ML18026B129

Proposed Tech Spec Re Radioactive Gaseous Effluent Instrumentation Surveillance

ML18026B129
Person / Time
Site:	Browns Ferry
Issue date:	08/01/1984
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18026B128	List: ML18026B127 ML18026B129
References
NUDOCS 8408070375
Download: ML18026B129 (74)

Text

ENCLOSURE 1

PROPOSED TECHNICAL SPECIFICATION REVISIONS TVA BFNP TS 192 SUPPLEMENT 1

BROWNS FERRY NUCLEAR PLANT 8408070375 84080i PDR ADOCK 05000259 P

PDR

PROPOSED UNIT 1 SPECIFICATIONS

NOTES FOR TABLE 3.2.D

~At all times

~:<During releases via

. ~'<:During operation of I"

this pathway an MtR loop and associated RNR service water system ACTMN A During release of radioactive wastes from the radwaste processing

system, the following shall be met (1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.l, (2) if this cannot be met, two independent samplers of the tank being discharged shall be analyzed in accordance with Table 4.S.A;>and two qualified station personnel shall independently veri~f the release ratle/calcu-lations and check valving before tne aiscnarge.

j}therwise, suspend r

~ase via this pathway.

ACTION B'ith a 'radioactive liquid effluent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway wit.hout delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications.

'ACTION C During operation of an MIR loop and associated RHR service water system, the effluent from that unit's service water shall be conti uously monitored.

If an installed monitoring system is not available, a

temp ary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LLlfjdf 1E-1 pCi/ml (gross) or < applicable MPC ratio (y isotopic) shall be used to monitor the effluent.

ACTION D Wit.h the number of channels OPERABLE less than required by the Minimum Channels Operable requirement;, effluent releases via this 'pathway may continue provided that a temporary monitor is installed or, 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 radioactivity with an LLD < ) of lE-7.

tjCi/ml (gross) or < applicable MPC ratio (y isotopic).

ACTION E With the number of channels OEPRABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue 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 F Alarm/trip,sct.points will be calculated.in accordance with the guidance,give in the Offsite Dose Calculation Manual (ODCM).

(1)

Spe Table Notation - 4.8.8 for definitig of LLD.

76A

'k

TADLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Instrument STACK a.

Noble Gas Honltor b.

Iodine Cartridge c.

Particulate Filter d.

Sampler Flow Abnormal e.

Stack Flowmeter 2.

REACTOR/TGRBIRF. BLDG 'Jiff a.

Noble Gas Honitor b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flowmeter 3.

TURDINE DLOG M!AUST (6) a.

Nobile Gas tlonltor b.

Iodine Sampler c.

Particulte Sampler d.

Sampler Flowmeter 4.

IthDMASTE DLI)G VEN1 6) a.

Ifoble Gas tfonitor b.

Iodine Sampler

'c.

Particulate Sampler d.

Sampler Flowrate 5.

OFF GhS IIYDROGEH ANALYZER (Ilgh,. II2D)

G.

OFF GAS 1'OST TIIEA'flfEHT(5) a.

Noble Gas Activity Honitor b.

Sample Flow Abnormal Instrument Clieck D

I)

Source Check H

Nh NA Nh Nh H

NA Nh Nh H

NA IIA Nh H

Hh HA NA NA H

NA Channel Calibration R(1)

HA NA R

R R(I)

NA Nh R

R(l)

Nh Nh R(1)

Nh NA n

R(3)

R(1) lf ~

Functional R

Test Q(2)

NA NA Q

9) '

NA NA Q

Q(?)

HA HA Q

Q(2)

Nh Nh (2)

Q 108A

LIMITl'NG CONDITIONS FOR OPERATION 3.8 RADIOACTIVE MATERIALS SURVEILLANCE RE UIREHENTS 4.8" RADIOACTIVE MATERIALS excess of limits specified in 3.8.A.5, prepare and submit the Special Report pursuant to Section 6.7.2.8.2.

7.

The maximum activity to be contained in one liquid radwaste tank or temporary radwaste storage tank that can be discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.

6.

The quantity of radioactive material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least.

once per 7 days when radioactive materials are being added to the tank.

8.

With radioactive liquid waste exceeding 3.8.A.7 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the 1imit.

Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report (6.7.3.A).

283

LIMITING'CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.S P~IOACTD~ MATERIALS B.

A'borne Effluents 4.8 RADIOACTIVE MATERIALS B.

Ai"born Effluents a.

The dose rate limit for noble gases sh ll be (500 mrem/yr to tne total body and (3000 mrem/yr to the

skin, and b.

The dose rate limit for I-131, I-133, I1-3.

and particulates with greater than eight day half-lives shall be 4500 mrem/yr to any orga'n.

2.

I the limits of 3.8.B.1 are exceeded, appropriate corrective action shall be immediately initiated.to bring the releases within limits.

Provide prompt notification to the NRC pursuant to section 6.7.2.A.

1.

The dose rate at anv time to areas at and beyond the site boundary (see Figur 4.8-lb) due to radioactivity released in gaseous effluents from the site shall be limited to the following values:

1.

The gross P/y and particulate activity o gaseous wastes released to the envi onment shall be monitored and recorded.

f a.

~or effluent streams having continuous monitoring capabil. ty, the activity shall be mon-'tored and

'loi'ate evalua ed and recorded to enable release "ates of gross radioac"ivity to b determined at le st donee pe" sh ft using instruments spec.'ied in table 3.2.K.

b.

For effluent streams without continuous monitoring capability, the activity shall be' monitored and record d

and the releases through these streams controlled to within the limits specified in 3.8.B.

2.

Radioactive gaseous waste

'ampling and activity analysis shall be

-p'erformed in accordance with Table 4.8.B.'ose rates shall be determined to be within limits of 3.8.B using methods contained in the ODCH.

284.

0

""': 4G CO>'DZTIONS ~OP T 0'URE ILMC~ iK P~'ANTS 3.

• The air dose t<> ar<<as at and beyond the site bounda (see Figure4.8-lb) due to

- noble gases released in gas ous effluents per unit shall be limited to he following:

Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCN at least once every 31 days.

4.

a.

During any calendar

quarter, to (5 mrad for gamma radiation and (10 mrad for beta radiation; b.

During any calendar year, to (10 mrad for gamma. radiation and (20 mrad for beta "adiation.

If the calculated air dose exceeds the limits specified in 3.8.3.3

above, prepare and submit a special report pursuant to section 6.7.2.B.2.

The dose to a member of the public from radio-iodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gasec us effluent released per unit to areas at and beyon the site boundary (see Figure 4. 8-..1b)

~ shall be limited to the following:

4.

Doses due "o gaseous releases to areas at and beyond the site boundary shall be projected in accordance with the ODCM at least once per 31 days.

Samples of offgas svstem effluents shall be'nalyzed at. least weel:ly to determine the identity and quantity of the principal radionuclides being released.

a.

To any organ during any calendar quarter to (7.5 mrem; b.

To any organ during any calendar year to (15 mrem; 285

0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS

6. If the calculated doses ex'ceed the limits of 3.8.B.5 above, prepare and submit a special report pursuant to section 6.7.2,B,2.

7.,During operation above 2~% power the discharge of the SJAE must be routed through the charcoal adsorbers.

6.

During operation above 25% power, the position of the charcoal bed bypass valve will be verified daily.

7.

The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the 'offgas whenever the SJAE is in service using instruments described in Table 3.2.K.

Instru-ment surveillance requirements are specified in Table 4.2.K.

8.

With gaseous wastes being discharged for more than 7

days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.B.2.

9.

Whenever the SJAE is in

service, the concentration of hydrogen in the offgas downstream of the recombiner shall be limited to

< 4% by volume.-

l0.

With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

286

4 I'

TARLE NOTATTON " TARLE 4.8sA (2)

A hatch rclcasc is the discharge of liquid wastes of a discrete volume.

Thc discharge shall. be thoroughly mixed prior to sampling.

A proportional composite sample is one in which the quantity of liquid sample(l is proportional to the quantity of liquid yaste discharged from thc plant and is representative of the liquid discharged.

(3)

The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that villbe detected with 95/ probability with only 5g probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which msy include radiochemical scpa ration):

4.66 sb U.D =

E

~

V

~ 2.22 x 10

~ Y

~ exp

-Adt Wl>ere:

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

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

E is thc counting efficiency (as counts per disintegration),

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is thc fractional radiochemical yield (when applicable),

is the radioactive decay constant for the particular radionuclide, il(l(l 4t for plant efflucnts is the elapsed time between the midpoint. of sample collection and time of counting.

Typical values of E, V, Y, and 4t,should be used in the calculation.

It should be recognized that the hLD is defined as an a priori (before thc fact) limit representing.

the capability of a measurement system and not as an a posteriori '(after the gact) limit for a particular mcasurcmcnt.

2908

The LLD is defin d, for th purposes of -nes" sp c'fecations as the sma est. concertration of rad'active m "erial '" 2 sample tha-will yield a n w count (above system backgrourd) tha will be detec d with 95 probabilitv with OD y 5 p obabill.ty c 21sely conclucing that a

blank obse~ation represeats a "real" signal.

For. a par icular measurement syste (which mzy 'ncluoe radiochemical

,separation):

4.66 sb V

~ 2.22 x 10" Y

~ exp (-Mt)

Vnere:

LXD is the "a prio i" lowe limit o de ection as de ined above (as microcu ies per unit mass or volume),

s is the standard devia ion of the background counteng rate or of tie couating rate of a blank sample as appropriate (as counts per miaute),

8 is the count'ng effe ciency (as coun s per disintegration),

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

2.22 x 10s is the number of dis ntegrations pe" minute, pe" microcurie ~

I is the fractional radiochemical yield (when applicable),

A, is the radioactive decay cons ant for the particular radionuclide, and ht for plant effluents is the elapsed tume between the midpoint of sample collection 2nd ime of counting.

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized Mt the LID is defined as ao a e "iori (before the dart) linit rep"esentins tha capability of a neasurenant ystee and not as an a osteriori (after the fact) limit for a particular measurement.

(2)

When samples are taken more often that that.shoba, the minimum detectable concentrations can be correspondingly higher.

290E

SMitchyard Turbine Building Exhaust Fan (32m)

Service Building Bld Bldg.

Turbine Building Rad-Waste Bldg.

Reactor Building Stack (180m)

Reactor Building Ventilation (40m)

Figure 4.8-.1a GASEOUS RELEASE POINTS AND ELEVATIONS

Figure 4.8-1b LAND SITE BOUNDARY

~

~

.~+;-""":

~ P;w'~'.', ~",:",:"

LlisN Oleckartt

~ qp

'I HVClCAO~

~ a~

~ ~

1 mile 2 miles 290H e

4

'. 0 AD~X?iISTRATIV:. CO!i CAROLS Procedures Process Con=rol Proera (PCP) 1.

The PCP shall be approved br the Com=ission prio" to

~lementa ion.

2.

Changes o the PCP shal' svb=it-ed -o th Com= ssion he semi annval Rad=oac

.ve Eff'u "

Release R po t for the period in w'"'ch he change(s) was made.

his submit al shall contain:

a.

Svfficien ly de ailed information o tota'ly svpport the change.

b.

A determination hat he change did not change the overall conformance of the solidified produc to existing criteria.

3.

Changes to the PCP shall becom effec.ve voon review and acceptance by POPC.

Oualitv Assu ance Procedures

- Ef=luent ano.Environmental Nonitorin Quality Assurance procedvres shall be established, implemen ed, and ma'ntained fo" effluent and environmen al monitoring, using the guidance in Regulator Guide 1.21, rev. 1, June 1974 and Regula ory Gvide 4.1, rev.

1, April 1975 or Regulatory Guide 4.15, Dec.

1977.

G.

OFFSITE DOSE CALCULATIONALMANUAL (ODOM The ODCM shall be approved by the Commission prior to implementation.

2.

Changes to the ODCM shall be submitted to the Commission in. the semi-annual Rad Ioact ive Eff]uen t Release Report for the period in which the change(s) was made.

This submittal shall contain:

a.

Sufficiently detailed information to totally support" the change.

3.

Changes to the ODCM shall become effective upon review and acceptance by PORC..

340

PROPOSED UNIT 2 SPECIFICATIONS

NOTES FOR TABLE 3.2.D "At all times

~::During releases via this pathway

~'"::During operation of an QIIR loop and associated RHR service water sys<<m ACTION A During rclcasc of radioactive wastes from the radwaste processing

system, the following shall be met (1) liquid ~aste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified.in 3.8.A.I, (2) if this cannot be met, two independent samplers of tlute tank being discharged shall be analyzed in accordance with Table 4.8.A;land two qualified station personnel shall independently veri~f thc release rate calcu-lations and check valving before tne aiscnarge.

Othcrwisc, suspend rjl~asc via this pathway.

ACTION 8 li With a radioactive liquid effluent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without dcIay, declare the channel inoperable, or adjust the alarm/trip sctpoint to establish the conservatism referred by these specifications.

ACTION C

During operation of an RIIR loop and associated RHR service water system, the effluent from that unit's service water shall be conti uously monitored.

If an installed monitoring system is not available

~

temp ary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an I.L6iojf 1E-7 IjCi/ml (gross) or

< applicable MPC ratio (y isotopic) shall be used to monl.tor the effluent.

ACTION 0 With th>> number of channels OPEIQBIS less than required by the Minimum Channels Operable requirement, effluent rclcases via this pathway may continue provided that a temporary monitor is installed or, 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 radioactivity with an I.LD

) of lE-7 uCi/ml (gross) or

< applicable NPC ratio (y isotopic).

ACTION F.

With thc number of channels OEPRABI.F. less than required by the Minimum Channels Opcrablc requirement, effluent releases via this pathway may continue provided, thc flow rate is estimated at least once pcr 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases'ump curves-may be used to cstimatc flow.

ACTION F Alarm/trip sctpoints will be calculated.in accordan'ce with the guidance given in the Offsitc Dose Ca]culation Manual (ODCM).

'I)

Svv 'I'able Not at lon - 4.8. 8 l'or di'f in i t fig of l,l,l).

7bA

0

ThBLE 4.2.K Radioactive Gaseous Effluent inslrumentatlon Surveillance Ins trun)cut STACK a.

Noble Gas tlonitor b.

Iodine Cartridge-c.

Particulate Filter d.

Sampler Flow Abnormal e.

Stack Flowmeter Instrument Check D

W W

D Source Check tl Nh HA HA NA Channel Calibration R(l)

HA NA R

Functional'est (2)

Nh Nh 2.

. 3.

4.

RERCTOR/TURIIINR BIDG @AT a.

Noble Gas tlonitor b.

Iodine San)pier c.

Particulate Sampler d.

Sampler Flowmeter TURi3IHE 13LDG EXllAUST 6)

Hobile Gas Honitor b.

Iodine Sampler c.

Particulte Sainpler d.

Sampler Flowmeter RADWASTE DLl)G VENT a.

Noble Gas Honitor b.

Iodine Sampler c.

Particulate Sampler

. d.

San)pier Flowrate OFF GAS llYDROGEH ANAT.YZER (ll,h, ll,D)

OFF GAS POST THEA'l'IlENT (5) a.

Noble Gas Activity tlonitor b.

Sample Flow Abnormal D

W W

D D

W M

D D

W W

D D

D tl tlA tlA Nh H

Nh NA Nh ll NA Hh Nh NA H

NA.

R(l)

NA Nh R

R(1)

NA NA R

R(l)

Hh NA R(3) q(R)0 HA Nh q(?)

NA NA

+)

HA Nh q(4)

(2)

(.4) 108A'

LIHITINC CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 RADIOACTIVE MATERIALS

.8 RADIOACTIVE MATERIALS excess of limits specified in 3.8.A.5, prepare and submit>>

the Special Report pursuant to Section 6.7.2.B.2.

7.

The maximum activity to be contained in one liquid radwaste tank or temporary radwaste storage tank that can be discharged directly to the environs shall not epceed 10 curies excluding tritium and dissolved/entrained noble gas.

6.

The quantity of radioactive.

material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

8.

With radioactive liquid waste exceeding 3.8.A.7 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.

Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report

~ (6.7.3.A).

283

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS P~IOACTD'E Yik.ERIALS 4.8 RADIOACTIK~i. MATERIALS B.

A'rborne Effluents B.

Airborn Effluents a.

The dose rate limit for noble gases sh ll be (500 mrem/yr to tne total booy and (3000 mrem/yr to the

skin, and b.

The dose rate limit for I-131, I-133, H-3.,

and particulates with.

greater, than eight day half-lives shall be 4500 mrem/yr to any orga'n.

2.

I the limits of 3.8.B.1 are exceeded, appropriate correc ive action shall be immediately initiated to bring the releases, within limits.

Provide prompt notification to the NRC pursuant to section 6.7.2.A.

1.

The dose rate at anv time to areas at and beyond the site boundary (see Figur 4.8-1b) due to radioactivity released in gaseous e"fluents from the site shall be limited to the following values:

The gross P/y and pa rtz cul a te a

ctz.vasty o

gaseous wa tes released to the environment shall be monitored and recorded.

a.

For effluent streams having continuous monitoring capability, the activity shal1.

be monitored and flow rate evalua ed and recorded to onable release

=ates of gross radioac-ivity to be determined at least once pe sh ft using instruments specified in table 3.2.K.

b.

For effluent streams without continuous monitoring capability, the activity shall be monitored and record d

and the releases through these streams controlled to within the limits specified in 3.8.B.

2.

Radioactive gaseous, waste sampling and ac ivity analysis shall be p'erformed in accordance with Table 4.8.B.

Dose

'ates shall be determined to be within limits of 3.8.B using methods contained in.the ODCM.

284.

bG CO~'D"TIONS ~OP RAT 0'UBWr.ILLAÃC~

IF~~".ENTS 3.

4.

The zir dose to areas at and beyond the site bounda (see Figure 4.8 1b)due to noble gases released in gas ous effluents per unit shall be limited to he following:

a.

During any calendar

quarter, to (5 mrad for gamma radiation and (10 mrad for beta radiation; b.

During any calendar year, to 410 mrad for gamma radiation and (20 mrad for beta "adiation.

If the calculated air dose exc eds the limits specified in 3.8.B.3

above, prepare and submit a special report pursuant to section 6.7.2.B.2.

3.

4.

Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCM at least once every 31 days.

Doses due to gaseous releases to areas at and beyond the site boundary sha11 be projected in accordance with the ODCM at, least once per 31 days.

Samples of offgas svstem erfluents shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.

5.

The dose to a member of the public from radio-iodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gasec us effluent released per

~ unit to areas at an'd beyon the site boundary (see Figure4.8-1b) sha11 be limited to the following:

a.

To any organ during any calendar quarter to $7.5 mrem; b.

To any organ during any calendar year to (15 mrem; 285 1 ~

l p'

~i 'ji>gp

0 jl

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIRBKNTS

6. If the calculated doses exceed the limits of 3.8.B.5 above, prepare and submit a special report pursuant to section 6.7.2.B.2.

7.

During operation above 25% power the discharge of the SJAE must be routed through the charcoal adsorbers.

6.

During operation above.25%

power, the position of the charcoal bed bypass valve will be verified daily.

7.

The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the offgas whenever the SJAE is in service using instrumen'ts described in Table 3.2.K.

Instru-ment surveillance requirements are specified in Table 4.2.K.

8.

With gaseous wastes

being, discharged for more than 7

days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.B. 2.

9.

Whenever the SJAE is in,

service, the concentration of hydrogen in the offgas downstream of 'the recombiner shall be limited to < 4% by volume.,

10.

With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

286

0

'TARI;l'. HO'fATIOM " TABLE 4.8sA (l)

A l)arch release is the discharge of liquid wastes of a discrete volume.

Thc <<lischarge shall, be thoroughly mixed prior to sampling.

(2')

A. proportional composite sample is one in which the quantity of liquid sample(i is proportional to the quantity of liquid waste discharged from the l)lant and is representative of the liquid discharged.

.(3)

Th<<i Ll.D is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yicl<<l a new count (above system background) that will be detected with 95/ probability with only 5$ probability of falsely concluding that a

blank observation represents a "real" signal.

For a particular measurement systim (which may include radiochemical separation):

4.66 sb LID =

E

~

V

~ 2.22 x 10

~ Y

~ exp

-Aht Where:

l'.LD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

is the standard

<<h.'viation of the background counting rate or of t,l)c counting rate of a blank sample as appropriate (as counts per minute),

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

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

2.22 x 106 is the number of disintegrations per minute per microcurie, I

Y 'is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide,

~lsd ht. for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V,.Y, and ht should be used in the calculation.

(t should he rccotnised that tha LLD is defined as an a Dciori (hefore thc Cact) limit representing, the capability of a measurement system and'ot as an a posteriori (aftdr the.fact) limit for a particular mcasurcmcnt.

290B

Cl

+ NOTATIOÃ - 4.8.B The LLD is defined, for the purposes of tnes spec'ficztions zs the sma est concertration of rad'oactive m -erizl '" z sample that will yield a new count (above system background) tnz" will oe detect d wi-h 93>> probability c"ith only 3rooability of =zlse'y conclucing that a

blznk obse~ation represents a "real" s'gnzl.

For a particulzr measurement system (which mzy enclude radiochemical separation):

4.66 sb E

~

V

~ 2.22 x 10

~

Y

~ exp (-Mt)

Rhere:

ZLD is the "a priori" lowe" limit o detection as de incd above (as microcu ies per unit mass or volume),

s is the standard devia=ion of the b"eh~round countinj :ate or of tEe counting rate of a blank sample as appropr'ate (as counts per minute),

5 is the count'ng efficiency (as counts per dis'ntegratio-),

V is the sample size (in uni-s of mzss or vo}ume)g 2.22 x 10s is the number of disintegrations pe" minute per microcuriep 7 is the fractional radiocnemical yield (when applicable),

A, is the radioactive deczy constant for the par icular radionuclide, and ht for plant effluents is the elapsed

<<'me between the midpoint of sample collection znd ime of counting.

Typical values of E, V, Y, and ht should be used in the calculation.

Zt shon1d be recognised Mt Ae LID is dcdined as an a o"iori (before the fact) limit rep"esenting he capability of a measnroment system and not as an a posteriori (afte= the fact) limit for a pasticcio" measurement.

(2)

When samples are ~ken more often that that shobe, the minimua. detectable concentrations can be correspondingly higher.

290E

Switchyard Turbine Building Exhaust Fan (32m)

Service Building Bld Bldg.

Turbine Building Rad-Waste Bldg.

Reactor Building Stack (180m)

Reactor Building Ventilation (40m)

- Figure 4.8-,1a GASEOUS RELEASE POINTS AND ELEVATIONS

Figure

.8-lb LAND SITE BOUNDARY

.1 mile 2 miles l

29 H,;

'6.0

~~~1>':1SW-'.TIV:-

CO)i POLS P=ocedu es Process Con "ol Pro"ram (o"o)

The PCP shall bc approved by th= Cor"ission prior to Qaplemen ation.

Changes o the PCP shel be sub=it ed:o he Co=-ission

'n the sem'-annual Rad'oac-'ve Zffluen R

1 ase R"po=t for the period 'n w'"'ch the change(s) was made.

"'s submit al shall contain:

a.

Su ficien-ly de" ailed in ovation

=o tota' y suppor-the change.

A.determina ion -'"at the chang did not chz

.e the overall conformance of the solidified produc to existing criteria.

3 ~

Changes to the PCP shall become e~~ec ive noon

." view and acceptance by POPC.

Oualitv Assurance P.ocedures

- Effluent ano ".nvironment al t~lonitorin Quality Assurance procedures shall be es ablished, hplemen ed, and ma'ntained fo" effluen and enviromen al monitoring, using the guidance 'n Pegulato~

G ide 1.21, rev.

1, June 1974 and Regula oy Guide 4.1, "ev.

1, April

975, or Regulatory Guide 4.15, Dec.

1977.

. G.

OFFSITE l)OSE CAI.CIII.A'I' LIAI. hiAhIIIAI. (I)l)(.'hl) 1.

'I'lie Ol)(hl sl)al I l)c.)pprov((l l>>v

) I)(~ C()(n)))lssin)) I>>'i<<)r (o I )lip I (. ment <Il~ll)i( s to t II(

()I)Chi

) ~ I):) I I l)(a

((l)ml ( f( ~(I

) <<<<( I)(

(<amml a ~ aa I ()))

I n tll(a )<<el(I) auu)(l:I I II<<l(l ) o:I('I

) V('".fI' ll('lit l4<< I (' (:a('((apol t for tl)e perio(l i>> wl)icl)

) l)e

( I)))n).(. (s) w)s m)(l(.

'I'l)is Hul)ml t tal I sallal I I coll( <<I I n:

a.

Sufficiently (letailed information to totally support tile cl)a)nge

~

3.

CI)anges to tl)e Ol)Chl sl):) I I I)(.(:ome <<ffeet ive upon review

()n(1 acceptance I)v, l)OR(..

PROPOSED UNIT 3 SPECIFICATIONS

IviITIllG CONDITIONS FOP. OP~~'TION I 'SURW~ILLQ'C"- REOUIPZ~~?iTS l~

~I>>

I

~ ~L ~I <<>>

~

I

~I~

I

3. 2'RO~ CTIKK INSTR'~~'TATION 4 '

PROT:-CTiV NSTRP.'=NTATION 3.2.D P~>ZIOACTD~i. LI UID EFFLUZST

"!ONITORING INSTRPEKTATION The radioactive liquid effluent instrumentat.'on listed in Table 3.2.D shall be operable with the applicability as shown in Table 3.2.D/4.2.D.

Alarm/

trip setpoints will be set in accordance with guidance given in the ODCYi to ensure that the limits of specification 3.8.A.1 are not exceeded.

MONITORING INSTRU. -STATION

).

C Each of the rz-.oactive liquid effluen-moni ozing, instruments shz 1 be demons ated o-erable by performance o

est in accordance with Table 4.2.D.

.4.2.D PMIOACTD'I UID E:.FLU".NT 2.

3 ~

4 The action required when the number of operable channels is less than the minimum channels operable requ'zement is specified in the, notes for Table 3.2.D.

Exert best efforts to return the instru-ment(s)'to OPERABLE status within 30 days and if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.]

With a radioactive liquid effluent monitozing channel alarm/trip setpoint less

'conservative than required'y these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/tr'p setpoint to establish the conservatism

. required by these specifi-cations.

4.

The provisions of specifi-cations

).O.C and 6.7.2 are

'- not applicable,.

51

~

0

NOTES FOR TABLE 3.2.D

<<At all times

~"During releases via this pathway "T"--During operation of an MlR loop 'and associated MIR service water system ACTION A

'During release of radioactive wastes from the radwaste processing

system, the following shall be met (1) liquid waste'activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.l, (2) if this cannot be met, two'ndependent samples of the tank being discharged shall be analyzed in accordance with Table 4.8.A; and two qualified station personnel shall independently veri~f the release rate calcu-lations and check valving before the aiscnarge.

Otherwise suspend release via this path~ay.

ACTION B Mith a radioactive liquid effluent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications.

ACTION C During operation of an RHR loop and associated RNR service water system, the effluent from that unit's service water shall be continuously monitored.

If an installed monitoring system is not available,'

temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LL6 kf 1K-7 pCi/ml (gross) or c applicable MPC ratio (y isotopic) shall be used to monitor the effluent.

ACTION D Wit.h the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, 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,radioactivity with an LLD(i) of lE-7

,uCi/ml (gross) or < applicable MPC ratio (y isotopic).

ACTION E Mith the, number of channels OEPRABLE less than required by the Minimum Charm'cia Operable requirement, effluent releases via this pathway may continue 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 F I

Alarm/trip sctpoints will be calculated.in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM).

(1)

- See Table Notation 4.8.B for definition of LLD.

TABLE 4.?.K Radioactive Gaseous Effluent Instrumentation Surveillance I

Instrument 1.

STACK a.

Noble Gas tfonitor b.

Iodine Cartridge c.

Particulate Filter d.

Sampler Flow; -Abnormal e.

Stack Flowmeter 2.

REACTOR/TORBIRE BLBG IIEET a.

Hoble Gas tlonitor b.

Iodine Sampler c.

Particulate Sampler d.

Sampler Flowmeter 3.

TURBINE IKDG EKIIAUST a.

tlobile Gas tlonitor b.

Iodine Sampler c.

Particulte Sampler d.

Sampler Flowmeter 4.

RADMhSTE BLDG VENT a.

Noble Gas tlonitor b.

Iodine Sampler c.

I'articulate Sampler d.

Sampler Flowrate 5.

OFF GAS IIYDIIOGI:IIANALYZER (ll2A, II2D) 6.

OFF GAS POST TREATIIEHT (5) a.

Noble Gas Activity tlonitor b.

Sample Flow Abnormal Instrument Check D

N D

D D

M D

D W

M D

D M

D D

D Source Check tI NA HA NA Nh tl tlA Nh Hh H

NA Nh HA ll NA NA Nh NA H

Nh Channel Calibration R(1)

NA Nh R

R R(1)

NA tlh R

R(1)

Nh R(1)

Nh NA R

R(3)

Functional.

'fest q(2)

NA q(2)

NA Nh q(2)

NA Hh q(2)

Nh Nh 0

q(4) q(?)

q(4) 103A

LIMITING CONDITIONS FOR OPERATION 3.8 RADIOACTIVF. MATERIALS 4.8 RADIOACTIVE MATERIALS SURVEILLANCE RE UIREMENTS excess of limits specified in 3.8.A.5, prepare and submit the Special Report pursuant to Section 6.7.2.B.2.

The maximum activity to be contained in one liquid radwaste tank or temporary radwaste storage tank that can

'e discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.

6.

The quantity of radioactive material cont'ained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's 'contents at least once per 7 days when radioactive materials are, being added to the tank.

8.

Mith radioactive liquid waste exceeding 3.8.A.7 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.

Events leading to this condition must be reported in the next

'Semiannual Radioactive Effluent Release Report (6.7.3.A).

301

LIMI ING COhDITIOhS FOR OPERATIOh SURVEILLAhCE PZ UIRE."KÃTS 3.8 RADIOACTIVE MATERIALS B.

Airborne Effluents

.8 RADIOACTIVE MATERIALS B.

A'rborne Effluents 2.

If the limits of 3.8.B.1 are exceeded, appropriate corrective action shall be immediately initiated to bring the releases within limits.

Provide prompt notification tithe NRC pursuant to section 6.7.2.A.

1.

The dose rate at any time to areas at and beyon the site boundary (see Figure 4.8-1b) due to radio activity released in gaseo effluents from the site shall be limited to the following values:

a.

The dose rate limit for noble gases shall be (500 mrem/yr to the total body and (3000 mrem/yr to the

skin, and b.

The dose rate limit for I 131 ~ I 133' 3

and particulates with greater than eight day half-lives shall be <1500 mrem/yr to any orga'n.

1.

The gross P/y and particulate activity of gaseous wastes released to the en:ironment shall be monitored and recorded.

a.

For effluent streams having continuous monitoring capability, the -ctivity shall.

be monitored and flow ate evaluated and recorded to enable relea'e rates of gross radioactivity to be determined at 'least once.per shift using inst uments specified in table 3.2.K.

b.

For effluent streams without continuous moni"oring capability, the ac"ivity shall be moni'red and recorded and the releases through these streams cont"oiled to within the limits specified in 3.8.B.

2.

Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table 4.8 B Dose rates shall be determined to be within limits.of 3.8.B using methods contained in

. the ODCM.

302

IMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.

The air dose to areas at a beyond the site boundary (see Figure 4.8-Ib)due to noble gases released in gaseous effluents per unit shall: be limited to the following:

a.

During any calendar ouarter, to (5 mrad fo" gamma radiation and (10 mrad for beta radiation; b.

During any calendar year, to (10 mrad for gamma radiation and (20 mrad for beta radiation.

4.

If the calculated air dose exceeds the limits specified in 3.8.B.3

above, prepare and submit a special report pursuant to section 6.7.2.B.2.

Cumulative auarterly and yearlv dose contribut-'ons from gaseous releases shall be determined using methods, contained in the ODCM at least once every 31 days.

4.

Doses du to gaseous releases to areas at and beyorld the site boundary sha11 be projected in accord'ance with the ODCM at 3:east once per 31 days.

Samples of offgas'ystem effluents shall be analyzed at least weekly to determine the identity "nd quantity of the p" ncipal radionucl"'des being released.

5.

The dose to a member of the public from radio-iodines, radioactive materials in particulate form, and radionuclides other than noble gases

,with half lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the site boundary (see Figu 4.8-lb)shall be limited to the following:

a.

To any organ during any calendar" quarter to g7.5 mrem; b.

To any organ during any calendar year to $15 mrem; 303

~:

LIMITING CONDITIONS FOR OPERATION

6. If the calculated doses exceed the limits of 3.8.B.5 above, prepare and submit a special report pursuant to section 6.7.2.B.2, 7.

During operation above 25X paver the discharge of the SJAE must be routed through the charcoal adsorbers.

SURVEILLANCE RE UIREHENTS 6.

During operation above 25X power, the position of the charcoal bed bypass valve will be verified daily.

7.

The concentration of hydrogen downstream of the recombiners shall be determined to be within the'imits of 3.8.B.9 by continuously monitoring the offgas whenever the SJAE is in service using instruments described in Table 3.2.K.

Instru-ment surveillance requirements are specified in Table 4.2.K.

8.

With gaseous vastes being discharged for more than 7

days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.B.2.

9.

Whenever the SJAE is in

service, the concentration of hydrogen in the offgas downstream of the recombiner shall be limited to < 4X by volume.

10.

With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

3Q4

(

P

TABLE NOTATION " TABLE 4.8eA (1)

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

Thc ilischarge shall. be thoroughly mixed prior to sampling.

(2)

.A proportional composite sample is one in which the quantity of liquid samplrd is proportional to the quantity of liquid waste discharged from thc plant and is representative of the liquid discharged.

(3)

The I.LD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will.

yield a new count (above system background) that will be detected with 95/ probability with only S$ probability of falsely concluding that a blank observation represents a "real" signal.

, For a particular measurement system (which may include radiochemical separation):

4,66 sb LI.D*=

E '

~ 2.22 x 10

~ exp Aht Where:

I.LD is the "a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),

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

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

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

2.22 x 10s is the number of disintegrations per minute per microcurie, Y is thc fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and bt for plant effluents is the elapsed time between the midpoint of sample collection and time of.counting.

Typical values of E, V, Y, and ht should be used in the calculation.

lt should be recognized that tha LLD is defined as an a pr'iori (before thd fact) limit representing the capability of a measurement system and hot as an a posteriori (aftdr the fact) limit for a particular mcasurcmcnt.

309A

The LU) is defin d, for th purposes of -nes spec'f.nations as the sma est concentration of rad'oactive m -erial== a sample tha-will yield a n w cournt (above system background) that will be detect d with 95 probabi)ity with only 5

ooability of =alse'y concluding that a

blank obsewation.represents a "real" s'gnal.

For a particular measurement system (which may encluoe radiochemical separation):

4.66 s b Z

~

V

~

2 e 22 x )0" Y

~ exp (-Mt)

Vnere:

LLD is the "a priori" lowe" limit o. detection as de ined above (as microcu ies per unit mass or volume),

s is th standard devia ion of the b"ckground count ng ra-e or of tie counting rate of a blank sample as appropriate (as counts per minute),

E is the count'ng eff'iency (as coun s pe" disin-egratio-),

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

2.22 x 10s is the number of dis'ntegrations pe" minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A, is the radioactive decay cons ant for the particular radionuclide, and ht for plant effluents is the elapsed ime between the midpoint of sample collection and time of counting.

Typical values of E, U, Y, and At should be used in the calculation.

It should b>> recognized ~t rbe LID is defined a." an a o"iori (before the fact) limit rep=esenting tbe capability of a measu ament"system and not as an a osteriori (af e" the fact) limit for a particular measuremcnt

~

(2)

When samples are taken more often that that shobw, the minimus detectable concentrations can be correspondingly higher.

310A

0

-0

Stoitchyard Turbine Building Exhaust Pan (32m) 0 fic Service Building Bldg.

Turbine Building Rad-Uaste Bldg.

Reactor Building 4

Stack (180m)

Reactor Bui:lding Ventilation (40m)

Pfgure 4.8-.l.a GASEOUS RELEASE POINTS AND ELEVATIONS

0

Figure 4.8-lb LAND SITE BOUNDARY 1 mile 2 miles 310D

TABLE 3.13.C REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS.IN EmtIROHNEHTAL SAMPLES h~aal sis Mater

~(Ci 1)

Reporting Levels Airborne Particulate Fis>>

Nilk Food Products

~tl H-3 Nu-54 Fe-59 Co-5S Co-60 Zn-65 Zr-Nb-95 I-131 Cs-134 Cs"137 Ba-La-140

2. 10<<'

x 10' x 102 1 x 103 3 x 102 3 x 10~

4 x 102 30 50 2 x 102 N.A.

N.A.

H.A.

N.A.

N.A.

N.A.

H.A.

0.9 10 20 N.A.

N.h.

3 x 10" 1 x 10~

3 x 10~

1 x 10~

2 x 10~

N.A.

i N.A.

1 x 10s 2x103 N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

H.A.

60 70 3 x 102 N.A.

N.A.

H.A.

N.A.

N.A.

N.A.

N.A.

1 x 102 1 x 10s 2 x 103 N.A.

For drinking water samples.

T>>is is 40 CFR Part 141 value.

359M

0

6.0 M~XKiSTRATIVz. CO!i, LS Procedures

& ~

Process Con rol Procram P"P The PCP shall be aporoved bv the Com"ission prior to implementation.

2.

Changes o the PCP shal'e submitted -o th Com=issioa the aem'-annual Pad. oac-'ve Ef~~uen Release R po" for the period in w"'ch the change(s) was made.

his submittal shall contain:

a.

Sufficicn ly de a-'led information o to a'ly support the change

~

b.

A determiaatioa

hat, he change did not change the overall conformance o

he solidified produc to existing criteria.

3.

Changes to the PCP shall becom effective upon review aad acceptance by PORC.

F.

Oualitv Assurance Procedures

- Effluent and Environmental Moaitorin Quality Assurance procedures shall be established, implemcn ed, and ma'ntained fo" effluent aad eni'iroamea al monitoring, using the guidance in Regulatory Guide 1.21, rev. 1, June 1974 and Regulatory Guide 4.1, rev.

1, April 1975 or Regulatory Guide 4.15, Dec.

1977.

G.

OFFSITE DOSE CALCULATIONALMANUAL ODD~M 1.

The ODCQ shall be approved by the Commission prior to implementation.

2 ~

Changes to the ODCM shall bu submitted to the Commissfon in. the semi-annual Radioactive Effluent Release Report for the period in which the change(s) was made.

This submittal shall contain:

a.

Sufficiently detailed information to totally support the change.

3.

Changes to the ODCM shall become effective upon review and acceptance by PORC.

370

ENCLOSURE 2 PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION.

SUPPORTING TVA APPLICATION TVA BFNP TS 192 SUPPLEMENT 1

BROWNS FERRY NUCLEAR PLANT TVA application for license amendment TVA BFNP TS 192, submitted by letter'rom L. M. Mills to H.

R. Denton dated October. 27,

1983, was prenoticed in the Federal Re ister dated January 26, 1984, in "Part III, Nuclear Regulatory Commission." That notice contained a

discussion of the changes proposed in the October 27, 1983 TVA application. It also contained a proposed NRC staff determination that the application does not involve a significant hazards consideration since the change constitutes additional restrictions a'nd.controls that are not currently included in the technical specifications.

The additional specification changes proposed in application TVA BFNP TS 192 SUPPLEMENT 1, are not substantive changes to the original application dated October 27, 1983.

The changes were made in response to NRC staff comments sent to TVA (reference, letter from D. B. Vassallo to H. G. Parris dated

.December 20, 1983) and as discussed in a March 22, 1980 telephone confer ence between TVA and NRC staffs.

There are no changes proposed which would alter the NRC staff's conclusion regarding the no significant hazards consideration determination made for the October 27, 1983 application.

The specification changes proposed in TVA BFNP TS 191 SUPPLEMENT 1

constitute additional restrictions and controls that are not currently in the technical specifications.

This is consistent with one of the examples of no significant hazards consideration provided by the Commission in the Federal Re ister (48FR14870).

For those reasons TVA proposes to determine that application TVA BFNP TS 192 SUPPLEMENT 1, involves a no significant hazards consideration.

ENCLOSURE 3 JUSTIFICATION FOR USE OF 1$

HYDROGEN GAS TO CALIBRATE BROMNS FERRY NUCLEAR PLANT OFFGAS HYDROGEN ANALYZERS Normally, there is no detected hydrogen present in the offgas system during power operations.

Therefore, the presence of any detectable hydrogen is an operational concern.

Attached is information currently in Operating Instruction 66 that is utilized by Operations personnel in the event hydrogen concentration exceeds 1-percent.

One-percent and lower is the critical, range for Browns Ferry Nuclear Plant, therefore it is imperative we are very accurate through this critical range.

Procedures require corrective actions to

'start at 1-percent.

Calibration to a higher percent hydrogen will not increase reliability or instrument accuracy at the lower critical range.

In addition, the analyzer has a self-calibration feature which initiates approximately every 3-1/2 hours to self-calibrate it to certified 1-percent hydrogen gas.

(Excep t from Operating Xnst ruction 66) 6.

Hydrogen in off-gas system ) 1g but' 4g.

a.

Check H2 analyzer recorder on 9-53 to ve if H

/

y 2 percentage.

Both analyzers should show the same H

e same 2 level.

If disagreement between analyzers, contact instrum t d umen epartment to perform a calibration and proceed based upon H

up>>

2 level indicating highest per centage.

b.

Request chemical lab begin sample procedure.

m (Continued)

Q, OFF-GAS HYDROGEN ANALYZER.

(Continued)

Page 46 BF OI 66 6I 19i992 6.

Hydrogen in off-gas system 1C but

< 4g.

(Continued) c.

Check recombiner preheater temperature

> 340 F.

1)

Check PIC-66-175A or -175B throttling to maintain steam inlet pressure at 250 psig.

If'reheater inlet steam valve is not fully open the preheater may be charged through common drain lines.

2)

Visually verify preheater steam valves open.

3)

Check if preheater is draining properly and all other drains open.

gJQIXXQK:

LOW INLET TEMPERATURE TO RECOMBINER CAN CAUSE DEACTIVATION (ALARM < 275oF).

d.

Check SJAE operating. properly.

1)

Check for proper draining.

2) If recomb1ner inlet is less than 340 F water carryover from the SJAE discharge may be occurring. If 1nlet temperature to recombiner is low and cannot be increased, place spare SJAE in service.

3)

Check first and third stage pressure " 210 psig.

e.

Check recombiner differential temperature.

If recombiner is operating properly, the differential temperature should follow load changes, i.e., increase load should show increased AT.

Check per OI>>66, III.D.1.f, f.

Check if off-gas condenser dra1n wells are dra1n1ng correctly.

j g

'I

.)

XV (Continued)

Q.

OFF-GAS HYDROGEN ANALYZER.

(Continued)

P Page 47 55TY~$32 6.

Hydrogen in off-gas system

> 1$ but < 4$.

(Continued) g.

Zf recombiner is not functioning properly, place standby recombiner in service.

1) 'pen standby recombiner outlet valve (FCV-66<<78 or -91).

2)

Close malfunctioning recombiner outlet valve (FCV-66<<78 or "91) ~

h.

Continue to check H2 concentration frequently with radiochemical analysis of grab sample.

7.

Hydrogen in off-gas system

> 4$ (refer to DPM BF76010 and BF 7705).

a.

Insure that all steps listed in Abnormal Operations for H2 >

1g and

< 4C have been performed.

GQlXXQK:

AFTER THE H2 CONCENTRATION EXCEEDS 4$ q ANY ACTION TO SWITCH FLOW PATHS, BYPASS SYSTEM COMPONENTS OR TO SWITCH TO SPARE COMPONENTS MAY CAUSE H2 IGNITION.

THIS COULD POSSIBLY BE FOLLOWED BY COMBUSTXON OF THE ACTIVATED CHARCOAL ZN THE SYSTEM AND DAMAGE TO THE PREFILTERS AND POST FILTERS.

IMMEDIATE REDUCTION OF THE H2 CONCENTRATION IN THE OFF-GAS ZS IMPERATIVE.

POTENTIAL SYSTEM DAMAGE DUE TO H2 IGNITION INCREASES DRAMATICALLYWITH TXME.

b.

Notify shift engineer of conditions and upon shift engineer's

approval, manually scram the reactor when the following conditions exist:

1)

H2 analyzers show ~ 4$ ~

2)

Radiochemical laboratory grab sample indicates explosive mixture.

~

~

I Page 48 BF OI 66 Jul 2 7 1983 (Continued)

Q.

OFF-GAS HYDROGEN ANALYZER.

(Continued) 7.

(Continued) b.

(Continued) 3)

Recombiner differential temperature trend is extrenely low for

. present power level (pe - Table 1, BF OI-66).

c. If reactor has been

scramned, follow GOI-100-11.

DUE K) KiE EOSSIBILITY OF H2 IN ME CONDENSER'TARTING OF CONDENSER VACUUM'UNPS MAY CAUSE AN EXPLOSION.

d.

Closely monitor the following parameters:

l)

H2 analyzers.

J 2)

Charcoal adsorbers and adsorber vault tanperatures.

3)

Prefilters and post filters differential pressure.

I 4}

Off-gas flow rate.

5)

'System pressure.

6}

Post treatment radiation level.

7)

Recombiner differential temperature.

8)

Temperature drop across the vault refrigeration unit.

e.

Continue hourly radiochemical lab grab samples until H2

" concentration is 5 2%.

f.

Do not start condenser vacuum pumps until H2 concentration is

( 2% ~

g.

Visually survey, in conjunction with Health Physics coverage, all accessible system components such as post filters, prefilters, recombiners, preheaters<

and off-gas condenser.

'evision

I