Text

Proposed Tech Specs Re Min Frequencies for Sampling Tests, Including Reactor Coolant
	ML19332F160
Person / Time
Site:	Fort Calhoun
Issue date:	12/01/1989
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML19332F156	List: ML19332F155; ML19332F158; ML19332F160;
References
	NUDOCS 8912130478
	Download: ML19332F160 (19)
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' l TABLE 3-4 !

MINIMUM FRE0VENCIES FOR SAMPLING TESTS i

Type of Measurcment Sample and Analysis [

and Analysis Frecuency l

1. Reactor Coolant (a) Power Operation (1) Gross Radioactivity 1 per 3 days !

(ope c.w3 H ..L. g M ** m s. * * ' " " $) s (2) Isotopic Analysis for (1) I per 14 days DOSE EQUIVALENT I-131

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(ii) I per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (l) whenever the radio- :

activity exceeds :

1.0 Ci/gm DOSE ,

EQUIVALENT I 131.

(iii) I sample between 2 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a thermal power change exceeding 15% ,

of the rated thermal power change exceeding 15% of the rated thermal power .

within a 1-hour

, period.

l (3) E Determination 1 per 6 months (2)

(4) Dissolved oxygen 1 per 3 days and chloride (b) Hot Standby (1) Gross Radioactivity 1 per 3 days (o pe ne.b n..t. r.) ( Gm m .m ist*Q Hot Shutdown (2) Isotopic Analysis for (i) I per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (l)

(,e p.e.c,3 H.J.3} DOSE EQUIVALENT I 131 whenever the radio-activity exceeds 1.0 C1/gm DOSE

EQUIVALENT I-131.

(ii) 1 sample between 2 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a thermal power change exceeding 15% of the rated thermal power within a 1-hour period.

(3) Dissolved oxygen 1 per 3 days and chloride Amendment No. /E, 67 3-18

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- TABLE 3 k (Continued)

MINIMUM FREQUENCIES FOR SAMPLING TEST

- 7ype of Measurement Sample and Analysis and An alys t s Frecuenev

1. F.eacter Coolant

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'(c) Cold Shutdown (1) Chloride 1 per =3 days -

( o pec.s g t%.le.64

[ (d) P,efueling Sbst.d**)* (1): Chloride 1 per 3 days N I C

(. c NEN M deale.E)(2) Boron Concentration 1 per 3 days (O i

f-he 2. S P.W Tank- Boron Concentration 1 per 31 days 4 b .

o ' 3. Concentrated Boric Beren Concentration 1 per 31 days j

.+ iAcid Tanks L. S!' Tanks Boron Concentration 1 per 11 days l

FL 5 . Spent Fuel Pool. Boron Concentration 1 per 31 days-f-

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t (1) Until the radioactivity of the reactor coclant is ' restored to 11 uCi/Em

~" DOSE EQUIVALDIT I-131.

(2) Sample to be te. ken after a minimum of 2 EFPD and 20 days of power cperation have elapsed since reactor was suberitical for L8 hours or icnger.

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- Amend..ent !!o. 23, 67, 66 3-19 7-W %

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l ATTACHMENT B I

i DESCRIPTION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATION Description of amendment request:

The proposed amendment is an administrative change to clarify the minimum frequencies for sampling requirements established in Table 3-4, Item 1, Reactor Coolant by adding Operating Mode numbers and assuring each of the operating modes is included. Presently, Table 3-4 of the Technical Specifications requires reactor coolant sampling and analysis during the following conditions: a: Power Operation, b: Hot Standby and Hot Shutdown, c: Cold Shutdown, and d: Refueling Operation. Refueling Operation, by Technical Specifications definition, refers only to actual fuel movement. Therefore, the wording is being changed to reflect the actual " Refueling Shutdown" mode terminology. Requirements generally observed during Refueling Shutdown are one sample for chloride and boron concentration per every three days; although a strict Technical Specification interpretation would, inappropriately, fail to require this except during actual movement of fuel.

Basis for No Significant Hazards Determination:

The proposed change does not involve a significant hazards consideration because the operation of Fort Calhoun Station in accordance with this amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. This administrative change clarifies wording in Table 3-4, Item 1, by adding Operating Mode numbers and assuring each of the operating modes is included.

2. Create the possibility of a new or different kind of accident from any previously analyzed. It has been determined that a new or different kind of accident will not be possible due to this change. This change is administrative and clarifies Table 3-4, Item 1, thus assuring nperation will be as specified in the Technical Specifications.

3. Involve a significant reduction in a margin of safety. The change is administrative, will not eliminate any sampling requirements, and clarifies the requirement to sample during the Refueling Shutdown condition.

Therefore, based on the above considerations, Omaha Public Power District has determined that this change does not involve a significant hazards ,

I ATTACHMENT B Page 1 of 1 ;

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l BEFORE THE UNITED STATES

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NUCLEAR REGULATORY COMMISSION j

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' Omaha Public Power District ) l (fort Calhoun Station- Docket No. 50-285 ,

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Unit No. 1) )~

APPLICATION FOR AMENDMENT-0F OPERATING LICENSE n '

l Pursuant, to Section 50.90 of the regulations of the U. S. Nuclear

'j Regulatory Commission ("the Commission"), Omaha Public Power District, i

holder of facility Operating License No. DPR-40, herewith requests that Section 3.2, Table 3 4 of the Technical Specifications set forth in t

Appendix A to that License be amended to clarify the Minimum Fr_ quencies '

for Sampling Tests, Reactor Coolant, Sample and Analysis frequency.

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' The proposed changes in Technical Specifications are discussed in the attachment to this Application. A discussion, Justification and no

Significant Hazards Consideration Analysis, which demonstrates that the !

proposed' changes do not involve significant hazards considerations, is appended in Attachment B.

The proposed changes-in specifications would not authorize any change in the types or any increase in the amounts of e j ffluents or a change in the authorized power level of the facility. '

WHEREFORE, Applicant respectfully requests that Section 3.2 of L

Appendix A to Facility Operating License No. DPR-40 be amended in the form attached hereto as Attachment A.

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2-t A copy of this Application, including its attachments, has been sub- ,

mitted to the Director Nebraska State Division of Radiological Health, as required by 10 CFR 50.91.

OMAHA PUBLIC POWER DISTRICT ,

By , - - -

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,7, DiNsionManager Nuclear Operations Subscribed and sworn to before me this day of December, 1989.

annanasusteame .a asamLevANs m S/b A n_'7h) k m s S "' * * #~ "

Notary Public i

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TABLE 3 4

., , l MINIMUM FRE0VENCIES FOR SAMPLING TESTS !

1 Type of Measurement Sample and Analysis !

and Analysis Frecuency '

1. Reactor' Cool ant ]

(a) Power Operation (1) Gross Radioactivity 1 per 3 days j

' (op.c.w3 M..t g M*= m s * *a * *m *)

(2) Isotopic Analysis for (i) I per 14 days DOSE EQUIVALENT I-131 (ii) I per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (l) whenever the radio-activity exceeds 1.0 Ci/gm DOSE EQUIVALENT l 131.

(iii) I sample between -

2 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following -

a thermal power ,

change exceeding 15f; of the rated thermal power change exceeding 15Y. of the rated thermal power within a 1-hour

._ period. ,

(3) EDetermination 1 per 6 months (2) ;

(4) Dissolved oxygen 1 per 3 days and chloride (b)' Hot Standby (1) Gross Radioactivity 1 per 3 days (ooenu.h8.1.Q C G.- m . ct <0 Hot Shutdown (2) Isotopic Analysis for (i) I per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (I)

(,ep.<.c.3 H.J.3) DOSE EQUIVALENT I-131 whenever the radio-activity exceeds 1.0 C1/gm DOSE EQUIVALENT I 131.

(ii) I sample between 2-8

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hours following a thermal power change exceeding IST. of the rated thermal power within a 1-hour period.

(3) Dissolved oxygen I per 3 days and chloride Amendment No. JE, 67 3-18

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TABLE 3 k (Continued)

MINDM4 FRECUENCIES ' FOR SAMPLING TEST

?,rpe of Measurement Sanple ar.d Analysis i

and Analysis Frecuency

1. Res.ctor Coolant H (Continued)

(c) Cold Shutdevn (1) Chloride 1 per 3 days

.( 0eeras s Hade.'0 j (d) Refueling $ bad *** (1) Chloride - 1 per 3 days U)

C'WP**Wia>

C H *de(2)5Boron

) Concentratien 1~per 3 days D) b

2. S RW Tank Boron Concentration 1 per 31 days ~t-i

3. Concentrated Boric Boron Concentration 1 per 21 days ,

' Acid Tanks L. S: Tanks. Boron Cencentration 1 per 31 days

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5. Spent Fuel. Pool Boron Concentration 1 per 31 days (1).- 'Until the radioactivity of the reactor coolant is restored to 5,2 :01/E

" DOSE EQUIVALENT I-131.

(2) Sample to be taken after a mini =un of 2 ETFD and 20 days cf power Opera:1:n

.have elapsed since reactor was suberitical for kB hours or longer.

(3) 3 .cen - an1 d I.,i.I 5 ~ pl'6%3 / A. % l9 sen ,,, ,, w .T c , 3 .. .t n ud e w . t h e - f. eve . b e, s b .e sw a%-Imed*el.

Ament.ent tio. 23, 67, c6 3-19

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ATTACHMENT B :

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DESCRIPTION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATION Description of amendment request:

The proposed amendment is an administrative change to clarify the minimum frequencies for sampling requirements established in Table 3-4, Item 1, Reactor Coolant by adding Operating Mode numbers and assuring each of the operating modes is includsd. Presently, Table 3-4 of the Technical Specifications requires reactor coolant sampling and analysis during the-following conditions: a: Power Operation, b: Hot Standby and Hot Shutdown, c: Cold Shutdown, and d: Refueling Operation. Refueling Operation, by Technical Specifications definition, refers only to actual fuel movement. Therefore, the wording is being changed to reflect the actual " Refueling Shutdown" mode terminology. Requirements generally observed during Refueling Shutdown are one sample for chloride and boron concentration per every three days; although a strict Technical Specification interpretation would, inappropriately, fail to require this except during actual movement of fuel.

Basis for No Significant Hazards Determination:

The proposed change does not involve a significant hazards consideration because the operation of Fort Calhoun Station in accordance with this amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. This administrative change clarifies wording in Table 3-4 Item 1, by adding Operating Mode numbers and assuring each of the operating modes is included.

2. Create the possibility of a new or different kind of accident from any previously analyzed. It has been determined that a new or different kind of accident will not be possible due to this change. This change is administrative and clarifies Table 3-4, Item 1, thus assuring i operation will be as specified in the Technical Specifications.

l 3. Involve a significant reduction in a margin of safety. The change is

) administrative, will not eliminate any sampling requirements, and -

clarifies the requirement to sample during the Refueling Shutdown condition.

Therefore, based on the above considerations, Omaha Public Power District has determined that this change does not involve a significant hazards ATTACHMENT B Page 1 of 1

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b BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )

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[ 0maha Public Power District )

(Fort Calhoun Station Docket No. 50-285

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, Unit No.;l) )-

T APPLICATION FOR AMENDMENT OF OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U. S. Nuclear Regulatory Commission ("the Commission"), Omaha Public Power District, p

holder of Facility Operating License No. OPR 40, herewith requests that Section 3.2, Table-3 4 of the Technical Specifications set forth in

' Appendix A to that License be amended to clarify the Minimum Frequencies for Sampling Tests, Reactor Coolant, Sample and Analysis frequency.

The proposed changes in Technical' Specifications are ' discussed in the

-attachment to this Application. A discussion, Justification and no

'Significant Hazards Consideration Analysis, which demonstrates that the !

. proposed changes do not involve significant hazards considerations, is

.. appended in Attachment B. The proposed changes in specifications would not authorize any change in the types or any increase in the amounts of effluents or a change in the authorized power level of the facility.

WHEREFORE, Applicant respectfully requests that Section 3.2 of Appendix A to facility Operating License No. OPR 40 be amended in the form

= attached hereto as Attachment A.

j

2-A copy of this Application, including its attachments, has been sub-mitted to the Director - Nebraska State Division of Radiological Health, as required by 10 CFR 50.91.

OMAHA PUBLIC POWER DISTRICT By 27 u ir<

DiMsion Manager Nuclear Operations l

Subscribed and sworn to before me this day of December, 1989. !

eman osmar-enn a no..w hgh) , i pg S MaunL wAns Notary Public i

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, TABLE 3-4 MINIMUM FRE00ENCIES FOR SAMPLING TESTS Type of Keasurement Sample and Analysis and Analysis Frecuency

1. Reactor Coolant (a) Power Operation (1) Gross Radioactivity 1 per 3 days (o p.c.c.,3 H.A.g (6~-i* *'""O (2) Isotopic Analysis for (1) I per 14 days DOSE EQUIVALENT I-131 (ii) I per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (l) whenever the radio-activity exceeds 1.0 Ci/gm DOSE EQUIVALENT I-131.

(iii) 1 sample between 2-8 hours following a thermal power change exceeding 15%

of the rated thermal power change exceeding 157 of the rated thermal power within a 1-hour period.

(3) 5 Determination 1 per 6 months (2)

(4) Dissolved oxygen 1 per 3 days and chloride l (b) Hot Standby (1) Gross Radioactivity 1 per 3 days I

(o pe nc.b s.A Q C G.- m .e istm)

Hot Shutdown (2) Isotopic Analysis for (1) I per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (l)

(,o p.e.c.3 H.4 3) DOSE EQUIVALENT I-131 whenever the radio- ,

activity exceeds '

I 1.0 Ci/gm DOSE l -

EQUIVALENT I-131, i

(ii) 1 sample between 2-8 hours following a thermal power change exceeding 15Y. of the t rated thermal power-within a 1-hour period.

(3) Dissolved oxygen 1 per 3 days and chloride Amendment No. 3 , 67 3-18

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, TABLE 3-k (Continued) [ .

I c' ' MIND 4UM FREQUENCIES FOR SAMPLING TEST !

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?/pe of Measurement Sample. and Analysis i t

and Analysis Frecuency i F

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1. Reacter Coelant

> (Continued) !

(c)~ Cold Shutdevn (1) Chloride 1 per 3 days -

( opecas a t4.de.'

-(d) Refueling $brf.d*0. ** (1) Chloride 1 per 3 days N C

l- (u'p."W'W..f M .de E ) (2) Boron Concentratien 1 per 3 de.ys b i

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2. S RW Tank. Beren Concentration 1 per 31 dtys (i,

3. Cencentrated Boric Beren Concentration 1 per 31 days Acid Tanks !L i ~t t

1 S: Tanks Boron Concentration 1 per 31 dcys ;I

5. Spent Fuel Pool Boron Concentration 1 per 31 days r

(1) Until the radioactivity of the reactor coclant is restored to f,I uC1/ p *

" DOSE EQUIVALETT I-131.

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(2) Sample to .be taken af ter a minimum of 2 ETFD and 20 days of power cperatien !

. have elapsed since reactor was suberitical for LB hour:: or icnSer. -

(3) 3.een nl c.U.vid 5 mp 11%3 / A.mn 9 3.a y , .t g o ,.. J i uA.( o=.c.ve_L 3b .w .W-1...i.J.. i 4

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ATTACHMENT B l

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9 DESCRIPTION, JUSTIFICATION AND

f. NO SIGNIFICANT HAZARDS CONSIDERATION Description of amendment request:

The proposed amendment is an administrative change to clarify the minimum frequencies for sampling requirements established in Table 3-4, Item 1 Reactor Coolant by adding Operating Mode numbers and assuring each of the operating modes is included. Presently, Table 3 4 of the Technical Specifications requires reactor coolant sampling and analysis during the following conditions: a: Power Operation, b: Hot Standby and Hot Shutdown, c: Cold Shutdown, and d: Refueling Operation. Refueling Operation, by Technical Specifications definition, refers only to actual fuel movement. Therefore, the wording is being changed to reflect the actual ' Refueling Shutdown" mode terminology. Requirements generally observed during Refueling Shutdown are one sample for chloride and boron concentration per every three days; although a strict Technical Specification interpretation would, inappropriately, fail to require this except during actual movement of fuel.

Basis for No Significant Hazards Determination:

The proposed change does not involve a significant hazards consideration because the operation of Fort Calhoun Station in accordance with this amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. This administrative change clarifies wording in Table 3 4, Item 1, by adding Operating Mode numbers and assuring each of the operating modes is included.

2. Create the possibility of a new or different kind of accident from any previously analyzed. It has been determined that a new or different kind of accident will not be possible due to this change. This change is administrative and clarifies Table 3-4, Item 1, thus assuring !

operation will be as specified in the Technical Specifications.

3. Involve a significant reduction in a margin of safety. The change is administrative, will not eliminate any sampling requirements, and clarifies the requirement to sample during the Refueling Shutdown condition. !

Therefore, based on the above considerations, Omaha Public Power District has determined that this change does not involve a significant hazards

(

l l ATTACHMENT B l_ Page 1 of 1

,

ML19332F160

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