Text

Proposed Tech Specs Reducing Reporting Requirements for Iodine Spiking from short-term Rept to Item Included in Annual Rept
	ML20206T688
Person / Time
Site:	LaSalle
Issue date:	06/27/1986
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20206T677	List: ML20206T670; ML20206T688;
References
	1762K, NUDOCS 8607080208
	Download: ML20206T688 (10)
	v • d • e

.- .- . . - _ _ _ _ _ _ .

ATTAODEDIT A I

PROPOSED CHANGE M APPENDIX A TECHNICAL SPECIFICATIONS TO OPERATING LICENSE NPF-11 NPF-18 i REVISED PAGES: 3/4 4-13 3/4 4-14 3/4 4-14 3/4 4-15 6-21 6-21 B 3/4 4-3 B 3/4 4-3 8607080208 860627 PDR ADOCK 05000373 P PDR ,

1762K

l CAUTION ,

THIS COCU:?D!T/0: '".!i:'G 13 m.a, 20a REACTOR COOLANT SYSTEM AQ\p'..;q:~.:"..-. :.-

lt 40 o ; .

3/4.4.5 SPECIFIC ACTIVITY .i. .. ". . , ,. :. :, ,.., r

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LIMITING CONDITION FOR OPERATION ' O ' ' T ' *fi ' *. ~ ~ ~ ;

I. 7_.

3.4.5 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT I-131, and

b. Less than or equal to 100/I microcuries per gram.

t APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and 4. .

ACTION:

l- __ a. In OPERATIONAL CONDITIONS 1, 2 or 3 with the specific activity of g, the primary coolant;

>Ese z

u, a - -

mo 1. Greater than 0.2 microcuries per gram DOSE EQUIV,ALENT I-131 but p g ,L g lessthanorequalto4.0microcuriespergrams:;:r:tterm:y 2; gg _

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"Ee AC;L Greater than'100)I microcuries per gram, be in at least HOT

+5 ,9 5-e: E SHUTDOWN with the main steamline isolation valves closed within e

Ea 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

E E U =s In OPERATIONAL CONDITICilS 1, 2 3 or 4, with the sp'ecific activity au..

a u, *g of the primary coolant greater'than 0.2 microcurie per gram DOSE g3,g EQUIVALENT I-131 or greater than 100 i microcuries per gram . perform .

'- g * , the sampling and analysis requirements of Item 4a of Table 4.4.5-1

. g h,.5

until the specific activity of the primary coolant is restored to u.g within the limit.

S; :i:1 *:;:-t :h:!' 5: ;r:;;.;d .c.d . L... i;;d -

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LA SALLE-UNIT 1 3/4 4 Amendment No.23 i

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REACTOR COOLANT SYSTEM . . . . . :.

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LIMITING CONDITION FOR OPERATION (Continuedl"* - 7 7 .

l ACTION (Continued)

c. In OPERATIONAL CONDITION 1 or 2, with:

1. THERMAL POWER changed by more than 155 of RATED THERMAL POWER in ps 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ", or

2. The off gas level, prior to the holdup line, increased by more l

than 25,000 microcuries per second in one hour during steady l state operation at release rates less than 100,000 microcuries :'

per second, or

3. The off-gas level, prior to the holdup line, increased by more than 15% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during steady state operation at release pg rates greater than 100,000 microcuries per second, perform the sampling and analysis requirements of Item 46 of ;

Table 4.4.5-1 until the specific activity of the primary coolant is ;

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! restored to within its limit. . _;:r; :.. :- t- 05: - '::'::

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SURVEILLANCE REQUIREMENTS 4.4.5 The specific activity of. thf, reactor coolant shall be demonstrated to be within the limits by perforinsoce of the sampling and analysis program of Table 4.4.5-1.

a Not applicable during the Startup Test Program.

LA SALLE - UNIT 1 3/4 4-14 Amendment No. 38

=-

l ADMINISTRATIVE CONTR01.5 .

g, ANNUAL REPORTSG7 ('02:c o--"n +m= "'" %e**""

s} } , . s Shes it be a.% cluded *N fl<

% eum / repul-<.lon3 WJ4 The results of specific activity analysis ih which the primary coolant exceeded the limits of Specification 0.0.0 s'% e..J C pie..u). s 0.0.; 'Z% ,,1;..n; a 3.4.5 ' pie..; ftMe fonowing informationr sheE=6e=daeleded: (1) Reactos power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of -

the last isotopic analysis for radiciodine performed prior to ex- l ceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which' the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine .

Ifnit.

l

~

CAUTION

' THIS DOCUMENT / DRAWING iS FOR ADMINISTRATIVE REFERENCE CNLY.

IT SHALL NOT BE USED FOR MAIN-TENANCE, OPERATION, DESIGN OR ASME/ TECH SPEC RELATED ACTIVITIES.

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REACTOR COOLANT SYSTEM

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SASES l

3/4.4.5 SPECIFTC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific sita parameters, such as site boundary location and l metacrological conditions, were not c:nsidered in tais evaluation.

l The ACTICM statament persitting PCWER OPERATICN to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram 00$E EQUIVALENT I-131, but less than or equal to 4.0

. microcuries per gram DOSE EQUIVALENT I-131, accommodates possible f odine spiking '

- ";.ni.: i=

pheno,me,non

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r:Ty:i: ":1?=1 ; ;r:r dr;r n; b; ;;- '::it?: ' =' ' 0d by t.". :t M -

- Closing the main steen line isolation valves prevents the release of activity to the environs should a steen line rupture occur outside containment.

~

i The surveillance requirements piovide adequata assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

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. REACTOR COOLANT SYSTEM d.0 y $i!N F 3: ~ 1. ' '. f-k-..-J

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- b-3/4.4.5 SPECIFIC ACTIVITY h..,;.j rY,,,5 N... ' o.*'.' .%

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"' f h, I LIMITING CONDITION FOR OPERATION -

3.4.5 The specific activity of the' primary coolant shall be limitef to:

i a. Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT

I-131, and

b. Less than or equal to 100/l microcuries per gram.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and 4. -

)

ACTION:

a. In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of the primary coolant; e .

y td 1. Greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 but ,

'uj 3 9 g;, less than or equal to 4 microcurie per gramg:::r:ti:n ::,,

jyc~* ---t'rx: ':r x; i: ** h: r: ;r::'d:: th:1 th; ::: ictir; ::- t- ;

,5 - M ng i nder these circumstances does not exceed urs in S.! yj*,, - any consecu -month period.. With the cumulative i u,** g 3 operating time at mary coolant c activity greater

!$gg* than or equal to 0.2 mier er gram DOSE EQUIVALENT I-131

,a yg *****di"8 5 h*""' * "**

8""*"** '*"i"d' '"*"*"*

C u, 5

, and submit al report to the Come pursuant to t* 8 tl Sp lon 6.6.C within 30 days indicating mber of 0 e - 270 0' : Sti!" 250VO th': t- 'h ?r:T':itr -

ng% f; -i#i::ti:^. 3.C.* r: :t :;;lI;;tl:.

e i. a wa - - - - - " ' " " " " ' ' " ' " '--

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."g ** 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time int 5.5 more than 80 ve n a consecutive ~

a microcuries per

"'3J 12-month peri e tnan

, we in at least HOT SHUTDOWN with the main s Eh h ,

5g

.cs.h,8 f,::':ti:n ;;'.:: :1:::: u'th'- 12 h: r:.

' o usn

$ 1 E @ Greater than 100/l microcurios per gram, be in at least HOT e a 'a .c SHUTDOWN with the main steamline isolation valves closed within W *9 5 s,4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . .

. c. .,

b. In OPERATIONAL CONDITION 1, 2, 3, or 4, with the specific activity g5Si of the primary coolant greater than 0.2 microcurie per gram DOSE

?3 EQUIVALENT I-131 or greater than 100/l microcuries per gram, perform -

5 * ., 'i; the sampling and analysis' requirements of Item da of Table 4.4.5-1

3*. until the. specific activity of the primary coolant is restored to M b,.C

within the limit. 1 !;::':1 ":;;rt :h:1' 5: pr:;: :d ::: : t 'ited ',

';* u . ';; ti th: 01---!;;i;; ;.- .u .0 t; 0,;;;i'i;; tie.- 0. 0. 0. Thi; .;;;.t ;n;11

- - - contam m.. :-"1+< of the specific activity analv=== -! t;.. wime

- duration when the specif u- -

r,* coolant exceeded n ' ; . m . per gram DOSE EQUIVALENT I-131 toge m.. -: t' + h_a

'"^1?22' ; 222' t':::1 * ";=:t' LA SALLE - UNIT 2 3/4 4-14 Amendment No.11

1

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' -". '-' . '. J-LIMITING CONDITION FOR OPERATION (Contfriiledf: -

ACTION: (Continued)

c. In CPERATIONAL* CONDITION 1 or 2, with:

1. THERMAL POWER changed by more than 155 of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 8, or

~

2. The off-gas level, prior to the holdup line, increased by more <

than 25,000 microcuries per second in one hour during steady state operation at release rates less than 100,000 microcuries per second, or

3. The off gas level, prior to the holdup line, increased by more -

than 155 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during steady state operation at release rates greater than 100,000 microcuries per second,

! perform the sampling'and analysis requirements of Item 4b of Table 4.4.5-1 until the specific activity of the primary coolant is rd :- M..' ,".:..".-- .' ..':-

~

restored,to .>. within its limit.

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SURVEILLANCE REQUIREMENTS 4.4.5 The specific activity of the reactor coolant shall be demonstrated to l be within the limits by performance of the sampling and analysis program of l Table 4.4.5-1.

t

Notapplicabledurir$gtheStartupTestProgram.

LA SALLE - UNIT 2 3/4 4-15 ;

i e

_ . _ _ . _ _ _ _ - _ . . .- _ _ . - . . - . _. - - . . . _ . - , , . ,-m-,-.-.,- r,._-w., ,p-..v.,,-~~,-. .

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l ADMINISTRATIVE CONTROLS t. -

. m

)' ANNUAL REPORTS (c.c.s

'.'.dd 0.5tr '-??._;

u we* )f;; 0; t.'.i; ::;ti;;) 'flic // f e . f.'n c/c.4,s Cen m se l rep

4 a h n g wa'h i,E4e The results of specific activity analysis ih which the primary coolant exceeded the limits of Specific on 0.0." ;;d Z ;?;;t;) .

2.0.0 '"1" ;?::::) :- 3.4.5 'O ;?;;d a fol' owing inforinauon.

W 1' 5: f-d'W: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to ex-ceeding the Ifmit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiofodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concordration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

. e ., 1 z n .mu w,aivsu THIS DCCU:!IINT/D'AW!NG 1S FOR ADMiNISTRATv!5 RE. BINCE ONLV.

IT SHALL NOT 22 USED FOR iviAIN-TENANCE, OPERATION, DESIGN OR ASME/ TECH SPEC RELATED ACTIVITIES. ,

La& & -(L;t2 .

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3ASES 3/4.4.5 SPECIFIC ACTIVITY . , _._ . .

The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid and whole body doses resulting from a main steam ifne failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100. The values for the Ifmits on specific activity represent interia limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters, such as site boundary location and meteorological conditions, were not considered in this evaluation.

The ACTION statemet t perinitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2

) sicrocuries per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 .

nicrocuries per gram DOSE EQUIVALENT I-131, accommodates possible "-

todine spiking phenomenon which any occur following changes in THERMAL POWER. :-; tic f t.'.

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Closing the main steam line isolation valves prevents the release of activity to the environs should a steam line rupture occur outside containment.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

LA SALLE - UNIT 2 8 3/4 4-3

f ATTACHMENT B 4

SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a

.significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because: the change merely relaxes the reporting requirements for primary coolant iodine spiking and eliminates the 800 hour0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months / year cumulative run time limit (Operation with high iodine activity). The change does not alter the Technical Specification limits for primary coolant specific activity, nor does it change the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ;

shutdown requirement.

2) Create the possibility of a new or different kind of accident from any.

accident previously evaluated because: the iodine limit has no affect on ;

accident initiation.

3) Involve a significant reduction in the margin of safety because the change to relax the reporting requirements has no effect on the margin of

] safety, and the change to eliminate the 800 hour0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months / year limit for operation ;

1 with high iodine activity is justified based on improvements in nuclear j fuel which have made this limit unnecessary. I Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(e), the proposed change does not constitute a significant hazards consideration.

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