ************ * * * * * ******** * * * * * *****
  • a .9 .a 1 GiFCulation VVateF Level > 2a Ft Residual l=leat Removal (Rl=IR) and c~~l*~~t * ................. ******************a .9 .4 1 GiFOulation VVateF Level < 2a Ft a Refueling Cavity WateF Level ***************************************** **. .9 .6 1

........................................................ a .9 .6 1 DESIG~J FEATURES

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Site Looation u* ** *** *** *** *** ** ** ** ** uu*** * * *** * ** * ** * * * * * * * * * * * * * * * * * * * . * * * * * * * * * * * * * * * . * * * * ** . : . ~ :

RE: . Ginna ~Juolear Power Plant Amendment 80

TABLE! OF GO~JTE~ffS e ADMl~HSTRATIVE GO~HROLS

&:+ Responsibility ............................................................................... 6 .1 1

~ Organization ................................................................................. 6.2 1

&:-3 Plant Sta# Qualifications ... ...... ... ... ...... ...... ... ... ...... ...... ... ..... ...... .... 6.3 1

&:4 Procedures ....... ................. ............... ................. .......... ..... ........... 6 .4 1

&.-& Programs and Manuals ......... ......... ........................... ........... ......... 6.6 1

&:-e Reporting Requirements ... ...... ... ... ...... ....... ... ...... ...... ... ... ........ ...... 6 .6 1

&:+ High Radiation Area ...... ...... ... ......... ... ........... ...... ...... ...... .............. 6.7 1 RE . Ginna ~Juolear Power Plant Amendment 80

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