ML20303A327

License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 of 5

ML20303A327
Person / Time
Site:	Byron
Issue date:	10/29/2020
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20304A147	List: ML20303A323 ML20303A325 ML20303A327 RS-20-129, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 5
References
RS-20-129
Download: ML20303A327 (54)

Text

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1. 3 3

/\CTI OMS co~mnrn~i REQbJ mm ,ll,C+ IOM COMPLE++/-OM +IME nA . One A.+/-- Restore 7 days

~unction x ~unction x train train to OPERM~LE i noFJera91 e. status .

g. One -lh+/- Restore n Rours

~unction y ~unction y train train to OPER,l\gLE i noFJera91 e. status .

c. One w Restore n RO bl rs

~unction x ~unction x train train to OPER,l\gLE inoFJera9le . status .

MID 00 GAe- td Restore n Rours

~unction y ~unction y train train to OPER,l\gLE i noFJera9l e. status .

BYRON - UNITS 1 &2 1.3 - 6 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

When one Function X train and one Function Y train are inoperable , Condition A and Condition B are concurrently applicable . The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condi ti on \.'as entered . A separate Completion Ti me is established for Condition C and tracked from the time the second train was declared inoperable Ci .e., the time the situation described in Condi ti on C '.Jas discovered) .

If ReqLiired Action C.2 i s completed \Jithin the specified Completion Time , Conditions B and C are exited . If the Completion Time for Required Action A. l has not expired ,

operation may continLie in accordance \*Jith Condition f\ . +h-e-remaining Completion Time in Condition A is measLired from the time the affected train was declared inoperable (i .e.,

initial entry into Condition/\) .

It is possible to alternate between Conditions A, B, and C in sLich a manner that operation coLild continLie indefinitely

..'i thob1t ever restoring systems to meet the LGO . Hmmver ,

1 doing so woLild be i nconsi st ent wi t h the ba si s of t he Completion Times . Therefore , there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO . These administrative controls shall ensure that the completion times for those conditions are not inappropriately extended .

BYRON - UNITS 1 &2 1.3 - 7 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1. 3 4

/\CTI OMS co~mnrn~l REQbJIREQ ,i\CTIO~l COMPLETIOM TIME nA . One or r:11ore A.+/-- Restore valve(s) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves to OPERM~LE inoperable . status .

fL ReEJuired .g.i ge in MOQE 3. 9 hours Action and associated Ai@.

Cor:11pletion Tir:Re not .g....i ge in MOQE 4 . +/-~ hours met.-

/\ single Cor:11pletion Tir:Re is used for any nur:11ber of valves inoperable at the Sar:Re tir:Re . The Cor:11pletion Tir:Re associated

'A'ith Condi ti on A is based on the initial entry into Condition A and is not tracked on a per valve basis .

Qeclaring subseEJuent valves inoperable , Hhile Condition A is still in effect , does not trigger the tracking of separate Cor:Rpletion Tir:11es .

Once one of the valves has been restored to OPERAgLE status ,

the Condition A Cor:11pletion Tir:Re is not reset , but continues fror:R the tir:11e the first va l ve \Jas decl ared inoperable . -TJ::\.

Cor:11pletion Tir:Re r:Ray be extended if the valve restored to OP ERAgLE status *.1as t he first inoperabl e va l ve . -TJ::\.

Condition A Cor:11pletion Tir:Re r:Ray be extended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provided this does not result in any subseEJuent val ve being inoperable for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> .

If the Cor:11pletion Tir:Re of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (plus the extension) expires \Jhile one or r:11ore valves are still inoperable ,

Condition g is entered .

BYRON - UNITS 1 &2 1.3 - 8 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1. 3 5 ACTIONS Separate Condi ti on entry is all o',Jed for each inoperable valve .

cG~mnHm R~QbJ mm iA,c+rn~1 CQ~Wb~+rnN +H4~

"A . One or more A.-+/-- Restore valve to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves OPERAgLE status .

inoperable .

g. Required .g.+/-- ge in MQQ~ 3. 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Action and associated AflID Completion

+ime not ~ ge in MQQ ~ 4. +/-~ hours met-.-

+he ~l ote above the ACTimlS +able is a method of modifying ho'.J the Completion Time is tracked . If this method of modifying hmJ the Completion Ti me is tracked ',Jas appl i cable only to a specific Condition , the Note \rould appear in that Condition rather than at the top of the AC+IGNS +able .

+he Note al lo\JS Condition A to be entered separately for each inoperable valve , and Completion Times tracked on a per valve basis . When a valve is declared inoperable ,

Condition/\ is entered and its Completion Time starts . +f.

subsequent valves are declared inoperable , Condition A is entered for each valve and separate Completion Times start and are tracked for each va l ve .

BYRON - UNITS 1 &2 1.3 - 9 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

If the CoFRpletion TiFRe associated .:ith a valve in 1

Condition A expires , Condition B is entered for that va l ve .

If the CoFRpletion TiFRes associated with subsequent valves in Condition A expire , Condition B is entered separately for each va l ve and separate CoFRpletion TiFRes start and are tracked for each valve . If a va l ve that caused entry into Condition B is restored to OPER/\BLE status , Condition B is exi ted for that va l ve .

Since the Note in this exaFRple al lows FRul tiple Condition entry and tracking of separate Completion Times , Completion TiFRe extensions do not appl y.

EX/\MPLE 1. 3 6

/\CTIONS c o ~mITIO~l REQbJIREQ ACTIO~l COMPLETION TIME "A . One channel A.+/-- PerforFR Once per g hours inoperable . SR 3.x.x.x.

GR-

-A-;J Reduce Tl=IERMAL g hours POIAIER to

~ 90~6 RTP.

l~L Requi red .@.....+/-. Be in MOQE 3. 8 hou rs

.ll.cti on and associated Completion Ti FRe not met.-

BYRON - UNITS 1 &2 1.3 - 10 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Entry into Condi ti on /\ offers a choice bet .1een Required 1

Action A.1 or /\ .2. Required Action A.1 has a "once per "

Completion Time , which qualifies for the 25% extension , per SR 3.0.2, to each performance after the initial performance .

The initial 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval of Required Action A. l begins

\Jhen Condition A is entered and the initial performance of Required Action A.1 must be complete *.1ithi n the first 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval . If Required Action A.1 is followed , and the Required Action is not met \Jithin the Completion Time (plus the extension allm*Jed b:Y SR 3.0.2) , Condition Bis entered .

If Reqbli red Action /\ . 2 is foll mmd and the Completion Ti me of 8 hoblrs is not met , Condition B is entered .

If after entry into Condition B, Reqblired Action /\ . 1 or A. 2 is met , Condition B is exited and operation may then continue in Condition A.

BYRON - UNITS 1 &2 1.3 - 11 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1. 3 7 ACTIOMS co~mnrn~i REQbJ mm ,ll,C+ IOM COMPLE++/-OM +IME nA . One A.+/-- \leri tj1 affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> su8s:,1stem su8s;Ystem inoperable . isolated . A@

Once per g hours thereafter A@

A....i Restore s618s:,1stem n ho61rs to OPE R,l\gLE status .

g. Required U ge in MOQE 3 . 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Action and associated A@

Completion

+ime not ~ ge in MOQE 5. 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> me.t-.

Required /\ction A. l has t ',JO Completion +imes . +he 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time 8egins at the time the Condition is entered and each "Once per g hours thereafter " interval 8egins upon performance of Required Action A.1.

BYRON - UNITS 1 &2 1.3 - 12 Amendment ~

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

If after Condition A is entered , Required Action A.1 is not FRet \Jithi n either the i ni ti al 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or any subsequent 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval froFR the previous perforFRance (plus the extension all m1ed b:J' SR 3. 0. 2) , Condi ti on g is entered . +Re-CoFRpl eti on TiFRe clock for Condition A does not stop after Condition g is entered , but continues froFR the tiFRe Condition/\ Has initially entered . If Required Action A.1 i s FRet after Condition g i s entered , Condition g is exited and operation FRay continue in accordance \Jith Condition A, provided the CoFRpletion TiFRe for Required Action A.2 has not expired .

ExaFRpl e 1. 3 8 f\CTIOMS co~mnrn~i REQldIREQ ACTIOM COMPLETIO~l TIME A

M . One A.+/-- Restore subsystem 7 days subsj1stem to QPERABLE inoperable . statbls . .QR In accordan ce

~;1 ~ tR the Ri s l~

Informed Completion Pro§raFR B. Reqblired .g...i Be in MO bl~ 3. i hoblrs

/l,cti on and associated A@

Compl etion TiFRe not ~ Be in MG bl~ 5. 38 hou rs met.-

BYRON - UNITS 1 &2 1.3 - 13 Amendment l Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

When a subsystem is declared inoperable , Condition A is entered . The 7 day Completion Time may be applied as discussed in Example 1.3 2. However , the licensee may elect to apply the Risk Informed Completion Time Program \Jhich permits calculation of a Risk Informed Completion Time CRICT) that may be used to completion the Required Action beyond the 7 day Completion Time . The RICT cannot exceed 30 days . After the 7 day Completion Time has expired , the subsystem must be restored to OPERABLE status ',Ji thin the RICT or Condition B must also be entered .

The Risk Informed Completion Time Program req~ires recalculation of the RICT to reflect changing plant conditions . For planned changes , the revised RICT must be determined prior to implementation of the change in configuration . For emergent conditions , the revised RICT must be determined within the time limits of the Required Action Completion Time Ci .e. , not the RICT or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the plant configuration change , whichever is less .

If the 7 day Completion Time clock of Condition A has expi red end s ~b s eq~ent chenges in plent conditi on r es~lt in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status , Condition B is also entered and the Completion Time clocks for Required Actions B. l and B.2 start .

If the RICT expires or is recalculated to be less than the elapsed ti me si nee the Condi ti on *.,ias entered and the inoperable subsystem has not been restored to OPERABLE status , Condition B is also entered and the Completion Time clocks for Required Actions B. l and B.2 start . If the inoperable subsystems are restored to OPER/\BLE status after Condition B is entered , Conditions A is exited , and therefore , the Required Actions of Conditions B may be terminated .

IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

BYRON - UNITS 1 &2 1.3 - 14 Amendment ~

Frequency 1.4 1.0 USE AND APPLICATION

1. 4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirement s.

DESCRIPTION Each Surveillance Requirement CSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation CLCO). An understanding of the correct application of the specified Frequency i s necessary for compliance with the SR .

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Survei 11 ance Requirement (SR) Appl i ca bi l i ty. The "specified Frequency" consists of the requirements of the Frequency column of each SR as 'vv'Cl l as certai A ~Jotes i A Hie SUl"'v'Ci 11 aACC col UFRA Hiat FROdi fy perforFRaACC requi rCFRCAts .

Si tuati oris 'oJAere a Sl:lrvei 11 arice COl:ll d be required ( i . e. , its Frequericy could eHpi re) , but 'vv'Aere it is riot possible or riot desired tFiat it be perforFRed uritil soFRetiFRe aft er tFie associated LCD is 'oJi tFii A its Appl i ca bi l i t,y , represerit poteritial SR 3.0.4 COAflicts . To avoid tACSC COAflicts , tAC SR (i . e. , Hie Survei 11 arice or Hie Freql:leAcy) is stated Sl:lCA tFiat it is orily "reql:lired " 'vv'ACA it cari be arid sfiol:lld be perforFRed . ',Ji tFl ari SR satisfied , SR 3. 0. 4 iFRposes Ao restrictiori .

SoFRetiFRes special situatioris dictate \JACA tFie reql:lireFRerits of a Surveillarice are to be FRet. TFiey are "otfier*ov'ise stated " coriditi oris all m.*ed by SR 3. 0 . 1. Tfiey FRay be stated as clarif,yirig ~Jotes iri tfie Surveillarice , as part of tfie Surveillarice , or botfi . EHaFRple 1. 4 5 discl:lsses tfiese special sitl:latioris .

BYRON - UNITS 1 &2 1.4 - 1 Amendment -+/-Ge-

Frequency 1.4 1.4 Frequency DESCRIPTION (continued)

The use of "met" or "performed" iA H1ese iAstaAces conveys specific meaning. A surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability t o meet the acceptance criteria. SR 3.0.4 restrictioAs 'oJould Aot apply if botA Ule foll mv'i Ag coAdi ti OAS are satisfied .

-er.- n1e Sur'¢ei 11 aAce is Aot required to be perforffled , aAd

-Ir.- Tfie SurveillaAce is Aot required to be Fflet or , eveA if required to be Fflet , is Aot lmmm to be failed .

EXAMPLE-&

illustrates the type of Frequency statements that appears in the Technical Specifications (TS).

BYRON - UNITS 1 &2 1.4 - 2 Amendment Ht-

Frequency 1.4 1.4 Frequency EXAMPLE-& (continued)

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SU RV EI LLANCE FREQUENCY PerforFfl CHnJNEL CHECK . ~ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR Fflost often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) during which t he associated Surveillance must be performed at least one time.

Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.D.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.D.1 (such as when the equipFFlent is inoperable , a variable is outside specified limits, or the ~i s outside ltacilityl ltacility I the Applicability of the LCD ~ If the interval specified by . .

SR 3.D.2 is exceeded while the-ttffi-t. is in a MODE or other specified condition in the Applicability of the LCD, and the perforFflance of the Survei 11 anee is not oU1eNi se Fflodi fi ed (refer to E)(JFflple 1.4 3) , then SR 3.D.3 becomes applicable.

~ t he interval as specified by SR 3.D.2 is exceeded while

~th?ttffi.t. is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to ent ry into the MODE or other specified condition. Failure to do so 'oJould result in a violation of SR 3.0.4.

BYRON - UNITS 1 &2 1.4 - 3 Amendment -+/-Ge.

Frequency 1.4 1.4 Frequency EXAMPLES Ccontinued)

EXA~1PLE 1. 4 2 SU RV EI LLMJCE REQUI RE~1E~JTS SU RV EI LLMJCE FREQUE~JCY Verify flm: is vv'itAin liffiits . Once 'oJi H1i n 12 Aours after

~ 25?6 RTP 24 AOUrS tAereafter

[)taffipl e 1. 4 2 Aas t 'oJO Frequencies . TAC first is a one tiffie perforffiance Frequency , and tAe second is of tAe type sAmvn in [)taffipl e 1. 4 1. TAe logical connector "film " indicates that both Frequency requireffients ffiust be ffiet . Each tiffie reactor pm:er is increased froffi a pm:er level ..;:: 25?6 RTP to

~ 25?6 RTP , tAe Survei 11 ance ffiust be perforffied \o'itAi n 12 AOUrS .

The use of "once " indicates a single perforffiance vJi 11 satisfy tAe specified Frequency (assuffiing no ot Aer Frequencies are connected b)' "Alli) " ) . TAi s t)'PC of Frequency does not qualify for tAe eHtensi on all m:ed by SR 3. 0. 2.

TAereafter " indicates future perforffiances ffius t be establisAed per SR 3.0. 2, but only after a specified condition is first ffiet (i . e., tAe "once " perforffiance in tAis exaffipl e) . If reactor pm:er decreases to ..;:: 25?6 RTP , tAe ffieasureffient of botA intervals stops . Nev: intervals start upon reactor pm:er reacAi ng 25?6 RTP .

BYRON - UNITS 1 &2 1.4 - 4 Amendment -+/-Ge-

Frequency 1.4 1.4 Frequency EXAMPLES Ccontinued)

EXA~1PLE 1. 4 3 SU RV EI LLMJCE REQUI RE~1E~JTS SU RV EI LLMJCE FREQUE~JCY Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after ~ 25% RTP .

Perform channel adjustment . 7 days The interval continues , 1o1hether or not the uni t operation is

~ 25?6 RTP bet\1een performances .

As the Note modifies the required performance of the Survei 11 ance , it is construed to be part of the specified 11 Frequency . Shaul d the 7 day interval be e)(Ceeded '1Jhil e 11 operation is ~ 25?6 RTP , tAi s ~Jote all 0'1JS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after pm1er reaches ~ 25?6 RTP to perform the Survei 11 ance . i=Ae Survei 11 ance is sti 11 considered to be performed '1Ji thin the 11 specified Frequency . Therefore , if the Survei 11 ance '1Jere 11 not performed 'vv'ithi n tAe 7 day (pl us the e)(tensi on all m1ed by SR 3. 0. 2) interval , but operation '1Jas ~ 25?6 RTP , it 'vo'oul d not constitute a failure of the SR or failure t o meet the 1:£8-:- Al so , no vi elation of SR 3. 0. 4 occurs '1Jhen changing MODES , even 'vvi tA the 7 day Frequency not met , provided operation does not e>Eceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 'vJith pm1er ~ 25?6 RTP .

Once the unit reaches 25?6 RTP , 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> '1Joul d be all m1ed for completing the Sur'v'eillance . If the Surveillance 'oJere not performed 'oJi thin this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval , there '1Joul d then be a failure to perform a Survei 11 ance i,vi thin the specified Frequency', and the provisions of SR 3. 0. 3 'oJoul d apply .

BYRON - UNITS 1 &2 1.4 - 5 Amendment -+/-Ge-

Frequency 1.4 1.4 Frequency EXAMPLES Ccontinued)

EXA~1PLE 1. ~ ~

SU RV EI LLMJCE REQUI RE~1E~JTS SU RV EI LLMJCE FREQUE~JCY Only required to be perforffled in MODE 1.

Perforffl cofflplete cycle of the valve . 7 days The interval continues , \Jhether or not the uni t operation is in ~10DE 1, 2, or 3 Ethe assuffled Applicability of U1e associated LCO) bet',1een perforfflances .

As the Note fflodifies the required perforfflance of the Surveillance , the note is construed to be part of the "specified Frequency ." Should the 7 day interval be e)weeded *01hi le operation is not in MODE 1, tAi s Note all o*,1s entry into and operation in MODES 2 and 3 to perforffl the Surveillance . The Surveillance is still considered to be perforffled *,1i thin the "specified Frequency " if cofflpl eted prior to MODE 1. Therefore , if the Survei 11 ance \Jere not perforffled 'oJithin the 7 day (plus the e)(tension allo'oJed by SR 3. 0. 2) interval , but operation \o'as not in MODE 1 , it

\Jould not constitute a failure of the SR or failure to ffleet the LCD . Also , no violation of SR 3.0.4 occurs when changing MODES , even *,1i th the 7 day Frequency not fflet ,

provided operation does not result in entry int o ~10DE 1.

Once the unit reaches MODE 1, the requirefflent for the Survei 11 ance to be perforffled 'vJi thin its specified Frequency applies and \Jould require that the Surveillance had been perforffled . If the Survei 11 ance 'de re not perforffled prior to MODE 1, there \Jould then be a failure to perforffl a Survei 11 ance h'i thin the specified Frequency , and the provisions of SR 3. 0.3 o1ould apply .

1 BYRON - UNITS 1 &2 1.4 - 6 Amendment -+/-Ge-

Frequency 1.4 1.4 Frequency EXAMPLES Ccontinued)

EXA~1PLE 1. 4 S SU RV EI LLMJCE REQUI RE~1E~JTS SU RV EI LLMJCE FREQUE~JCY Only required to be met in MODE 1.

Verify leakage rates are '1Jithin limits . 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

[J(ampl e 1. 4 S specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times , as described in EJ(ampl e 1. 4 1. I lmJever , the Note constitutes an "othenJi se stated " C)Wepti on to the Appl i ca bi l i ty of this Survei 11 ance .

Therefore , if the Survei 11 ance '*Jere not performed 'vJi thin the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval (plus U1e CJ(tension allo*,Jed by SR 3.0. 2) ,

but the unit *,Jas not in MODE 1 , there '1v'Oul d be no failure of the SR nor failure to meet the LCO . Therefore , no violation of SR 3. 0. 4 occurs '1Jhen changing MODES , even \Ji th the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency eJweeded , provided the MODE change '1Jas not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency 'vv'Cre not met) , SR 3. 0. 4 *,Joul d require sati sf:yi ng the SR .

BYRON - UNITS 1 &2 1.4 - 7 Amendment -+/-Ge-

LCD Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION CLCO) APPLICABILITY LCD 3.0.1 LCDs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCD 3.0.2, LCO 3.0. 7, and LCO 3.0.9.

LCD 3.0.2 Upon discovery of a failure to meet an LCD, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s) , completion of tho Required Action(s) is not roquirod unless otherwise stated .

LCD 3.0.3 When an LCO is not met and the associated ACTIONS are not met , an associated ACTION is not provided , or if directed b:Y the associated ACTIONS , the unit shall be placed in a MODE or other specified condition in which the LCO is not appl i ca bl o. Action shall bo i ni ti atod \Ji thin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place tho unit , as applicable , in:

-a-. MODE 3 \vi thin 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;

-b-. MODE 4 \*Jithin 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and

-. MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> .

Exceptions to this Specification are stated in the individual Specifications .

Where corrective measures are completed that permit operation in accordance 'n'i th the LCO or ACTIO~J S , completion of the acti ans required b2J' LCD 3. 0. 3 is not required .

LCO 3.0.3 is onl:Y applicable in MODES 1, 2, 3, and 4.

BYRON - UNITS 1 &2 3.0 - 1 Amendment -200

LCD Applicability 3.0 3.D LCD Applicability O 3.0.4 LC~ When an LCO is not met , entry into a MODE or other specified condition in the Applicability shall only be made:

DELETED -a-. \*/hen the associated ACTIOMS to be entered permit continued operation in the MODE or other specified condition in the /\ppl i ca bi l i ty for an unlimited period of time;

-8.- After perforr-T-lance of a risk assessr-T-lent addressing inoperable systems and components , consideration of the results , deterr-T-lination of the acceptability of entering the MODE or other specified condition in the Appl i ca bi l i ty , and establ i shr-T-lent of risk r-T-lanager-T-lent actions , if appropriate (exceptions to this Specification are stated in the individ~al Specifications); or

-&.-- \*/hen an allo*,.;ance is stated in the individblal valble ,

parar-T-leter , or other Specification .

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are reqblired to cor-T-lply with ACTIOMS or that are part of a shbltdmm of the blni t .

LCD 3.0.5 Eqblipr-T-lent rer-T-loved fror-T-1 service or declared inoperable to cor-T-lply ',Jith /\GTimlS r-T-lay be retblrned to service binder adr-T-linistrative control solely to perforr-T-1 testing reqblired to der-T-lonstrate its OPERAgILITY or the OPERAgILITY of other eqblipr-T-lent . This is an exception to LCD 3.0.2 for the syster-T-1 retblrned to service binder adr-T-linistrative control to perforr-T-1 the reqblired testing to demonstrate OPERAgILITY .

BYRON - UNITS 1 &2 3.0 - 2 Amendment ~

LCD Applicability 3.0 3.0 LCD Applicability LCD 3.0.6 When a supported system LCD is not met solely due to a support system LCD not being met , the Conditions and Required Actions associated with this supported system are not required to be entered . Only the support system LCD ACTIONS are required to be entered . This is an exception to LCD 3.0.2 for the supported system . In this event , an evaluation shall be performed in accordance \Ji th Specifi ca ti on 5. 5.15 , "Safety Function Determination Program CSFDP) ." If a loss of safety function is determined to exist by this program , the appropriate Conditions and Reqbli red Acti ans of the LCO in ..'hi ch the lass of safety 1

function exists are required to be entered .

When a Sbipport system ' s Reqblired Action directs a Sbipported system to be declared inoperable or directs entry into Conditions and Reqblired Actions for a Sbipported system , the applicable Conditions and Required Actions shall be entered in accordance with LCD 3.0.2.

BYRON - UNITS 1 &2 3.0 - 3 Amendment +/-Ge.

LCD Applicability 3.0 3.D LCD Applicability LCD 3.0.7 Exception LCOs allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations . Unless otherwise specified , all other TS requirements remain unchanged . Compl iance with Exception LCOs is optional . When an Exception LCO is desired to be met but is not met , the ACTIONS of the Exception LCO shall be met . When an Exception LCO is not desired to be met ,

entry into a MODE or other specified condition in the Appl i ca bi l i ty shall be made in accordance '"'i th the other appl icable Specifications .

LCD 3.0.8 LCOs , including associated ACTIONs , shall apply to each unit i ndi vi dually , blnl ess othen1i se indicated . h'henever the LCO refers to a system or component that is shared by both units , the ACTIONs will apply to both units simultaneously .

LCD 3.0.9 \~hen one or more required snubbers are unable to perform their associated support function(s) , any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed , and :

.a.-.- the snubbers not abl e to perform their associated support function(s) are associated .:ith only one train 1

or subsystem of a multiple train or subsystem supported s;ystem or are associated ',Jith a single tra i n or subsystem supported system and are able to perform their associated support function 1Ji thin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ; or 1

.g... the snubbers not able to perform their associated support function(s) are associated 1Jith more than one 1

train or subsystem of a multiple train or subsystem supported system and are abl e to perform their associated support function .Ji thin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> .

1 At the end of the specified period the required snubbers must be able to perform their associated support function(s) , or the affected supported system LCO(s) sha l l be declared not met .

BYRON - UNITS 1 &2 3.0 - 4 Amendment ~

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT CSR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless ot herwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO . Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met .

For Frequencies specified as "once ," the above interval extension does not apply .

If a Completion Time requires periodic performance on a "once per . . . " basis , the above Frequency extension applies to each performance after the initial performance .

Exceptions to this ~pecification are stated in the individual ~pecifications .

BYRON - UNITS 1 &2 3.0 - 5 Amendment +/-Ge.

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the surveillance will be met when performed. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

I

- - - - - - - lsR 3. o . 4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3. 0. 3. h'hen an LCO is not FRet dble to Sblrveillances not having been FRet , entry into a MODt or other specified condition in the /\pplicability shall only be FRade in accordance \Jith LCO 3 . 0 . ~ .

This provision shall not prevent entry into MODtS or other specified conditions in the /\ppl i cabil ity that a re reqbli red to coFRply ',Jith ACTIOMS or that are part of a shbltdmm of the blAit .

SR ~ SRs shall apply to each bin it i ndi vi dblally , blnl ess othen1i se

~ 11 indicated .

BYRON - UNITS 1 &2 3.0 - 6 Amendment ~

Spent Fuel Pool Water Level 3.7.14

~

3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Water Level LCD 3.7.14 The spent fuel pool water level shall be~ 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool.

ACTIONS LCD 3.0.3 is Rot applicable .

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water A.1 Suspend movement of Immediately level not within irradiated fuel limit. assemblies in the spent fuel pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool water level is In accordance

~ 23 ft above the top of the irradiated with the fuel assemblies seated in the storage Surveillance racks. Frequency Control Program BYRON - UNITS 1 &2 3.7.14 - 1 Amendment +A-

Spent Fuel Pool Boron Concentration 3.7.15

~

3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Boron Concentration LCD 3.7.15 The spent fuel pool boron concentration shall be~ 300 ppm.

APPLICABILITY: Whenever fuel assemblies are stored in the spent fuel pool.

ACTIONS LCD 3.0.3 is Rot applicable .

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron A.1 Suspend movement of Immediately concentration not fuel assemblies in within limit. the spent fuel pool.

A.2 Initiate action to Immediately restore spent fuel pool boron concentration to within limit.

BYRON - UNITS 1 &2 3.7.15 - 1 Amendment .ffl5.

I NO CHANGES ON THIS PAGE I Spent Fuel Pool Boron Concentration 3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel pool boron In accordance concentration is within limit . with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.7.15 - 2 Amendment 171

Spent Fuel Assembly Storage 3.7.16

~

3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Assembly Storage LCD 3.7.16 Each spent fuel assembly stored in the spent fuel pool shall, as applicable:

a. Region 1 of spent fuel pool storage racks Have an initial nominal enrichment of~ 5.0 weight percent U-235 to permit storage in any cel l location.

b. Region 2 of spent fuel pool storage racks Have a combination of initial enrichment and burnup within the Acceptable Burnup Domain of Figure 3.7.16-1 .

APPLICABILITY: Whenever fuel assemblies are stored in the spent fuel pool.

ACTIONS LCD 3.0.3 is Rot applicable .

CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Initiate action to Immediately LCD not met. move the noncomplying fuel assembly into a location which restores compliance.

BYRON - UNITS 1 &2 3.7. 16 - 1 Amendment -+/-e5-

INO CHANGES ON THIS PAGE I Spent Fuel Assembly Storage 3.7.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify by administrative means the initial Prior to nominal enrichment of the fuel assembly is storing the

~ 5.0 weight percent U-235. fuel assembly in Region 1 SR 3.7.16.2 Verify by administrative means the Prior to combination of initial enrichment and storing the burnup, as applicable, of the fuel assembly fuel assembly is within the Acceptable Burnup Domain of in Region 2 Figure 3.7.16-1.

BYRON - UNITS 1 &2 3. 7 . 16 - 2 Amendment 165

I NO CHANGES ON THIS PAGE I Spent Fuel Assembly Storage 3.7.16

()

'!,.~)  :~ :5. :-) 4 '1.:-1 INITIAL U-235 ENRICHMENT (w/o)

Figure 3.7.16-1 (page 1 of 1)

Region 2 Fuel Assembly Burnup Requirements BYRON - UNITS 1 &2 3. 7 . 16 - 3 Amendment 165

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site Location The site is located in Rockvale Township, approximately 3.73 mi (6 km) south-southwest of the city of Byron in northern Illinois.

4 .1. 2 [)(Cl l:lS i GA Area Bol:lAda ry E EP,B) ~<---ii Deleted I TAC EAB SRall AOt be less tRaA 1q60 ft (qqs ff1Cters) froffi tAC Ol:lter COAtai AfflCAt *, :all .

4. 1. 3 Lmo* Pop1:1l ati GA ZoAe E LPZ) ~<--11 Deleted I TAC LPZ SRall be a 3.0 ffli (q828 fflCter) radil:lS fflCaSl:lred froffl tRC ffli dpoi At bet*,:eeA tAe tvvo reactors .

4. 2 Reactor Core ~<--I Deleted I q,2.1 Fl:lel Assefflblies TRe reactor sRall coAtaiA 193 fl:lel assefflblies . EacR assefflbly sRall coAsist of a fflatri)( of Zircaloy , ZIRUf , or Optifflized ZIRLOlM clad fl:lel rods '1JitA aA iAitial cofflpositioA of Aatl:lral or sligRtly eAricRed l:lraAil:lffl dim<ide (UO~ ) as foel fflaterial . Lifflited Sl:lbstit1:1ti0As of zircoAil:lffl alloy or staiAless steel filler rods or vacaAci es for fl:lel rods , i A accordaAce *,:i tR appro'ted appl i cati OAS of fl:lel rod c0Afig1:1rati0As , fflay be l:lsed . Fl:lel assefflblies sRall be l ifflited to tRose f1:1el desi gAs tRat Rave beeA aAalyzed *, :itR applicable ~JRC staff approved codes aAd fflCtRods aAd sRmm by tests or aAalyses to cofflply vvitR all foel safety desigA bases . A lifl'lited Al:lfl'lber of lead test assefl'lblies (LTAs) tRat Rave Aot cofflpleted represeAtative testiAg ffla]' be placed iA AOAlifflitiAg core regiOAS .

Dl:lri Ag UAit 2 Cycles 22 ' 23 ' JAd 24 ' tvv'O LTAs COAtai Ai Ag l:lp to t'1:eAty total l cad test rods fflay be pl aced i A tRe reactor for eval l:lati OA . TAC LTA rods coAtai Ai Ag l:lraAi l:lffi silicide fl:lel pellets aAd rods coAtai Ai Ag staAdard UO~ foel pellets vvi tR coated cl addi Ag SRall be AOAlifl'litiAg . TAC LT1!\ rods COAtaiAiAg 1!\DOPTlM fl:lel pellets fl'lay be loaded iA core regioAs *,*FiicA are AOAlifflitiAg l:lAder steady state reactor coAditioAs aAd sRall cofflply vvitA fl:lel lifflits specified iA tFie COLR aAd TCCAAical SpecificatiOAS l:lAder all operatioAal COAditiOAS .

BYRON - UNITS 1 &2 4.0 - 1 Amendment 206/207

Design Features 4.0 4.0 DESIGN FEATURES

~ Reacto r Core (coAti Auee)

~ .2.2 CoAtFol Roe Asseffiblies TAC FeactoF COFC SAall COAtaiA 53 COAtFol FOG asseffiblies . +fte.

COAtFol ffiateFial SAall be sil¥eF iA8iuffi caeffiiUffi , AafAiUffi , OF a ffii )(tu Fe of botA types .

4. 3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained, as applicable, with:

a. Fuel assemblies having a maximum U-235 enri chment of 5.0 weight percent;

b. A k~ff :::; 0.95 if fully flooded with unborated water, which inc1udes an allowance for uncertainties as described in Holtec International Report HI-982094, "Criticality Analysis for Byron/ Braidwood Rack Installation Project," Project No.

80944, 1998;

c. A nominal 10.888 inch north-south and 10.574 inch east-west center to center distance between fuel assemblies placed in Region 1 racks; and

d. A nominal 8.97 inch center to center distance between fuel assemblies placed in Region 2 racks.

4.3.2 Drainage The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 410 ft, 0 inches.

4. 3. 3 Capacity The spent fuel pool is designed and shall be maintained with a st orage capacity limited to no more than 2984 fuel assemblies.

BYRON - UNITS 1 &2 4.0 - 2 Amendment 206/207

TS Markups unchanged from Attachment 2 of Byron Administrative Controls LAR submitted on Responsibility September 24, 2020 (ML20269A401) 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 shift manager 5.1.2 A shall be responsible for the coAtrol POOFA command function 0JAile eitFier 1:1Ait is iA HOOE 1, 2, 1

3, 012 4. For eacFi 1:1Ait , aA SRO FAay be desi§Aated as 12esp0Asible fop tAC COAtrol POOFA COFAFAaAd f1:1Acti OR . ',JF!i le botA 1:1Ai ts a PC i Fl MODE 5 012 e, 012 def1:1el ed, aA i Adi vi d1:1a l il'i t Fi aA acti ve SRO l i ceAse 1

or Reactor Operator l iceAsc sFiall be desi gAated to ass1:1FAe t Fie COAtrol POOFA COFAFAaAd f1:1ActioA .

BYRON - UNITS 1 &2 5.1 - 1 Amendment -+/-Ge-

TS Markups unchanged from Attachment 2 of Byron Administrative Controls LAR submitted on September 24, 2020 (ML20269A401) Organization

5. 2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organizat ion the safe storage and handling 5.2.1 Onsite and Offsite Organizations of irradiated fuel.

Onsite and offsite organizations shall be es ablished for facility operatioA and corporate management, respecti ely. The onsite and

~ offsite organizations shall include the po tions for activities affecting safet)' of Hie Al:Wl ear po'oJer pl arit . facility

a. Lines of authority, responsibility, and commu ication shall be defined and established throughout highes anagement levels, intermediate levels, and all operatiAg organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentat ion. These Exelon Decommissioning re uirements including the generic titles of t hose personnel fulfilling the responsibilities of the positions delineated in th Technical Specifications, shall be 1.-fa-c-ili-ty....,I documented in the Quality Assurance Program; storage Iplant I

b. Th~statioA manage~shall be responsible for operation of the pl arit and shall have contra ver those

!handling on~ite activities necessary for safe operati OA and .-h-a-ve-c-or_p_o-ra_t_e...,

. ~ Ria1 riteriarice of Hie pl ari'4i:- * . ..

IA responsible officer ~ '"--iirradiated fuel I respons1b1hty

=======:----' c. The Chief ~J uc l ear Officer shall be resporisi ble or overall the safe storage ~pl arit riucl ear safety and shall take any measures needed to ~

and handling of 1---_,.,.. ensure acceptable performance of the staff in operatirig , J?. i..:..=.:.:.:..

irradiated fuel mai ntai ni ng-;- and providing techni ca 1 support to the pl arit to safe storage and ,______e_n_s_ ur~e Auel ear safety ; and ~CERTIFIED FUEL HANDLERS I handling of d. The individuals who train the operatirig staff , or perform irradiated fuel health pFiys i cs or qua 1i ty assurance functions, may report to Iradiation protection ~~~~ 1fPh~~~r~~~~i ~~~~ie o~~~~{~~f i ~~~fv~~ee~~~s~o i ~~~~~~u~~~i r irideperiderice froffi operatirig pressures .

ability to perform their assigned functions.

BYRON - UNITS 1 &2 5.2 - 1 Amendment -+/

TS Markups unchanged from Attachment 2 of Byron Administrative Controls LAR submitted on September 24, 2020 (ML20269A401) Organization 5.2 Each duty shift shall be composed of at least one shift manager and two NON-CERTIFIED 5.2 Organizat ion

~~~~~~~~~~~~--I'=!

OPERATORS. The NON-CERTIFIED OPERATOR position may be filled by a 5.2.2 Facility Staff CERTIFIED FUEL HANDLER.

The facility staff organization shall include the following:

a.

b.

during the movement of irradiated fuel and during movement of loads over irradiated fuel A radiation protection technician shall be on sit '1.4=1rn fuel is iA tAe reactor . The position may be vacant for t more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected abse e, provided immediate action is taken t o fill the required position. Oversight of irradiated fuel handling The shift operations shall be provided by a Deleted . CERTIFIED FUEL HANDLER.

manager shall be a CERTIFIED TAe operatioAs maAager or tAe supervisor iA cAarge of tAe FUEL HANDLER. operati OAS SAi ft crC'oJS SAal l AOl d aA SRO l i ceAse .

At all times when irradiated fuel is and the following conditions are met:

stored in the spent fuel pool, at least

1) No movement of irradiated fuel is in one person qualified to stand watch in progress; the control room (NON-CERTIFIED

2) No movement of loads over irradiated OPERATOR or CERTIFIED FUEL fuel is in progress.

HANDLER) shall be present in the This provision does not permit any shift control room.

crew position to be unstaffed upon shift change due to the absence or tardiness of an oncoming shift crew member BYRON - UNITS 1 &2 5.2 - 2 Amendment .ffl2.

TS Markups unchanged from Attachment 2 of Byron Administrative Controls LAR submitted on September 24, 2020 (ML20269A401) Facility Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications referenced for comparable positions as specified in the Exelon Qciality AssciPaAcc Topical Report .

Decommissioning Quality Assurance Program 1 I

An NRG-approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained.

BYRON - UNITS 1 &2 5.3 - 1 Amendment -283-

TS Markups unchanged from Attachment 2 of Byron Administrative Controls LAR submitted on September 24, 2020 (ML20269A401)

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS applicable to the safe

- storage and handling 5.4 Procedures of irradiated fuel 5.4.1 Written procedures shall be estcblished, implemented, and maintained covering the followirg activities:

a. The appl i casl e proceduresvrecommended in Regulatory Guide 1.33, Revision 2, Appendi x A, February 1978;

b. Tt=ie eFAergeAcy operatiAg proced1::1res req1::1ired to iFApl eFAeAt tt=ie

~ }1 req1::1i PCFFICAts of ~J U Rm 0737 aAd ~J U REG 0737 ' S1::1ppl CFFICAt 1, as

~ st at ed iA GeAeri c Letter 82 33 , SectioA 7.1;

c. Fire Protection Program implementation; and

d. All programs specified in Specificat ion 5.5.

BYRON - UNITS 1 &2 5.4 - 1 Amendment -+/-Ge-

I NO CHANGES ON THIS PAGE I Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implement ed, and maintained.

5.5.1 Offsite Dose Calculation Manual (QDCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program;

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3; and

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain :

i. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and ii. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2. Shall become effective after the approval of the station manager; and BYRON - UNITS 1 &2 5.5 - 1 Amendment 106

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (QOCM) (continued)

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Primary Coolant Sources Outside Containment IDELETED ~This program provides controls to minimize leakage from those

~---~ portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable . The systems include the recirculation portions of the Containment Spray , Safety Injection ,

Chemical and Volume Control , and Resi db1al Heat Removal . .Tfie.

program shall include the following:

.a-. Preventive maintenance and periodic visual inspection requirements; and

-9....- Integrated leak test requirements for each system at least once per ig months .

The provisions of SR 3.0. 2 are applicable .

5.5.3 Deleted .

!DELETED ~

BYRON - UNITS 1 &2 5.5 - 2 Amendment -+/-w.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses t o members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures , and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendi x B, Table 2, Column 2 (to paragraphs 20.1001 - 20.2402);

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each ~nit to unrestricted areas, conforming to 10 CFR 50, Appendi ~ 1; the facility

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days; BYRON - UNITS 1 &2 5.5 - 3 Amendment -+/-fil

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the following:

1. For noble gases: ~a dose rate of 500 mrem/yr to the whole body and~ a dose rate of 3000 mrem/yr to the skin, and

2. For Iodine-131, Iodine-133, Tritium, and for all radionuclides in particulate form with half lives

> 8 days: ~ a dose rate of 1500 mrem/yr to any organ;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from ~

tlH+-t to areas beyond the site boundary, conforming to lthe facility ~10 CFR 50 ' Appendix I; the facility

i. Limitations on the annual and quarterly doses to a member of the public from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with lf lives> 8 days in gaseous effluents released from

• to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit

.-ID_E_L_E_T_E_D___,~Thi s program provides controls to track the UViAR , ~ecti on 3. 9, cyclic and transient occ~rrences to ens~re that components are maintained .:ithin the design 1imits .

1 BYRON - UNITS 1 &2 5.5 - 4 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre Stressed Concrete Containment Tendon SLirveillance Program IDELETED J This program provides controls for monitoring any tendon degradation in pre stressed concrete contai nrnents , incl Lidi ng effectiveness of its corrosion protection rnediLim , to ensLire containment strLictLiral integrity . The program shall inclLide baseline rnea sLi rernents prio r to initial ope rations . The Tendon SLirveillance Prograrn , inspection freqLiencies , and acceptance criteria shall be in accordance with Section XI , SLibsection IWL of the ASME Boiler and PressLire Vessel Code and applicable addenda as reqLii red by 10 CFR 50 . 55a , except \*Jhere an alternative , exernption , or relief has been aLithorized by the ~lRC .

Deterrnining pre stressing forces for inspections shall be consistent with the recornrnendati ans of Reg Lil atory GLii de 1. 35 .1, JLil y 1990 .

The provisions of SR 3.0.3 are applicable to the Tendon SLirveillance Program inspection freqLiencies .

5.5.7 Reactor Coolant PLimp Flywheel Inspection Prograrn l~D-E_L_E_T_E_D-JThi s prograrn shall provide for the inspection of each reactor coolant pLimp fl)~~heel in general conformance with the recornrnendations of RegLilatory Position c.4.b of RegLilatory GLiide 1.14 , Revision 1, ALigList 1975 .

Fo r reactor coolant pLirnp rnotor serial nLirnbers 4sggp951 and 1sggp961 , in lieLI of RegLilatory Position c.4.b(l) and c.4.b(2) , a qLialified in place UT exarnination over the volLime frorn the inner bo re of the fl)~Jheel to the circle of one half the oLiter radiLis or a sLirface exarnination (MT and/ or PT) of exposed sLirfaces of the rernoved f l )~ Jheel rnay be condLicted at app roxirnatel y 10 yea r intervals coi nci ding \Ji th the Inservi ce Inspection schedLil e as reqLii red by ASME Section XI.

For all other reactor coolant pLirnp motors , in lieLI of RegLilatory Position c.4. b(l) and c.4.b(2) , a qLialified in place UT exarnination over the volLirne frorn the inner bore of the flywheel to the circle of one half the OLiter radiLis or a sLirface exarnination (MT and/ or PT) of exposed sLirfaces of the rernoved flywheel rnay be condLicted at an interval not to exceed 20 years .

BYRON - UNITS 1 &2 5.5 - 5 Amendment -+/-@

INO CHANGES ON THIS PAGE I Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 DELETED BYRON - UNITS 1 &2 5.5 - 6 Amendment 197

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 St earn Generator CSG) Program

~ID_E_L_E_T_E_D~~ A Stearn Generator Program shall be established and implemented to ensure that SG tube integrity is maintained . In addition , the St earn Generator Program shall include the following:

.a.- Provisions for condition monitoring assessments . Condition monitoring assessment means an evaluation of the "as found "

condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage . The "as found " condition refers to the condition of the tubing during an SG inspection outage , as determined from the inservice inspection results or by other means ,

prior to the plugging of tubes . Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met .

ft. Performance criteria for SG tube integritj SG tube 1

integrity shall be maintained by meeting the performance criteria for tube structural integrity , accident induced leakage , and operation al LEAKP.GE .

-+/--.- Structural integrity performance criterion: All in service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup , operation in the pm1er range , hot standby , and cool dmm) , all anticipated transients included in the design specification , and design basis accidents . This includes retaining a safety factor of 3.0 against burst under normal steady state full po',Jer operation primary to secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary to secondary pressure differentials . /\part from the above requirements , additional loading conditions associated \Jith the design basis accidents ,

or combination of accidents in accordance with the design and licensing basis , shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse . In the assessment of tube integrity , those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure

\Jith a safety factor of 1. 2 on the cornbi ned primary loads and 1. 0 on axial secondary loads .

BYRON - UNITS 1 &2 5.5 - 7 Amendment -+/-

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 St earn Generator CSG) Program (continued) b /\cci dent induced leakage performance criterion : +fie.

primary to secondary accident induced leakage rate for any design basis accident , other than a SG tube rupture , shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG .

Leakage is not to exceed a total of 1 gprn for all SGs .

Jo- The operation al LE/\K/\GE perforr-i:iance criteria is specified in LCD 3. 4.13 , "RCS Operational LE/\K/\GE ."

.&,- Provisions for SG tblbe pl bl~ffJi ng criteria . Tblbes foblnd by inservice inspection to contain flaws with a depth eqblal to or exceeding 40% of the nor-i:iinal wall thickness shall be plblgged . The following alternate tblbe plblgging criteria shall be applied as an alternative to the 40% depth based criteria :

For Unit 2, tblbes with service indblced flaws located greater than 14 .01 inches below the top of the tblbesheet do not reqblire plblgging . Tblbes with service i ndblced fl a',:s located in the port ion of the tblbe fror-i:i the top of the tblbesheet to 14 .01 inches bel m: the top of the tblbesheet shall be plb1gged blpon detection .

4.- Provisions for SG tube inspections . Periodic SG tube inspections shall be perforr-i:ied . The nur-i:iber and portions of the tubes inspected and r-i:iethods of inspection shall be perforr-i:ied ',Ji th the objective of detecting fl a1t1s of any type (e .g., volur-i:ietric fla',JS , axial and circur-i:iferential cracks) that r-i:iay be present along the length of the tube , fror-i:i the tube to tubesheet weld at the tube inlet to the tube to tubesheet '.Jel d at the tube outlet , and that may sati sty the applicable tube plugging criteria . For Unit 2, portions of the tube belo\1 14 .01 inches from the top of the tubesheet are excluded fror-i:i this requirer-i:ient .

BYRON - UNITS 1 &2 5.5 - 8 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator CSG) Program (continued)

The tube to tubes heet '11 el d is not pa rt of the tube . -+/-++

1 addition to meeting the requirements of d. l , d.2, and d.3 below , the inspection scope , inspection methods , and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection . A degradation assessment shall be performed to determine the t:ype and location of fl a1:1s to which the tubes may be susceptible and , based on this assessment , to determine

',Jhi ch inspection methods need to be employed and at \Jhat locations .

-+/--.- Inspect 100% of the tubes in each SG during the first refueling outage following SG installation .

b For Unit 1, after the first refueling outage foll m\'i ng SG installation , inspect each SG at least e'Jery 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections) . In addition , the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b, c, and d below . -I-f--a-degradation assessment indicates the potential for a t:ype of degradation to occur at a location not previously inspected *,1i th a technique ca pa bl e of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria , the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated .

The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a nm; form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period . tach inspection period defined belm1 may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage .

BYRON - UNITS 1 &2 5.5 - 9 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 St earn Generator CSG) Program (continued)

-a-+ After the first refueling outage following SG installation , inspect 100% of the t ubes during the next 144 effective full pov. 'er months . +R-i-&

constitutes the first inspection period ;

During the next 120 effective full power months ,

inspect 100% of the tubes . This constitutes the second inspection period; During the next 96 effective full power months ,

inspect 100% of the tubes . This constitutes the third inspection period; and 4+ During the remaining life of the SGs , inspect lOO~b of the tubes every 72 effective full power 1+1onths . This constitutes the fourth and subsequent inspection periods .

J.. For Unit 2, after the first refueling outage foll 0 .Ji ng 1 SG installation , inspect each SG at least every 48 effective full pmmr months or at least every other refueling outage (\Jhichever results in more frequent inspections) with the exception that each SG is to be inspected during the third refueling outage in B2R23 following inspections completed in refueling outage B2R20 . In addition , the 1+1ini1+1u1+1 nu1+1ber of tubes inspected at each scheduled inspection shall be the nu1+1ber of tubes in all SGs divided b:Y the nu1+1ber of SG inspection outages scheduled in each inspection period as defined in a, b, and c belo\J . If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected ',Ji th a technique ca pa bl e of detecting this type of degradation at this location and that may satisf:Y the applicable tube plugging criteria , the mini mum nurnbe r of locations inspected \i'ith such a capable inspection technique during the remainder of the inspection period may be prorated . The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be BYRON - UNITS 1 &2 5. 5-10 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 St earn Generator CSG) Program (continued) inspected in the inspection period after the deterrni nation that a nmJ form of degrada t ion could potentiall y be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period . Each inspection period defined below may be extended up t o 3 effective full po\ffir months to include a SG inspect ion outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage .

.a.+ After the first refblel i ng obit age foll m1i ng SG installation , inspect 100% of the t blbes dblring the next 120 effective full power months . +4-i-&

constitbltes the first inspection period; During the next 96 effective full power months ,

inspect 100% of the tubes . This constitutes the second inspection period; and Dblring the remaining life of the SGs , inspect 100?& of the tblbes every 72 effective fbll l pm:er months . Thi s consti tbltes t he t hi rd and sblbseqblent inspection periods .

4-.- P"or Unit 1, if crack i ndi cations are foblnd in any SG tube , then the next inspection for each affected and potentially affected SG for the degradation mechanism that cablsed the crack indication shall not exceed 24 effective full pm:er months or one refueling Obltage

( ,Jhi chever results in more freqblent in spections ). ~

1 Unit 2, if crack indications are foblnd in any SG tblbe from 14 .01 inches below the top of the tblbesheet on the hot leg side to 14 .01 inches belm: the top of the tubesheet on the cold leg side , then the next inspection fo r ea ch affected and potentiall y affected SG for the degradation mechanism that cablsed the crack indication shall not exceed 24 effective fblll pmffir months or one refueling outage (\Jhi chever results in more freqblent inspections) .

If definitive information , such as from examination of a pbllled tblbe , diagnostic non destructive testing , or engineering evaluation indicat es that a crack like i ndi cation i s not associated 'di th a crack( s ) , then the indi cation need not be treated as a crack.

.e.- Provisions for monitoring operational primary to secondary LE/\KAGE .

BYRON - UNITS 1 &2 5. 5-11 Amendment -+/-

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Secondary Water Chemistry Program 1.--D-E_L_E_T_E_D----.i-J This program provides controls for monitoring secondary ,..;ater 1

. . chemistry to inhibit SG tube degradation . The program shall include :

-a.- Identification of a sampling schedul e for the critical variables and control points for these variables;

-8.- Identification of the procedures used to measure the values of the critical variables ;

-G.- Identification of process sampling points , which shall include monitoring the discharge of the condensate pumps for evidence of condenser inleakage;

.fl.-.- Procedures for the recording and management of data;

.e.- Procedures defining corrective actions for all off control point chemistry conditions; and

.:h- f\ procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of admi ni strati ve events , .:hi ch is required to i ni ti ate 1

correcti ve acti on.

BYRON - UNITS 1 &2 5. 5 - 12 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Prograrn CVFTP)

-ID_E_L_E_T-ED-~ A prograrn shall be established to irnpl ernent the following required testing of Engineered Safety Feature CESF) filter ventilation systerns at the frequencies specified in conforrnance with Regulatory Guide 1.52 , Revision 2, and ANSI N510 1980 , with any exceptions noted in Appendix A of the UFSAR .

-a-. Dernonstrate for each of the ESF filter systerns that an inplace test of the High Efficiency Particulate Air (HEPA) filters shows a penetration specified below when tested in conforrnance

\Jith Regulatory Gui de 1. 52 , Revision 2, and /\~lSI N510 1980 ,

with any exceptions noted in Appendix A of the UFSAR , at the systern flow rate specified below . Verification of the specified flow rates rnay be accornplished during the perforrnance of SRs 3.7.10 .4, 3.7.12 .4, and 3.7.13 .5, as applicable :

ESF Ventilation Fl m*1 Rate Penetration Sy stern Control Roorn ~ 5400 cfrn and < 0 . 05~b Ventilation CVC) ~ 6600 cfrn Filtration Systern (rnakeup)

Nonaccessible Area ~ 55 ,669 cfrn and Exhaust Filter ~ 68 ,200 cfrn per Plenurn Ventilation train , and Systern (after ~ 18 ,556 cfrn and structural ~ 22 ,733 cfrn per rnaintenance of the ~

HEPA filter housings)

Nonaccessible Area ~ 55 ,669 cfrn and Exhaust Filter ~ 68 ,200 cfrn per Plenurn Ventilation train S:ystern (for reasons other than structural rnaintenance of the HEPA filter housings)

Fuel Handling ~ 18 ,900 cfrn and Building Exhaust ~ 23 , 100 cfrn Filter Plenurn CFHB)

Ventilation Systern BYRON - UNITS 1 &2 5.5-13 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Prograrn CVFTP) Ccontim~ed)

-8... Dernonstrate for each of the ESF filter systerns that an inplace test of the charcoal adsorber shov1s a bypass specified bel o'"'

• ,1hen tested in conforrnance ',Ji th Regul atory Gui de 1. 52 ,

Revision 2, and ANS I N5 10 1980, with any exceptions noted in f\ppendi x f\ of the UFS/\R , at the systern fl m1 rate specified bel m:. Veri fi cation of the specified fl o*.1 rates rnay be accornplished during the perforrnance of SRs 3.7.10 .4, 3.7.12 .4, and 3.7.13 .5, as applicab l e:

ESF Ventilation Systern Fl m1 Rate VG Filtration Systern ~ 5400 cfrn and (rnakeup) ~ 6600 cfrn VG Filtration Systern ~ 44 ,550 cfrn and < o.a (recirculation , charcoal ~ 54 ,450 cfrn bed after cornplete or partial replacernent)

VG Filtration Systern ~ 44 ,550 cfrn and (reci rculat ion for ~ 54 ,450 cfm reasons other than cornplete or partia l charcoal bed replacernent)

Nonaccessible Area ~ 55 ,669 cfrn and Exhaust Filter Plenurn ~ 68 ,200 cfrn per Ventilation Systern train , and (after structural ~ 18 ,556 cfrn and rnaintenance of the ~ 22 ,733 cfrn per charcoal adsorber ~

housings)

Nonaccessible Area ~ 55 ,669 cfrn and Exhaust Filter Plenurn ~ 68 ,200 cfrn per Ventilation Systern (for train reasons other than structural rnaintenance of the charcoal adsorber housings) mg Ventilation Systern ~ 18,900 cfrn and

~ 23 ,100 cfrn per train BYRON - UNITS 1 &2 5. 5 - 14 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Prograrn CVFTP) CcontimJed) t.- Dernonstrate for each of the ESF filter systerns that a laboratory test of a sarnpl e of the charcoal adsorber , \Jhen obtained as described in Regulatory Guide 1.52 , Revision 2, shows the rnethyl iodide penetration less than the value specified bel o*,1 *,1hen tested in conforrnance *,1i th Regulatory Guide 1. 52 , Revision 2, ANSI N510 1980 , and ASTM 03803 1989 ,

\Jith any exceptions noted in Appendi x A of the UFSAR , at a ternperature of 30°C and a Relative Hurni di ty CRH) specified bel O\'/:

ESF Ventilation System Penetration -Rl=4 VG Filtration System b-G% .f.Q%.

(makeup)

VG Filtreition System 4% .f.Q%.

(recirculation)

Nonaccessible Area 4-,.g .f.Q%.

Exhaust Filter Plenum Ventilation System FHg Ventil eiti on Syst em 4-.- Demonstrate for each of the ESF filt er systems that t he pressure drop across the combined HEPA filters and the charcoal adsorbers is < 6 inches of \later gauge *i1hen tested in conformance *.:i th Regulatory Gui de 1. 52 , Revision 2, and MJSI

~1510 1980 , *i1ith any exceptions noted in Appendi x A of the UFS/\R , at the system fl m1 rate specified bel O'.J . Verification of the specified fl m1 rates may be accompli shed du ring the performance of SRs 3.7. 10 .4, 3.7.12 . 4, and 3. 7. 13 .5, as applicable:

ESF Ventilation System Fl mv Rate VG Filtration S:ystem ~ 5400 cfm and ~ 6600 cfm (rnakeup)

Nonaccessible Area ~ 55 ,669 cfm and Exhaust Filter Plenurn ~ 68 ,200 cfm per train Ventilation System FHB Ventilation System ~ 18 ,900 cfm and

~ 23,100 cfm BYRON - UNITS 1 &2 5. 5 - 15 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5 . 5 . 11 Ventilation Filter Testing Prograrn CVFTP) CcontimJed)

-e.- Dernonstrate for each of the ESF filter systerns that a bypass test of the cornbined HEPA filters and darnper leakage shrn1s a total bypass specified bel o*.1 at the systern fl o*.1 rate specified below . Verification of the specified flow rates rnay be accornplished during the perforrnance of SRs 3.7.12 .4 and 3.7.13 .5, as applicable:

ESF Ventilation Systern Fl O'.J Rate Bypass Nonaccessible Area  ;;; 55 ,669 cfrn Exhaust Filter Pl enum -6:00 Ventilation System ~ 68 ,200 cfm per train FHB Ventilation System  ;;; rn ,900 cfm

-6:00

~ 23 ,100 cfm

.f.- Demonstrate that the heaters for each of the ESF filter systerns dissipate the value specified below when tested in conformance with ANSI N510 1980 , with any exceptions noted in Appendi x A of the UFSAR .

ESF Ventilation System 1

..iattage VG Filtration System  ;;; 24 . 0 1~ 1,o/

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies .

BYRON - UNITS 1 &2 5. 5 - 16 Amendment ~

I NO CHANGES ON THIS PAGE I Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the waste gas system, the quantity of radioactivity contained in gas decay tanks or fed int o the off gas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure." The liquid radwaste quantities shall be determined in accordance with the ODCM.

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the waste gas system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria Ci .e., whether or not the system is designed to withstand a hydrogen explosion);

b. A surveillance program to ensure that the quantity of radioactivity contained in each gas decay tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of~ 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and

c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

BYRON - UNITS 1 &2 5. 5-17 Amendment 158

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Diesel FLiel Oil Testing Program

~ID_E_L_E_T_E_D~~ A diesel fLiel oil testing program to implement reqLiired testing of both nmiJ foel oil and stored fLiel oil shall be established . -Tfte-program shall inclLide sampling and testing reqLiirements , and acceptance criteria , all in accordance with applicable ASTM St andards . The pLirpose of the program is to establish the fol lowing:

-a.- /\cceptabi l i ty of nmJ foel oil for Lise prior to addition to storage tanl<s by determining that the fLiel oil has :

h an /\PI gravity or an absol Lite specific gravity 'tJithi n limits ,

b a flash point and kinematic viscosity \*Jithin limits , and J-.- a cl ear and bright appea ranee \*Jith proper col or or a water and sediment content within limits;

-b. Ot her properties of ne'"' fLiel oil are within limits ,.,,ithin 30 days following sampling and addition to storage tanl<s ; and

-c. Total partirnlate concentration of the fLiel oil is~ 10 mg/ l

'l.Jhen tested every 31 days .

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel FLiel Oil Testing Program test freqLiencies .

BYRON - UNITS 1 &2 5.5-18 Amendment ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Technical Specifications CTS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. a change in the TS incorp jn the license; or DSAR

2. a change to the UFSAR r Basest at requires NRC approval pursuant to 10 CFR 50. 59. DSAR

c. The Bases Control Program shall contain provisions t nsure that the Bases are maintained consistent with the UFSAR .

d. Proposed changes that meet the criteria of Specification 5.5.14.b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.7l(e) as modified by approved exemptions.

BYRON - UNITS 1 &2 5. 5 - 19 Amendment ~