RS-09-164, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-490

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Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-490
ML093410042
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 12/04/2009
From: Simpson P
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-09-164
Download: ML093410042 (21)
v • d • e


Text

Exelon Generation 4300 Winfield Road Warrenville, IL 60555 RS-09-164 December 4, 2009 wwwexeloncorp.com Nuclear U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 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 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-490

References:

1.

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

December 4, 2009 U.S. Nuclear Regulatory Commission Page 2 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 review of the proposed license amendment in Reference 2, and a response was provided by EGC in Reference 3. Subsequently, the NRC made a second request for additional information to facilitate the review of the proposed license amendment in Reference 4. In response to this request, EGC is providing the attached information.

Attachments 2 and 3 provide revised markups of TS pages 3.4.16-1, 3.4.16-2, and 3.4.16-3 for Braidwood Station and Byron Station, respectively. Retyped TS pages with the proposed changes incorporated are provided in Attachments 4 and 5 for Braidwood Station and Byron Station, respectively. 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 4th day of December 2009.

spectfully,

\\

I

~

~triCk R. Simpson Manager - Licensing Attachments:

1.

Response to Request for Additional Information 2.

Revised Markup of Proposed Technical Specifications Pages for Braidwood Station 3.

Revised Markup of Proposed Technical Specifications Pages for Byron Station 4.

Retyped Technical Specifications Pages for Braidwood Station 5.

Retyped Technical Specifications Pages for Byron Station

ATTACHMENT 1 Response to Request for Additional Information NRC Request The Nuclear Regulatory Commission (NRC) staff is reviewing Exelon Generation Company, LLC's (the licensee's) license amendment request (LAR) dated December 4,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083390706), as supplemented by letter dated July 27,2009 (ADAMS Accession No. ML092090437). The LAR requests to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] Specific Activity," and Surveillance Requirements (SRs) 3.4.16.1 and 3.4.16.3.

The requested changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity. The LAR states that the changes are consistent with NRC-approved TS Task Force (TSTF) Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec." The NRC staff has determined that following additional information is required to complete its review.

In the LAR, the licensee proposed TS changes to revise Limiting Condition for Operation (LCO) 3.4.16, "RCS Specific Activity," APPLICABILITY requirements to specify that the LCO is applicable in MODES 1, 2, 3, and 4. In the LAR, the licensee also proposed to revise SR 3.4.16.1 to add the following NOTE, "Only required to be performed in MODE 1," thus removing the applicability of this SR to other MODES.

The NRC staff has a concern about the piOposed addition of the Note to SR 3.4.16.1. The proposed change revises the conditions for sampling for SR 3.4.16.1, and may exclude sampling during the plant conditions where LCO 3.4.16 may be exceeded. After transient conditions (Le. reactor trip, plant depressurization, shutdown or startup) that end in MODES 2, 3 or 4, the SR is not required to be performed. Radioactivity spiking and fuel failures are more likely during transient conditions than during steady state plant operations.

Because LCO 3.4.16 could potentially be exceeded after plant transient or power changes, please justify why sampling is no longer needed in the plant MODES that are proposed to be eliminated and justify how the LCO 3.4.16 remains consistent with the design bases analysis from which the LCO limits are derived (i.e. main steamline break, steam generator tube rupture, etc.). Furthermore, please justify why there is an apparent disparity between the modes of applicability (MODES 1, 2, 3, and 4) and the limited mode (MODE 1) under which the surveillance is required.

Response

The proposed TS pages have been revised to restore the Applicability of LCO 3.4.16 to "MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) ~ 500°F." In addition, the SR Note "Only required to be performed in MODE 1" has been removed from SR 3.4.16.1 and SR 3.4.16.2. Attachments 2 and 3 provide revised markups of the affected TS pages for Braidwood Station and Byron Station, respectively. Attachments 4 and 5 provide retyped TS pages for Braidwood Station and Byron Station, respectively, that reflect the revisions described above.

Appropriate changes to the TS Bases will also be made upon implementation of the proposed change.

Page 1 of 1

ATTACHMENT 2 Revised Markup of Proposed 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 3.4.16-3

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific A~ctivitY Tf\\JSEf<.!.1-LCO 3.4.16 the reactor coolant shall be "ithin the fa 11 m~i ng 1iRli ts :

a.

Dose [qui val ent I 131 specHi cacti viti < 1.0 j::tCi /gffi, Jfl4-b.

Gross specHi cacti viti < 100/E liei /glfl.

APPLICABILITY:

MODES 1 and 2, MODE 3 with RCS average temperature (Ta~) 2 500°F.

ACTIONS

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

LCO 3.0.4.c is applicable.

CONDITION A.

DOSE EQUIVALENT 1-131 specific activity

. 1 1\\

,r; /,.un g Sor, ~+ V"~~f h IV\\ \\i VVl; t.

~./\\"..A A.l REQUI RED ACTION Veri fy DOSE EQUIVALENT 1-131 specific activity

'iii thi n the acceptable region of

~

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

(continued)

BRAIDWOOD - UNITS 1 &2 3.4.16-1 Amendment 134

Insert 1 Res DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED,A.CTION COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 3 with Tavg < 500°F.

Be in MODE 3 with Tavg < 500°F.

C.1 OR DOSE EQUIVALENT 1-131 specific activity' the unaccept

~

region

-=fNS ERT 2.

F'

'red Action and B.1 aSSOCl Completion Time of Con.. n A not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 7 days BRAIDWOOD - UNITS 1 &2 3.4.16-2 Amendment 98

Insert 2 B. 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.

Insert 3 C. Required Action and associated Completion Time of Condition A or B not met.

DOSE EQUIVALENT 1-131

>60 /lCi/gm.

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SR 3.4.16.2 SR 4.16.3 SURVEI LLANCE

~~I~l~~~E-i..~

Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity

~ 1.0

~Ci/gm.

Deter:. e I from a re or coolant sample en in MODE 1 after a m"

'mum of 2 EFPD and 20 days of MODE 1 operatl have elapsed since the reactor was las subcritical for

~ 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

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 BRAIDWOOD - UNITS 1 &2 3.4.16 - 3 Amendment 98

ATTACHMENT 3 Revised Markup of Proposed 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 3.4.16-3

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS specific~ctiVit

LNSSR,T..1-LCD 3.4.16 ~c~f the reactoF coolant shall be within

~~e following liffiits:

a.

Dose Equi "ial eRt I 131 speci fi cacti 't/i ty < 1. 0 ~i Igffi;

-i1fl6-b.

610ss specific oct; vHy ( loo/I

~;/gm.

APPLICABILITY:

MODES 1 and 2, MODE 3 with RCS average temperature (Ta~)

~ 50oPF.

ACTIONS CONDITION A.

DOSE EQUIVALENT 1-131 specifi c act; ",it','

r. :r';

~

~

v REQUI RED ACTION

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

LCO 3.0.4.c is applicable.

COMPLETION TIME A.l Veri fy DOSE EQUIVALENT 1-131 specific activity

~,i thi n the acceptable region of

~

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 wi thin 1imi t.

(continued)

BYRON - UNITS 1 &2 3.4.16 - 1 Amendment 141

Insert 1 Res DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

'red Action and 8.1 Be in MODE 3 with aSSOCl C?m~letion Tavg < 500°F.

Time of Con n A not met.

OR DOSE EQUIVALENT 1-131 specific activity the unaccept region F'

e 3.4.16-1.

C.l Be in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> T.vg < 500°F.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.16.1 Verify reactor coolant gross specific activity $

i/gm.

FREQUENCY 7 days BYRON - UNITS 1 &2 3.4.16-2 Amendment 106

Insert 2 B. 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.

Insert 3 C. Required Action and associated Completion Time of Condition A or B not met.

DOSE EQUIVALENT 1-131

>60 flCi/gm.

I

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity

~ 1.0

~Ci/gm.

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 days Oete

. e Efrom a re or coolant sample en in MODE 1 after a m'

'mum of 2 EFPO and 20 days of MODE 1 operatl have elapsed since the reactor was las subcritical for

~ 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

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

Not required to be performed unti days after a minimum of 2 Effectiv

.ull er Days (EFPD) and 20 s of MODE 1 oper

'on have elaps ince the reactor was last criti for

~ 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

BYRON - UNITS 1 &2 3.4.16 - 3 Amendment 106

ATTACHMENT 4 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

RCS Specific Activity 3.4.16 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 and 2, MODE 3 wi th RCS average temperature (Tavg)

~ 500°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

DOSE EQUIVALENT 1-131

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

not within limit.

LCO 3.0.4.c is applicable.

A.1 Veri fy 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 s 60 IlCi/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.

B.

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.

(contlnued)

BRAIDWOOD UNITS 1 &2 3.4.16 1

Amendment

ACTIONS (continued)

CONDITION C.

Required Action and C.1 associated Completion Time of Condition A or B not met.

OR DOSE EQUIVALENT 1-131

> 60

~Ci/gm.

SURVEILLANCE REQUIREMENTS REQUIRED ACTI ON Be in MODE 3 with Tavg < 500 0 F.

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 /> SURVEI LLANCE SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity ~ 603

~Ci/gm.

SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity ~ 1.0

~Ci/gm.

FREQUENCY 7 days 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 BRAIDWOOD UNITS 1 &2 3.4.16 - 2 Amendment

ATTACHMENT 5 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

RCS Specific Activity 3.4.16 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 and 2 MODE 3 with RCS average temperature (Ta~)

~ 500°F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

DOSE EQUIVALENT 1-131

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

not within limit.

LCO 3.0.4.c is applicable.

A.1 Veri fy 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 ilCi/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 1imit.

B.

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.

(contlnued)

BYRON - UNITS 1 &2 3.4.16 - 1 Amendment

ACTIONS (continued)

CONDITION C.

Required Action and C.1 associated Completion Time of Condition A or B not met.

OR DOSE EQUIVALENT 1-131

> 60

~lCi Igm.

SURVEILLANCE REQUIREMENTS REQUIRED ACTION Be in MODE 3 with Tav9 < 500°F.

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 /> SURVEI LLANCE SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity ~ 603

~Ci/gm.

SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity ~ 1.0

~Ci/gm.

FREQUENCY 7 days 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 BYRON - UNITS 1 &2 3.4.16 - 2 Amendment

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