ML20214P543

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Proposed Tech Specs Changing Expression of Specific Activity Level in RCS from Activity Per Unit Mass to Activity Per Unit Vol
ML20214P543
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 05/22/1987
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214P522 List:
References
TAC-R00132, TAC-R00133, TAC-R132, TAC-R133, NUDOCS 8706030428
Download: ML20214P543 (14)


Text

. .

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CilANCES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-81-24)

LIST OF AFFECTED PAGES Unit 1 3/4 4-19 3/4 4-20 3/4 4-21 3/4 4-22 Unit 2 3/4 4-24 3/4 4-25 3/4 4-26 3/4 4-21 070603042() 070022 PDit ADOCK 05000327 p P Dit

1 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

Less than or equal to 1.0 microcuries/ gree DOSE EQUIVALENT I-131, and l L m,);,'j,p,,

b. Less than or equal to 100/E microcuries/geen. ,

l APPLICA8ILITY: MODES 1, 2, 3, 4 and 5 #'

ACTION:

MODES 1, 2 and 3* .

rn/I/e'/e'/ee .

a. With the specific a vity of the primary coolant greater than 1.0 microcuries/geam DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, l operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that the cumulative

- operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 month period. With the total cumulative operatin time at a primary coolant specific activity greater than 1.0 micro g fy,yfy,yf,. curieggeamDOSEEQUIVALENTI-131 exceeding 500hoursinanyconsecu-tive six month period, prepare and submit a Special Report to the l Commission pursuant to Specification 6.9.2 within 30 days indicating the number of hours above this limit. The provisions of Specifica-1icable, 4

tion 3.0.4 are not pniapp,//oWfee b.

With the specifigfactivity of the primary coolant greater than 1.0 microcuries/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown l on Figure 3.4-1, be in at least HOT STANDBY with T within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, avg less than 500*F c.

With the specific activity of the primary coolant greater than 100/E microcuries/geen, be in at least HOT STANDBY with T within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. . avg less than 500'F l "With T,yg greater than or equal 500*F.

I SEQUOYAH - UNIT 1 3/4 4-19

REACTOR COOLANT SYSTEM ..

ACTION: (Continued)

MODES 1, 2, 3, 4 and 5 g/,py

a. With the specific tivity of the primary coolant greater than _

l.0 microcuries/ gram DOSE EQUIVALENT I-131 or greater than 100/E

  1. //87'.M' 'microcuries].

/

gees,4.4-4 item 4a of Table perform the specific until the sampling and analysis activity requirements of of the primary coolant is restored to within its limits. A SPECIAL REPORT shall be prepared and submitted to the Commission pursuant to Specifica- R40 tion 6.9.2 within 30 days. This report shall contain the results of the specific activity analyses together with the following information:

1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded,
2. Fuel burnup by core region,
3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded,
4. History of de gassing operations, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, and
5. The time duration when the specific activity of the primary ("~-

coolant exceeded 1.0 microcuries/geen DOSE EQUIVALENT I-131. l. f

/HiUt%'/w SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

November 23, 1984 y 3/4 4-20 Amendment No. 36 SEQUOYAH - UNIT 1

- - e7 sg w TABLE 4.4-4  ;

5 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE

. u 9 AND ANALYSIS PROGRAM

', M N

c- TYPE OF MEASUREMENT SAMPLE AND ANALYSIS g AND ANALYSIS lREQUENCY MODES IN WHICH SAMPLE AND ANALYSIS REQUIRED

1. Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> " '

1, 2, 3, 4

2. Isotopic Analysis for DOSE EQUIVA- \

a) 1 per 14 days 1 LENT I-131 Concentration A rMove ,,N ,, orsd' ' C) ~ fc b00.J *), a t

3. Radiochemica) for E Determination 1 per 6 months * -

1

-4. -hetcpic Analysis for lediee-I..siud his I -131, I - 133, end I 135-

63) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, l # ,2',3

,4# ,5#

m whenever the specific activity exceeds 1.0 2 pCi/ge h DOSE

  1. 'p,y,;,,. #

u g,

EQUIVALENT I-131 or 100/E ~pCi/ gees, and

,,p,y,y,,

e y) One sample between 1, 2, S 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following ,

a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.

ntil the specific activity of the primary coolant system is restored within its limits.

Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

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0 20 30 40 50 00 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percentof RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0gCi/pam Dose Equivalent 1-131 l 9

( mi//i/ik- . .

SEQUOYAH - UNIT 1 3/4 4-22

REACTOR COOLANT SYSTEM

(

3/4.4.8 SPECIFIC ACTIVITY m LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

3.

Less than or equal to 1.0 microcurie per gree DOSE EQUIVALENT. I-131, and . t ,,y 7, ,, l

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

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ( mi}/s*/s?&

ACTION:

N00ES 1, 2 and 3*: g,)f' fff pe,

a. With the soecific ctivity of the crimary coolant greater than 1.0 microcurie per'-geee DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on l Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that the cumulative operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 month period. With the f total cumulative coersting time at a primary coolant specific activ- '

fty greater than 1.0 microcurie per tes# 00SE EQUlvALENT I-13 & /tf///i//M(+

exceeding 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6 month period, prepare and sucmit a Special Report to the Commission pursuant to Specifi-cation 6.9.2 within 30 days indicating the number of hours above tnis limit. The provisions of Specification 3.0.4 are not applicable.

mt/loliYor

b. Withthespecific[activityoftheprimarycoolantgreaterthan

'1.0 microcurie pel* geom-DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line l shown than on Figure 500*F within3.4-1, be in at least HOT STAN08Y with T'*9 less 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

's, c. With the specifihmi///XY&

etivity of the primary coolant greater than 100/E microcurie per5 gren, less than hours.be in at least HOT STAN08Y with T,y9 l.

500*F within I

i Eith T, g greater than or equal to 500'F.

S I

SEQUOYAH - UNIT 2 3/4 4-24 r

9

,7,,, , _ - , - - - + - - -r- ---e- 4 "' '" - " "

4

-. REACTOR COOLANT SYSTEM

\

ACTION: (Continued)

MODES 1, 2, 3, 4 and 5: fju//f///w .

a. With the specific ctivity of the primary coolant greater than 1.0 _ microcurie pe geam DOS EQUIVALENT I-131 or greater than 100/E microcuries per geam, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits. A SPECIAL REPORT shall be prepared and submitted to the Commission pursuant R28 to Specification 6.9.2 within 30 days. This report shall contain the results of the specific activity analyses together with t.he following information: '
l. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, ' -
2. Fuel burnup by core region, .
3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded,
4. History of de gassing operations, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

. - .. prior to the first sample in which the limit was exceeded, and

5. The time duration when the specific activity of the primary coolant exceeded 1.0 microcurie per gr-as DOSE EQUIVALENT I-131.

/yit///ltl&

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

_/

l November 23, 1984 l SEQUOYAH - UNIT 2 3/4 4-25 Amendment No. 28 1

1

l TABLE 4.4-4 E PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM I

c TYPE Of MEASUREMENT SAMPLE AND ANALYSIS HODES IN WillCil SAMPLE AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED h

1. Gross Activity Determination At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> *
  • 1, 2, 3, 4

\

2. Isotopic An.il,3is for DOSE EQUIVA- diper14 days 1 LENT l-131 Cm. centration f fyfove J)
  • g,f/
  • e ) ' d [//M *4.) *
3. Radiochemic.it for E Determination 1 per 6 mont hs* 1

- I su tug i c A ... i y s i a fer Iedi.m fp) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, l,2,3,4,5 ineltrdk.9 ' .l, I-133, a;.d I 135 whenever the specific activit exceeds 1.0 pCi DOSE gg x

EQUIVALE_NT I-131, y,)f,'f,y,,

[ or 100/E pCi/ m and 4

cn

()f) One sample between 1, 2, 3 --)

2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following d TilERMAL POWER change exceeding 15 percent of the RATED INERMAL POWER within a one hour period.

Until the specific activity of the primary coolant system is restored within its limits.

  • Sample to be taken af ter a minimum of 2 ElPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

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0 40 50 60 70 80 90 100 20 30 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Permnt of RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0pCi/ gram Dose Equivalent 1-131 L mtlN//ler u

SEQUOYAH - UNIT 2 3/4 4-27

)

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. . . . _.. ._ . . _ _ . . . = _ _ _ .. _ _ _ . . _ . _ _ _ _ _

ENCLOSURE 2 4

i PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-24)

DESCRIPTION AND JUSTIFICATION FOR THE PROPOSED AMENDMENT TO LIMITING CONDITION FOR OPERATION (LCO) 3.4.8 i

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, , ENCLOSURE 2 Description of Change The proposed change would affect the following three modifications and amendments to the Limiting Condition for Operation (LCO) 3.4.8, Reactor Coolant System (RCS) specific activity:

Change references of specific activity in RCS to units of microcuries per milliliter (mci /ml) from microcuries per gram (mci /gm).

Change references to various isotopes of iodine cited in item 4 of i

table 4.4-4 to DOSE EQUIVALENT I-131 Concentration.

Add a concise definition of gross activity and an explanation of how gross activity is evaluated.

i Reason for Change The proposed changes are made to provide for the following:

The use of terminology that is commonly used in the industry.

Consistent evaluation of specific activity in the RCS.

A clearly understood meaning of the term " gross activity" and the manner in which the gross activity of the RCS is evaluated.

Justification for Change The justification for the proposed changes to the technical specifications is j as follows:

- Units of Specific Activity All analyses of specific activity are performed on a basis of specific activity per unit volume, not on a per unit mass basis.

Also, it is common practice within the industry to generally express such analyses in terms of specific activity per unit volume. Thus, the proposed technical specification change would provide for the usage and terminology used in the Sequoyah technical specifications to be consistent with general industry usage and would reflect the actual basis of the, specific activity analyses performed.

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, The technical specifications currently express specific activity in terms of mci /gm. The proposed change would express specific activity in terms of mci /ml. At 4 degrees C, one gram of water occupies a volume of one milliliter. The specific activity analyses are typically performed at a temperature of about 24 degrees C. The change in volume of one gram of water in going from 4 degrees C to 25 degrees C is negligible; for all practical purposes, the two volumes are the same. Thus, expressing specific activity in terms of mC1/ml will not introduce any appreciable error in the analyses identified in LCO 3.4.8 and the associated Surveillance Requirements (SRs).

DOSE EQUIVALENT I-131 Concentration Table 4.4-4, " Primary Coolant Specific Activity Sample and Analysis Program," identifies the types of measurements and analyses required by SR 4.4.8 to satisfy LCO 3.4.8. Item 4 of table 4.4-4 currently identifies several isotopes of iodine that the required analysis is to check for. The proposed technical specification change would amend the description of the type of measurement and analysis of item 4 to identify only a DOSE EQUIVALENT I-131 Concentration, rather than specific isotype of iodine. This proposed change would provide for the description of the type of measurement and analysis of item 4 for item 2 and that generally used in the industry.

- Definition of Gross Activity Item 1 of table 4.4-4 currently identifies that a gross activity determination be performed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while the unit is in modes 1, 2, 3, or 4. There is, however, no definition given as to what constitutes the gross activity of the primary coolant. The proposed technical specification change would add a concise definition of what constitutes gross activity in the primary coolant, how quickly after drawing a sample the analysis must be performed, and how the analysis is to be extrapolated to the activity level in the RCS. The proposed addition of the definition of gross activity will provide for a uniform and consistent evaluation of RCS-gross activity that is in keeping with the general methodology used by the industry.

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ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANCES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-24)

DETERMINATION OF NO SIGNIFICANT HAZARDS EVALUATION FOR THE PROPOSED AMENDMENT TO LIMITING CONDITION FOR OPERATION (LCO) 3.4.8

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. ENCLOSURE 3 SIGNIFICANT HAZARDS EVALUATION

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed technical specification change would make three amendments to the Limiting condition for Operation (LCO) 3.4.8 and the associated Surveillance Requirements (SRs). First, references to specific activity in the reactor coolant system (RCS) would be made in terms of a unit volume rather than a unit mass; microcuries per milliliter (mci /ml) would replace references to microcuries per gram (mci /gm). Second, the results of isotopic analysis for lodine (I) would express activity in terms of DOSE EQUIVALENT I-131 rather than activity in terms of various isotopes of iodine. Third, a concise definition of gross activity is provided. This proposed amendment does not involve a change in plant hardwara, plant operating setpoints or limits, or plant operating procedures. Thus, the proposed technical specification change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

No. As previously stated, the proposed amendment does not involve a change in plant hardware, plant operating setpoints or limits, or plant operating procedures. Thus, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed amendment involve a significant reduction in the margin of safety?

No. Again, as previously stated, the proposed amendment does not involve a change in plant hardware, plant operating setpoints or limits, or plant operating procedures. The proposed amendment does provide for both the use of terminology that is common within the industry and a concise definition of gross activity, thereby reducing the potential for misinterpretation of the affected technical specification. Thus, the proposed amendment involves no reduction in the margin of safety but rather provides for an increase in the margin of safety.