RS-10-023, Units 1 and 2 - Supplement to Request for License Amendment Request to Adopt TSTF-490

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Units 1 and 2 - Supplement to Request for License Amendment Request to Adopt TSTF-490
ML100320144
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 01/29/2010
From: Simpson P
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-10-023, TSTF-490
Download: ML100320144 (20)
v • d • e


Text

Exelon Gener tior.

wwvv.exe10T'1C0TP.C0-n 4300 ad Wauemmo,. 0555 RS-10-023 January 29,2010 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units I and 2 Facility Operating License Nos. NPF-72 and NPF-77 NFIC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos.-STN 50-454 and STN 50-455 Exel n Nuclear Subject :

Supplement to Request for License Amendment Request to Adopt TSTF-490 References :

1.

Letter from P. R. Simpson (Exelon Generation Company, LLQ to U.S.

Nuclear Regulatory Commission, "License Amendment Request to Adopt TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification," dated December 4, 2008 2.

Letter from M. J. David (U.S. Nuclear Regulatory Commission) to C. G. Pardee (Exelon Nuclear), "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Request for Additional Information Related to Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification (TAC Nos. ME0206, ME0207, ME0208, and ME0209)," dated June 19, 2009 3.

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

Nuclear Regulatory Commission, "Additional Information Supporting License Amendment Request to Adopt TSTF-490," dated July 27, 2009 4.

Letter from M. J. David (U.S. Nuclear Regulatory Commission) to C. G.

Pardee (Exelon Nuclear), "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Request for Additional Information Related to Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification (TAC Nos. ME0206, ME0207, ME0208, ME0209)," dated October 22, 2009

January 29, 2010 U.S. Nuclear Regulatory Commission Page 2

5. Letter from P. R, Simpson (Exelon Generator Company, LLC) to U.S.

Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-490,"

dated December 4, 2009 In Reference 1, Exelon Generation Company, LLC (EGC) requested a license amendment for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, to revise Technical Specifications (TS) to replace the current limit on Reactor Coolant System (RCS) gross specific activity with a new limit on RCS noble gas-specific activity. The NRC requested additional information to complete the review of the proposed license amendment in References 2 and 4, and responses were provided by EGC in References 3 and 5, respectively. Based on a telecon held on January 14, 2010, between the NRC and EGC, the following supplemental information is being provided.

The proposed TS pages have been revised to modify the Applicability of Limiting Condition for Operation (LCO) 3.4.16 to "MODES 1, 2, 3, and 4." Additionally, the required actions for Condition C are C.1 "Be in MODE 3" with a completeion time of six hours and C.2 "Be in MODE 5" with a completion time of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Attachments 1 and 2 provide revised markups of TS pages 3.4.16-1 through 3.4.16-3 for Braidwood Station and Byron Station, respectively.

Retyped TS pages incorporating the proposed changes described above are provided in Attachments 3 and 4 for Braidwood Station and Byron Station, respectively. Appropriate changes to the TS Bases will be made upon implementation of the proposed changes.

EGC has determined that the information provided in the Attachments does not impact the conclusions of the No Significant Hazards Consideration or the Environmental Consideration as stated in Reference 1.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Ms. Jean M. Smith at (630) 657-2813.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of January 2010.

Patrick R. Simpson Manager - Licensing Attachments:

1. Revised Markup of Proposed Technical Specifications Pages for Braidwood Station

2. Revised Markup of Proposed Technical Specifications Pages for Byron Station
3. Retyped Technical Specifications Pages for Braidwood Station
4. Retyped Technical Specifications Pages for Byron Station

ATTACHMENT 1 Revised Markup of Proposed Technical Specifications Pages for Braidwood Station Braidwood Stat n, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.16-1 3.4.16-2 3.4.16-3

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The speG 844



  1. U 4 the r APPLICABILITY :

ACTIONS A.

DOSE EQUIVALENT I-131 speG#iG V4+y l

Cl gg4 Igm r

rr.

EGGS 6neni 4i (^ -,Gti V#'i ! l RCS Specific Activity 3.4.16

~4e REQUIRED ACTION CONDITION

NOTE ------------

LCO 3.0.4.c applicable.

not withi n limit.)

COMPLETION TIME Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 48 hours (continued)

BRAIDW00D - UNITS 1 & 2 3.4.16 - 1 Amendment 134 A.1 Verify DOSE EQUIVALENT I-131 c-pori -Fi r aGti y i tci "ice"

,q,G~ q4 GH fT Al A

- -p 3..-1QY

< 60 Ki/gm.

AND A.2 Restore DOSE EQUIVALENT I-131 specific activity to within limit.

Inert 1 RCS DOSE: EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 sped within limits.

activity shall be

ACTIONS (continued)

REQUIRED ACTION Qupe 3.4,41}-4 ITION 9

qw???

4eG4-f4G SURVEILLANCE REQUIREMENTS B-4 SURVEILLANCE Be 4H MODE 3 W; t",

('.1 Be 4 MODE 4-with

!DOSE EQUIVALENT XE-133 specific INSERT 3 SR 3.4.16.1 Verify reactor conlynt gpess speG44G activity ! ?GGJr,q0b)gCi/gm.

RCS Specific Activity 3.4.16 COMPLETION TIME

-S 6-44ywyls 7 days FREQUENCY (continued)

BRAIDWOOD - UNITS 1 & 2 3.4.16 - 2 Amendment 98

Insert 2

_________NOTE-________

LCO 3.0.4.c is applicable.

B.1 Restore DOSE EQUIVALENT XE-1 33 to within limit.

B. DOSE EQUIVALENT XE-133 not within limit.

Insert 3

? Required Acton and associated Completion Time of Condition A or B not met.

OR DOSE EQUIVALENT 1-131 5 60 pCi/gm.

CA Be in MODE 3.

AND C.2 Be in MODE 5.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 6 hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity 5 1.0 pfi/gm.

Net Peg&

ca cr a4tep a minimum G4 taken in MODE 1 ait d 20 days 94 MODE 1 e elapsed S*Ge the peaetep kpmed until 31 day-11 4jeebve F6414 minimum ef -c -c pat&R have w

RCS Specific Activity 3.4.16 FREQUENCY 14 days AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of

! 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period 184--4day-s BRAIDWOOD - UNITS 1 & 2 3.4.16 - 3 Amendment 98

ATTACHMENT 2 Revised Markup of Proposed Technical Specifications Pages for Byron Station Facility Operat Byron Station, Units 1 and 2 g License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.16-1 3.4.16-2 3.4.16-3

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity APPLICABILITY :

MODES 1 MODE 3 Wi 0-454 ACTIONS CONDITION A.

DOSE EQUIVALENT 1-131

-C,Peeifie aetivity i. n..ri Irim 1 ~

49 Got within limit REQUIRED ACTION

____________NOTE-___________

LCO 3.0.4.c is applicable.

A.1 Verify DOSE EQUIVALENT 1-131 spee4le alv-??44 W&P the A.2 Restore DOSE EQUIVALENT 1-131 specific activity to within limit.

RCS Specific Activity 3.4.16 COMPLETION TIME Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 48 hours (cost BYRON - UNITS 1 & 2 3.4.16 - 1 Amendment 141

Insert 1 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-1 33 specific activity shall be within limits.

APAPq CAP XG 07- -K--

aG-04ty Pet-&4 n

4?

414010.

SURVEILLANCE REQUIREMENTS SR 3.4.16.1 Verify reactor cool activity z WWATE-1603 ),Ci/gm.

SURVEILLANCE DOSE EQUIVALENT XE-133 specific gpess sqeG4-:~

RCS Specific Activity 3.4.16 7 days FREQUENCY (continued)

BYRON - UNITS 1 & 2 3.4.16 - 2 Amendment 106

Insert 2

-NOTE-________

LCO 3.0.4.c is applicable.

B-1 Restore DOSE EQUIVALENT XE-133 to within limit.

B. DOSE EQUIVALENT XE-1 33 not within limi insert 3 OR C. Required Action and associated Completion Time of Condition A or B not met.

DOSE EQUIVALENT 1-131

> 60 pCi/gm.

CA Be in MODE 3.

AND C.2 Be in MODE 5.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 6 hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.2 ORly peq&ped te be Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity ! 1.0 pfi/gm.

net-0 WkeR 4R MODE 1 a4tep a mum P-1 0- 4-14pp RCS Specific Activ 3.4.

14 days Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of n 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period 184 day-S BYRON - UNITS 1 & 2 3.4.16 - 3 Amendment 106

ATTACHMENT 3 Retyped Technical Specifications Pages for Braidwood Station Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.16-1 3.4.16-2

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity NCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY :

MODES 1, 2, 3, and 4.

CTIONS A.

B.

RCS Specific Activity 3.4.16 (continued)

BRAIDWOOD - UNITS 1 & 2 3.4.16 - 1 Amendment CONDITION DOSE EQUIVALENT 1-131 not within limit.

REQUIRED ACTION

____________NOTE-___________

LCO 3.0.4.c is applicable.

COMPLETION TIME A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131

< 60 pCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 specific activity to within limit.

DOSE EQUIVALENT XE-133

____________NOTE____________

not within limit.

LCO 3.0.4.c is applicable.

B.1 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.

ACTIONS (continued)

CONDITION C.

Required Action and associated Completion Time of Condition A or B not met.

0 DOSE EQUIVALENT 1-131

> 60 pCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity 1 603 gCi/gm.

SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity 1 1.0 pCi/gm.

RCS Specific Acti 3.4.16 REQUIRED ACTION C.1 Be in MODE 3.

Q C.2 Be in MODE 5.

COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours 7 days FREQUENCY Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of

? 15% RTP within a I hour period BRAIDWOOD - UNITS 1 & 2 3.4.16 - 2 Amendment

ATTACHMENT 4 Retyped Technical Specifications Pages for Byron Station Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.16-1 3.4.16-2

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY :

MODES 1, 2, 3, and 4.

ACTIONS CONDITIO A.

B.

REQUIRED ACTION RCS Specific Activity 3.4.16 COMPLETION TIME (continued)

BYRON --UNITS 1 & 2 3.4.16 - 1 Amendment DOSE EQUIVALENT 1-131 not within limit.

____________NOTE____________

LCO 3.0.4.c is applicable.

Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131

< 60 gC i l gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 specific activity to within limit.

DOSE EQUIVALENT XE-133

___________NOTE____________

not within limit.

LCO 3.0.4.c is applicable.

Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT XE-133 to within limit.

SURVEILLANCE REQUIREMENTS RCS Specific Activity 3.4.16 COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours BYRON - UNITS 1 & 2 3.4.16 - 2 Amendment SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT 7 days XE-133 specific activity 1 603 gCi/gm.

SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 14 days 1-131 specific activity j 1.0 pCi/gm.

AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of

? 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period ACTIONS (continued)

CONDITION REQUIRED ACTION C.

Required Action and C.1 Be in MODE 3.

associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE 5.

DOSE EQUIVALENT 1-131

> 60 uCi/gm.

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