ML19344A936

Amend 3 to License DPR-77,changing Surveillance Requirements for Taking Radioactive Liquid & Gaseous Samples

ML19344A936
Person / Time
Site:	Sequoyah
Issue date:	07/01/1980
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19344A935	List: ML19344A934 ML19344A936 ML19344A938
References
NUDOCS 8008250057
Download: ML19344A936 (22)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION a

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 LICENSE NO. OPR-77 AMEN 0 MENT (J. 3 1.

The Nuclear Regulatory Comission (the Comission) having found that:

A.

The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) license, DPR-77, filed by the Tennessee Valley Authority (licensee), dated March 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by j

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be con-ducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon l

defense and security or to the health and safety of the public, and l

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have j

been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-77 is hereby amended to read as follows:

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e o o 82 5005.7

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. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 3, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.

A.

This amended license is ' effective as of the date of issuance.

FOR THE LEAR REGULATORY COMMISSION ll V6'i $ V

, q, A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing

Attachment:

Appendix A Technical Specification changes fuly1,NN I

i i

ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. DPR-77 "

DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3/4 3-70 3/4 3-70A (added) 3/4 3-71 3/4 3-71A (added) 3/4 3-72A (added) 3/4 3-75 3/4 3-76 3/4 3-77 3/4 11-2 3/4 11-2A (added) 3/4 11-4 3/4 11-11 8-1 SEQUOYAH - UNIT 1 i

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INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm /

trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all times.

ACTION:

With a radioactive liquid effluent monitoring instrumentation channel a.

alarm /t*1p setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b.

With less than the minimum number of radioactive liquid effluent t

monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3.3-12.

The provisions of Specifications 3.0.3 and 3.0.4 are not appifcable.

c.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

l l

SEQUOYAH - UNIT 1 3/4 3-69 i

' " ' ~ ' ' "

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TABLE 3.3-12 E

gg RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION s

x MINIMUM c:

CHANNELS

'5 INSTRUMENT l

-4 OPERABLE ACTION 1.

GROSS RADIDACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE t

a.

Liquid Radwaste Effluent Line 1

30 i

b.

Steam Generator 810wdown Effluent Line 1

31 l

c.

Condensate Demineralizer Effluent Line 1

30 u,

2.

GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC 3:

TERMINATION OF RELEASE us j;

a.

Essential Raw Cooling Water Effluent Line 1

32 1

b.

Turbine Building Sump Effluent Line 1

32 3.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

33 b.

Condensate Demineralizer Effluent Line 1

33 j[

c.

Steam Generator Slowdown Effluent Line 1

33 h

d.

Cooling Tower 810wndown Effluent Line 1

33 y

4.

TANK LEVEL INDICATING DEVICES i

El a.

Condensate Storage Tank 1

34 b.

Steam Generator Layup Tank" 1

34 i

" Required when connected to the secondary system

'l '

s TABLE 3.3-12 (Continued) m RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION s

x MINIMUM E

CHANNELS q

INSTRUMENT OPERABLE ACTION

~

5.

CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR a

a.

Condensate Demineralizer Regenerant Effluent Line 1

35 I.

N.

Ya>

i t

a g

9n I

w 1

-mum TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 30 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:

I a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 31 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for grg9s radioactivity gamma at a limit of detection of at least 10 microcuries/ gram:

a.

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.

ACTION 32 -

With the

.mber of channels OPERABLE less than required by the Minimum waannels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross radioactivity gamma at a limit of detection of at 7

least 10 microcuries/ml.

l ACTION 33 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump curves may be used to estimate flow.

ACTION 34 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid I

level is estimated during all liquid additions to the tank.

SEQUOYAH - UNIT 1 3/4 3-71 Amendment No. 3

l-TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 35 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Specification 3.11.1.1, footnote g.

l SEQUOYAH - UNIT 1 3/4 3-71A Amendment No. 3

TABLE 4.3-8 wE RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL E INSTRUMENT CHECK CHECK CALIBRATION TEST

--4 H

1.

GROSS BETA OR GAMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluents Line D

P R(3)

Q(1)

b. Steam Generator Blowdown Effluent Line D

M R(3)

Q(1)

c. Condensate Demineralizer Effluent Line D

M R(3)

Q(1)

R I

2.

GROSS BETA OR GM9MA RADI0 ACTIVITY MONITORS I

Y PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC U

TERMINATION OF RELEASE I

Essential Raw Cooling Water Effluent Line D

M R(3)

Q(2) a.

b.

Turbine Building Sump Effluent Line D

M R(3)

Q(2) l i

3.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line D(4)

N.A.

R Q

i 2

b.

Steam Generator Blowdown Effluent Line 0(4)

N.A.

R Q

c.

Condensate Deminineralizer Effluent Line D(4)

N.A.

R Q

1 d.

Cooling Tower Blowdown Effluent Line D(4)

N.A.

R Q

4.

TANK LEVEL INDICATING DEVICES a.

Condensate Storage Tank D*

N.A.

R Q

b.

Steam Generator Layup Tank D*

N.A.

R N.A.

I

g TABLE 4.3-8 (Continued) o E

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS N

E CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL Q

INSTRUMENT CHECK CHECK CALIBRATION TEST

-l S.

CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR a.

Condensate Deelneralizer Regenerant Effluent Line P

N.A.

R N.A.

l N*

l Gb 9:

1 an

.O N

)

i

1. !

TABLE 3.3-13 v.E Ej RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION T-x MINIMUM CHANNELS l

j[

INSTRUMENT OPERABLE APPLICABILITY ACTION 4

1.

WASTE GAS DISPOSAL SYSTEM a.

Noble Gas Activity Monitor 1

40 b.

Effluent System Flow Rate Measuring Device 1

41 2.

WASTE GAS DISPOSAL SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.

Hydrogen and Oxygen Monitors 2

43 Id 3.

CONDENSER VACUUM EXHAUST SYSTEM

=

y a.

Noble Gas Activity Monitor 1

42 34 b.

Flow Rate Monitor 1

41 4.

SHIELD BUILDING EXHAUST SYSTEM a.

Noble Gas Activity Monitor 1

42 b.

Iodine Sampler 1

44 c.

Particulate Sampler 1

44 d.

Flow Rate lionitor 1

41 l

e.

Sampler Flow Rate Monitor i

41 ki a

h i

i.

TABLE 3.3-13 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Y

x MINIMUM CHANNELS e

INSTRUMENT OPERABLE APPLICA81LITY ACTION g

5.

~ AUXILIARY BUILDING VENTILATION

~

SYSTEM 42 a.

Noble Gas Activity Monitor 1

44 b.

Iodine Sampler 1

c.

Particulate Sampler I

44 41 d.

Flow Rate Monitor 1

41 e.

Sampler Flow Rate Monitor 1

6.

SERVICE BUILDING VENTILATION SYSTEM a.

Noble Gas Activity Monitor 1

42 41 b.

Flow Rate Monitor 1

w h

9 3n F.

N

-(.

2 TABLE 3.3-13 (Continued)

TABLE NOTATION I

At all times.

During waste gas disposal system operation.

• • • During shield building exhaust system operation.

ACTION 40 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 41 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 42 -

With the number of channals OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 43 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE raquirement, operation of this waste gas disposal system may continue for up to 7 days provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

With the hydrogen and oxygen monitors inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 44 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

SEQUOYAH - UNIT 1 3/4 3-77 Amendment No. 3

~

g; TABLE 4.3-9 x2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

)

$E e

c_

CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE Il INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 1.

WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor P

P R(3)

Q(1)

b. Flow Rate Monitor D

N.A.

R Q

2.

WASTE GAS DISPOSAL, SYSTEM EXPLOSIVE GAS MONITORING SYSTEM

a. Hydrogen Monitor D

N.A.

Q(4)

M

b. Oxygen Monitor D

N.A.

Q(5)

M I

((

3.

CONDENSER VACUUM EXHAUST SYSTEM b$

'a. Noble Gas Activity Monitor D

M R(3)

Q(2) j

b. Flow Rate Monitor D

N.A.

R Q

4.

SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

b. Iodine Sampler W

N.A.

N.A.

N.A.

c. Particulate Sampler W

N.A.

N.A.

N.A.

d. Flow Rate Monitor D

4.A.

R Q

)

e. Sampler Flow Rate Monitor D

N.A.

R Q

i 1

I

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved gr entrained noble gases, the concentration shall be limited to 2 x 10 microcuries/m1 total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall 5e determined prior to release by sampling and analysis in accordance alth Table 4.11-1.

The results of pre-release analyses shall be used with the calculational methods in the 00CM to assure that the concentration at the point of release is maintained within the limits of Specification 3.11.1.1.

4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accorda3cp uitt. Table 4.11-1.

The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Specification 3.11.1.1.

4.11.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4.11-1.

The results of the analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

(

SEQUOYAH - UNIT 1 3/4 11-1 i

,1 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Liquid Release Sampling Analysis Type of Activity Detection {LLD)

Type Frequency Frequency Analysis (pCi/ml)

A. Batch Waste P

P

~7

. Release Each Batch Each Batch Principa 5x10 Emitters) Gamma d

Tanks

1. Waste Con-densate

-6 Tanks (3)

I-131 1x10

-5

2. Cask Decon-P M

Dissolved and 1x10 tamination One Batch /M Entrained Gases Tank (Gamma emitters)

3. Laundry Tanks (2)

-5 P

M H-3 1x10 b

4. Chemical Each Batch Composite Drain Tank Gross Alpha 1x10,

5. Monitor Tank

-6

6. Distillate P-32 1x10 Tanks (2)

-8 P

Q Sr-89, Sr-90 5x10 b

7. Condensate Each Batch Composite Demineralizer Fe-55 1x10 "

l Waste i

Evcorator P, lowdown Tank (1)

~7 B. Continuous' D

W Principa} Gamma 5x10 c

Releases Grab Sample Composite Emitters

1. Steam i

-6 Generator I-131 1x10 Blowdown

-5 M

M Dissolved and 1x10 2.

Turbiae Grab Sample Entrained Gases Building (Gamma Emitters)

""P

-5 D

M H-3 1x10 c

Grab Sample Composite

_y Gross Alpha 1x10

-6 P-32 1x10

-8 0

Q Sr-89, Sr-90 5x10 C

Grab Sample Composite

-6 Fe-55 1x10 SEQUOYAH - UNIT 1 3/4 11-2 Amendment No. 3

TABLE 4.11-1 (Continued)

RADIOACTIVE LIQUID WA5TE SAMPLING AND ANALYSIS PROGRAM Minimum Ltwer Limit of Liquid Release Sampling Analysis Type of Act.ivity Detection (LLD)

Type Frequency Frequency Analysis

(,pci/al)

~7 C. Periodic W

Principa} Gamma 5x10 Continuoys Continuous 9 Composite Emitters c

Releases

-6

1. Non-Reclaim-I-131 1x10 able Waste

-5 Tank M9 M

Dissolved and 1x10 Grab Sample Entraired Gases (Gamma Emitters)

' 2. High Crud

-5 Tanks (2)

M H-3 1x10 Continuous 9 Compositec Gross Alpha 1x10 '

-6 P-32 1x10

~8 Q

Sr-89, Sr-90 5x10 C

Continuous 9 Composite

-6 Fe-55 1x10 I

i l

l l

l l

SEQUOYAH - UNIT 1 3/4 11-2A Amendment No. 3

l l

l TABLE 4.11-1 (Continued)

TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may incl de radiochemical i

separation):

4.66 s bb0

• E V

2.22x10*

Y exp (-Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

ss is the standard deviation of the background counting rate or of tMe counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 x 108 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s used in the calculation of the LLD for a detection systemshallbkbasedontheactualobservedvarianceofthebackground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y, and at shall be used in the calculation.

SEQUOYAH - UNIT 1 3/4 11-3

TABLE 4.11-1 (Continued)

TABLE NOTATION b.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c.

Prior to analyses, all samples taken for the composite shall be

(

throughly mixed in order for the composite sample to be represen-l tative of the effluent release.

d.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e.

A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

f.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

g.

Releases from these tanka are continuously composited during releases.

With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representive batch samples from each tank to be released to be taken prior to release and manually composite for these analyses.

SEQUOYAH - UNIT 1 3/4 11-4 Amendment No. 3

I TABLE 4.11-2 (Continued)

TABLE NOTATION b.

Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when c.

the refueling canal is flooded.

d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER level change exceeding 15% of RATED THERMAL POWER in one hour and analysis shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.

Tritium grab samples shall be taken at least once per 7 days from e.

the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f.

The ratio of the sam;;1e flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

g.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these i

nuclides are to be detected and reported.

Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and report.

h.

During releases via this exhaust system.

1 1.

In MODES 1, 2, 3 and 4, the upper and lower compartments of the con-i tainment shall be sampled prior to VENTING 'r PURGING.

Prior to o

entering MODE 5, the upper and lower compartments of the containment shall be sampled.

The incore instrument room purge sample shall be obtained at the c.;1 eld building exhaust between 5 and 10 minutes-following initiation of the incore instrument room pu;ge.

I I

f l

SEQUOYAH - UNIT 1 3/4 11-11 Amendment No. 3

~~

t o

l i

I i

RADIOACTIVE EFFLUENTS I

DOSE - NOBLE GASES

~

I l

LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents from the site (see Figure 5.1-1) shall be limited to the following*:

}

a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, 1

l b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION l

a.

With the calculated air dose from radioactive noble gcses in gaseous effluents exceeding any of the above limits, in lieu cf any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during tne remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b.

The provicions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall '. fetormined in accordance with the ODCM at least once per 31 days.

"Per reactor unit.

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SEQUOYAH - UNIT 1 3/4 11-12 1

2 8.1 SPECIFICATION 3/4.11.1 Prior to initial criticality, the requirements for sampling and analysis for items A.6, A.7, and A.9 in Table 4.11-1 may be waived provided the release is through the turbine building sump (item 8.2 of the Table 4.11-1).

8.2 SPECIFICATION 4.8.1.1.2c The surveillance requirements for verifying diesel generator voltage and frequency during diesel generator starts is waived for the original surveillance interval only.

8.3 SPECIFICATION 4.7.8.1, ITEM D 3 The 1/4 inch negative pressure requirement within the spent fuel storage area and ESF pump rooms is waived during the low power test program.

However, the auxiliary building gas treatment system shall be capable of maintaining these areas at a slight negativa pressure during this period.

8.4 SPECIFICATION 3.3.3.10, TABLE 3.3-13, ACTION 41 Flow rates for ventilation systems for the shield building exhaust, auxiliary building and service building may be estimated using the design flow rate for the appropriate fans.

This interim waiver extends the 30-day limit for 18 months from the issuance of this license.

This waiver is cansidered to be an interim measure until flow rate monitors for the ventilation system for these structures can be repaired or replaced.

8.5 SPECIFICATIONS 3. 5. 2, 3. 5. 3, 3. 6. 2.1, 3. 6. 3.1, a nd 3. 7.1. 2 Prior to initial criticality, the provisions of Specification 3.0.4 are not applicable when system inoperability has been determined solely on unresolved piping support or restraint deficiencies.

SEQUOYAH - UNIT 1 8-1 Amendment No. 3

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 3 TO LICENSE DPR-77 TENNESSEE VALLEY AUTHORITY INTRODUCTION By letter dated March 28, 1980, the Tennessee Valley Authority (TVA) proposed changes to the Technical Specifications for Sequoyah Unit 1 dealing with the surveillance requirements for taking radioactive liquid and gaseous samples.

We have evaluated these changes.

One change was proposed to install a continuous composite sagier and flow monitor on the condensate demineralizer regenerant effluent line to replace the present program which required compositing batch samples from the non-reclaimable waste tank and the high crud tanks to obtain a representive sample of those potentially radioactive releases.

A second change was proposed to specify the allowable time for taking remedial action when iodine or particulate samplers are inoperative. A third change was proposed to specify when gas samplers of the containment atmosphere were required prior to operating the purge fans. These changes were necessary to clarify sampling frequency for the gaseous effluent monitoring program.

In addition to the above proposed changes the licensee has agreed to include the continuous composite sampler and flow monitor on the condensate demineralizer regenerant effluent line in the effluent monitoring instrumentation section of the Technical Specifications.

ENVIRONMENTAL CONSIDERATION We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Section Sl.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.

l EVALUATION The proposed change to the Sequoyah Technical Specifications for the continuous composite sampler and flow monitor involves the installation of a device to take samples from the effluent line rather than taking routine samples from the non-reclaimable waste tank and high crud tanks on a batch basis and composit'ng l

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9

, 1 these samples for the post-release analysis. The change will not alter the liquid effluent sampling requiste or the continuous monitorin.g and control provisions, but will provide a continuous representive sample of all condensate demineralizer regenerant waste released. We find the charge is an improvement on taking samples, that the sampling by instrumentation method is permitted by the Standard Technical Specifications and the proposed changes to Tables 3.3-12, 4.3-& and 4.11-1 on pages 3/4 3-70A, 3/4 3-72A, 3/411-2A and 3/411-4 as enclosed, are acceptable.

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The proposed change to ACTION 36 to Table 3.3-13 of the present technical specification would specify a time period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to complete the installation of auxiliary sampling equipment for the collection of radiofodines or particulate materials in gaseous effluents whenever the routine sampling equipment is inoperable. We find that this period is reasonable for this remedial action and is within the scope of other prompt actions specified in the Standard Technical Specifications, and therefore, is acceptable as written.

1 l

The proposed change to footnote (f) to Table 4.11-2 of the present technical specifications would define the time for taking gaseous samples from the containment atmosphere prior to venting or purging. The present Standard Technical Specifications intended that an initial sample be taken prior to shutdown purging of the containment in order to open containment prior to each purge during reactor operation.

In the present technical specifications, the footnote (i) required sampling based on each purge fan operation. The licensee has requested additional operational flexibility to start and stop the purge i

fans during open containment withcut the requirement for additional samples.

We find this proposal acceptable, and the NRC staff suggested clarif;ing i

modifications with the agreement of the licensee, for this change.

CONCLUSION We have concluded, based on the considerations discussed above, that:

(1) because the amendment does not involve a significant increase in the pro-bability or consequences of accidents previously considered and does not involve i

a significant decrease in a safety mar significant hazards consideration, (2) gin, the amendment does not involve a there is reasonable assursnce that the j

health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with l

the Commission's* regulations and the issuance of this amenament will not be inimical to the common defense and security or to the health and safety of the public.

DATE:

July 1,1980 f

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