ML19260D893

Notification of 800214 Meeting W/Nrc in Bethesda,Md to Discuss Proposed Radiological Effluent Tech Specs.Forwards Written Responses to Proposed Agenda Items.Fourteen Oversize Drawings Available in Central Files Only

ML19260D893
Person / Time
Site:	Browns Ferry
Issue date:	02/08/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Ippolito T Office of Nuclear Reactor Regulation
References
NUDOCS 8002120562
Download: ML19260D893 (43)

Text

.

400 Chestnut Street Tower II February 8, 1980 Director of Nuclear Reactor Regulation Attention: Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nucicar Regulatory Commission Washington, DC 20535

Dear Mr. Ippolito:

In the Matter of the ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 In my letter to you dated December 7, 1979, a meeting between TVA and NRC staffs to discuss the proposed radiological effluent technical specifications for the Browns Ferry Nuclear Plant was tentatively estatlished for ~anuary 24, 1980. Because of other important meetings which could not be rearranged we were unable to meet on that date.

As discussed with R. J. Clark of your staff, we now plan to meet in the Bethesda, Maryland, offices on February 14, 1980.

As suggested in my letter dated December 7,1979, we are providing, as an enclosure, written responses to the proposed agenda items forwarded to us by your letter to H. G. Parris dated November 26, 1979. Although not rtquested by NRC, we believe such written responses will aid the NRC staf f in their review of the submitted technical specifications and will lead to a more productive meeting.

We look forward to a productive meeting with your staff on February 14, 1980.

Very truly yours, TENNESSEE VALLEY AUTHORITY a

\

d f' , !' .$

, L T M. Mills, Manager Nuclear Regulation and Safety p Enclosure \

1950 199 A[E-*p

1. 6 8002180sej 5 4 2

ENCLOSURE RESPONSE TO AGENDA ITC!S RADIOLOGICAL EFFLUENT IECliNICAL SPECIFICATIONS BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3

(

REFERENCE:

Letter T. A. Ippolito to H. G. Parris, dated November 20, 1979)

1. General Response

2. Attachment A - Revised pages 54a (units 1 and 2) and 56a (unit 3)

3. Attachment B - Revised Tables 3.2.R and 4.2.K, pages 84a, S4b, 84c, 110a, and 110b (units 1 and 2) and 37a, 87b, 87c, 107a and 107b (unit 3) 4 Attachment C - Flow diagrams of effluent paths (submitted under separate cover to the NRC Browns Ferry project manager)

5. Attachment D - Revised pages 233 (units 1 and 2) and 301 (unit 3)

c. Attachment E - Revised pages 2bl (units 1 and 2) and 299 (unit 3)

7. Attachment F - Revised pages 356a (units 1 c.id 2) nd 386a (unit 3)

8. Attachment G - hevised pages 153 (units 1 and 2) and 157 (unit 3) 1950 200

s GENERAL RESPONSES FOR AGESDA ITRIS FOR B OhES FERRY RETS 5!EETING GEFEICCE: LI'!!En FEC:1 T. A. IPPOLITO TO 11. G. PARRIS DATED MOVD13ER 26,1979)

1. No answer required. (Future questions should be referenced to TVA's Appendix I submittals dated June 29, 1979, and July 20, 1979.)

2. Requested wording can be incorporated. (See Attach =ent A)

3. A. Flew rate and sacpler flow rate. The design of EFMP's building ventilation systema does not incorporato installed flow rate conitoring instrumentation. Flow rate values are periodically measured using portable test instruments.

The radiation monitors associated with the building's exhaust cycten have sample flow rate instrumentation. These inotruments will be included in our technical specification submittal. (Sco Attachment E)

Stack exhaust flow rato is measured using an annubar flow cicuent.

The sauple flew rate to the stack's radiation monitor is ceasured using a rotoceter. The design and installation of these instruments do not require periodic calibration.

D. Hydrogen monitors in offgas treatuent system (0GTS). (Scc response to question 15B below.)

C. SJAE radiation monitor. (See ansucr to quection 15C below.)

D. OGTS exhaust conitor - The offgas post treat =cnt conitor is presently covered by technical specification tables 3.2.D. and 4.2.D.

A description of the monitor can be found in FSAR section 7.12.

E. Drywell purge monitors - Drywell purge conitors are not included in the design of BFMP. Purge flows are routed either through the reactor building ventilatica system at to the stack via the SGTS.

Each pathway contains charcoal and HEPA filters. (Ref. cxisting technical specification sections 3.7.B. and 3.7.F.)

20th release points have continuoun monitors. Additionally, table 4.8.B. requires an analysis of a drywell atmospheric sa:ple prior to each purge.

4. See Attachcent C.

5. Stack =enitor - The stack monitor continuously analynes the stack effluent.

This effluent is comprised of the discharge frc= each unit's offgaa system, each unit's steam packing exhauster, and the discharge of the coc=on SGTS.

Deletion of this conitor would result in unmonitored releases from the SGTS and the steam packing exhauster.

1950 201

e.

6. Channel functional test. It una car intention to include circuit failure with the IMOP/00WU scale failure. For the radiation conitors associated with building ventilation systen, In02/DCWN scale includes:

high voltage failure, detector failure, sample flow failura, counting rata =eter f ailure, or counting rateceter out-of-service.

k'e will include 'not set in operate code' for the stack's radiation coattor. The design of the ventilation system monitors will not accoumodate this function.

7. As requested, va vill =odify our wording to reflect i= mediate action.

(See Attachcents D and E)

8. Section 6.7.3.C.2 has been modified as requested. (Sce Attachment F)

9. The three BFUP units share a common liquid radwaste system. The design of Sn:P precludes the operation of the plant without operation of the liquid radwaste system. The necassity for radusste system operability has been demonstrated by our experience since the initial startup of Unit 1 in 1973. Therefore, incorporation of an operability specification will serve no useful purpose.

Proposed section 3.8.3.7 requires operability of the charcoal adsorber vessels, as necessary, to insure dose rate limits are not exceeded.

Additionally, the design of the BFMP augmented offgas treatment system precludes unit operation of the system with the hydrogen reccubiners by-passed (there is no bypass piping). Plant policy is to operate the charcoal vessels following startup of the units. There have been 4 occasions during the life of the plant that outage durations have exceeded 92 days. Under these circumstances, cocpliance with the proposed specification would not have been possible. (See also the answer to 14 below)

10. Service water nonitors - We will include requirecents for the RER service water monitors, as requested. (See Attachment G)

11. There is a flow rate conitor on the raduasto dischargo line. Thio instru-cent is addressed by our proposed technical specification sections 3.8.A.7 and 4.3.A.S.

12. There are no outside raduaste storage tanks at BFMP. Each unit has an outside condensato storage tank (CST). The overflow lines from these tanks are routed to radwante. There are no process radiation monitors designed for these outside CST's.

13. Channel function test - As requested, proposed technical specification scetion 4.3.A.3 has bcon revised to clearly define functional test requirements. (See Attachment E)

Additienally, functional test requirements for the RHR service water

=enitors is being incorporated into proposed section 4.5.C.S. (See Attachment G) 1950 202

14. At 3FNP, auxiliary boiler (non-nuclear) steam is used for operation of the SJ/2 during unit outages and during the initial startup opera-tions. During these periods, it is not essential to route offgas flow through the charcoal adsorber vessels. In f act, high of fgas flow rates are experienced prior to startup as condenser vacuum is being established.

A manditory requirement to route these high flou rates through the char-coal adsorber vessels would purge activity previously deposited at lcw flei rates. This wculd greatly increase the plant's releaso rate until vessel equibriun was reestablished. Experience has deconstrated that up to two weeks are someti=es required to reestablish adsorber vessel equibriu= release rates. Therefore, incorporation of the proposed oper-ability requirescut is not consistent with our joint objective to minimize the amount of activity released to the environment.

15. A. See answer to question 12 above.

3. Of fgas syctem explosion preventien - Actual esperience at 3FNP demonstrates the need to minimize the possibility of offras system expolosions. As stated in our reply to bulletin no. 78-03, BFNP adninistrative procedures czist presently to ensure that explosive hydrogen concentrations are de-tected. I=mediato corrective action (s) is specified to eliminate the potential hazard. Cur administrative control program is based on vendor recommendations. Because of this existing program, incorporation of the proposed specification would produce unnecessary duplication without improving plant safety.

C.  !!aximum curic limit at SJAE - Cascous activity leaving the reactor la continuously monitored by four nain steam line radiation monitors.

Upon detection of an abnormal amount of activity, these monitors initiate inmediate isolation of main secan flow with subsequent reactor shutdown.

The ef fluent from the offgas system is continuously monitored before it is discharged to the plant stack. These post-treatment monitors also contain isolation logic to initiate reactor shutdown. Additionally, prior to ,ffsito release, diluted offgas activity is continuously nonitored by the stack radiation conitors. The requirements for these conitors are specified in the current BFNP technical specifications.

The original offgas system design did not provide hydrogen reccebiners or charcoal adsorber vessels. Treatment consisted of an approxicate 30 minute holdup followed by a !! EPA filter. With the original systec, the radiation monitor at thu discharge of the SJAE provided an indication of tha amount of activity that would be discharged by a unit to the stack.

The eenitor, therefore, served a vital function and its importance at that time justified isolation logic as well as inclusion in the technical specifications.

Following addition of the reccmbiners and charcoal vessels, the function of predicting a unit's discharge to our co==on stack was assu=ed by monitors installed downstream of the charcoal vessels. Accordingly, these post-treateent monitors were designed with isolation logic which is presently acknowledged in our technical specifications. The new systen only retained ona of the original two SJAE conito'rs and clininated 1950 203

13 C. the isolation logic. By nutual agreement, requircecnts for this nonitor was deleted f rom the technical specifications.

The tonicor is new utili=ed as an operator aid and provides data to cent contractual fuel warranty co==it=ents.

The present of fgas system provides treatment by reducing the total offgas flow rate and utilizes both a holdup volute and charcoal vcasels to delay the release of activity. A IEFA filter then recoves any remaining particulate matter before the effluent is discharged to the stack. The performance of this systen is directly dependent upon the offges flew rato and the isotopic distribution of the offgas. Beenuse these are operational variables, the SJAE conitor cannot quantita-tively predict the concentrations of activity that will ulti=4tely be discharged to the stack later. Additionally, since all three unita discharge to a coc=on stack, calcula-tion of the total plant release rate is co= prised of the sum of each unit's ludividual contribution to the stack. Thus, the number of unica in operation and their respective puuer levels directly influence the plant release rate. For these reasona, including the SJAE ronitor in the technical specifi-cations and stating a actpoint would require using unwarranted conservatism for the three variables centioned above which directly affect the total plant release rate.

A candatory li=it on SJAE activity is unduly restrictive for our multi-unit plant with our type of trentrent system and would unduly inhibit our operating flexibility. This is especially true during refueling outages when atack contri-butions are from only two units.

D. Sec ruawer to question 3E above.

1950 204

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The :;ol;l radicactivo <ca t.: sy;te:n procecuca spen; res;;. 3 c.cid filter :.edias, sir,e r s .: u fil'ed ana dewatered to a level CC dryr.cc: cf leau than 1-; ercent Ly volw sh t .:. r e e's -a-  : li:,;.m.a 1 c ; i t.:; ;s. Redu,, :cs;.t ;su~.7 3 , valves, and j'i[ J .] '

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j 1950 205

16. The discharge from the techanical vacuum pumps used to initially establish condenser vacuun prior to startup is routed to the stack.

rollcuing a holdup period and dilution, it is monitored prior to release by the stack's radiation monitor. (Ref. to question 3 above).

The rational for section 3.3.D is explained in the bases associated wit,a this section.

1950 206

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ATTACHMEh r A /// / ' ~ . Lsi -.

LI!'ITI" CC':DITIC::5 FCR CI'EMTir:: SL*RVE!I.LACE REn"I P r'T"TS 3.2.K Radioactive caseous Effluent 4.2.K Radicactive Casecus Effluent Monitorinc Instrumentation Monitorir.c Instrunentation

1. TliE PADICACTIVE GASECUS EFFLUENT MONITCRING INSTRU- ,

l. Each of the radioactive FENTS LISTED IN TASLE 3.2.K gaseous effluent monitoring SHALL EE OPERABLE WITH THE instruments shall be demon-APPL ICA91L ITY AS SHO'JN IN strated operable by perfor-TAELES 3. 2.K. /4.2.K. AL ARM / mance of test: in accordance TRIP SETPOINTS U!LL SE SET with table 4.2.K.

TO ENSURE THAT THE LIMITS CF SPECIFICATIC'l 3.8.9.1. ,

ARE NOT EXCEEDED.

2. The action required when the number of operable channels is less than the Minimun Channels Operabic requirement is specified in the notes for table 3.2.K.

"Icetc/me<r[ //0 . 1950 207 -

2 , CL s2

ATTACHr'ENT A 9// / 7 5 LI?'ITI!: CC':DITIC!:S F( CPE?AT!C:: SUE"E!i.LA!:CE "En"!? T'E:'T5

<3.2./ Padioactive caseous rffluent 4.2.K Radicactive Casecun Effluent

!!cnitorine Instrumentation Monitcrinc Instrumentation

1. THE PADICACTIVE CASECUS EFFLUENT MONITORING INITRU- 1. Each of the radioactive MENTS LISTED IN TABLE 3.2.K ,

gaseous effluent monitoring SHALL SE OPERA 3LE UITH THE instruments shall be demon-APPLICABILITY AS SHOUN IN strated operable by perfor-TAELE5 3. 2. K . /4.2. K . ALARM / mance of tests in accordance TRIP SETPOINTS U!LL EE SET , with table 4.2.K.

I TO EN5URE THAT THE LIMIT 5 CF SPECIFICATI0H 3.8.8.1.

ARE NOT EXCEEDED.

2. The action required when the nucher of operable chanacls is less than the Minimum Channels Operable requirement is specified in the notes for table 3.2.K.

w

""" 1950 208 4.~/ ,~, / A.

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,3 TABI.E 3.2.K A., RADI0 ACTIVE CASEGUS EFFLtlEllT !!O:;ITORI!iG I!!STRU.'tENTATION I

4 liinicum Channels Instrueent Operable App 1fcability Parameter Action

.a 1. Stack ' '

a.  !!oble Cas (1)

• Release Rate A/C Activity lionitor fica s u recaen t

b. Iodine  !!A * -

Installed B .

. Cartridge n

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• Installed B filter S hi

% 2. Reactor / Turbine -

4 i lluilding Ventilation "3

^

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• Release Rate A/C ,

Activity Ffonitor fica su rec:en t

b. Iodine . 'onitor (1)

• Release Race B/C Q Fleasurement -

c. Particulate lionitor (1)

• Release Rate 11/C (t}

cl. SAf'PI ER Flf td FAlli t'CNitCR g p

~

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• Release Rate B/C

}feauurement

c. Particulate !!onitor * (1)

• Release Rate B/C Ifcaourement d . SGMf ift F1631 9 Art' N e t,r e p p [g} 4, g

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1OTES FOR TABLE 3.2.K

• Luring releases via this pathway.

., u -ACTIO!; A Ulth the number of channels CPEPA3LE less than re

!!inimum Channels Operable requirement, quired b'f the

affected pathway may effluent releases tia the continue for up to 7 da3s provided a tem-

{ and analyzed at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.perarynmenitoring sy

.1 ACTIO' B

!!inimum Channels Operable requirement,With effluena.

red by the the numb pathuay may continue for up to 28 days, presided samples areleases via thi continuously collected with auniliary sampling equipmentrer fo s

after the end of the sampling period. periods on the ours order of s i

ACTIO'I C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> f testing, calibration, or repair without providi or functional or initiating grab sampling. ng temporary nenitor ACTlod D, WEN -Svt. mJ-

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!!OTES FOR TABLE 4.2.K ,

• During releases via this pathway.

~ (1) The C!UMEL CALISPATIC!i shall include the use of a known (traceable to the

!!a tional Bureau cf s tandards radiation =casure=ent syste=) radioactive cource (s) positioned in a reproducible gec=etry with respect to the sensor.

(2) The CIL\!;!;EL FU:!CTIC !AL TEST shall also de=enstrate that centrol roon alarm -

annunciation occurs if any of the following conditions exist:

1. Instru=ent indicates =casured icvels above the alar =/ trip setpoint.

2. Instru=ent indicates an inoperable downscale failure.

3. .I'"1TRotANT th urRCt.L NOT EET I M O PE RA N AAoDC (S TAC K O M LT O

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1950.213

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,3 TABLE 3.2.K A RADIOACTIVE CASEOUS EFF1.UF:!1T 110NITORING INSTRUMENTATIO:1 3

+ ..

3 flinitum

% Chanrels Instrument Operable Ayplicability Parameter Action

.o 1. Stack

a. Iloble Gas (1)

• Release Rate A/C Activity Ifonitor  !!ca s u r et2en t

b. Iodine llA

• Installed B .

. Cartridge 2>

c. Particulate lia

• Installed B filter 03 2. Reactor / Turbine - ~4 us N liullding Ventilation h  !!oble Gas

=

• Release Rate A/C

a. (1) ,

Activity lionitor  !!casurement

b. Iodine lionitor (1)

• Release Rate B/C Ifeasurement

c. Particulate Ifonitor (1)

• Release Rate B/C Ifensurement

d. SAf.tPLER Ft1td mili facy gcz (g) t m 3. Turbine Building 5 s

D Exhaust .

Ln -s CD a, liable Gas (1)

• Release Rate A/C g Activity lionitor Ifeasurement

{ b. Iodine Ifonitor (1)

• Release Rate

!!eauurement B/C

c. Particulate }!onitor '(1) * ,

Release Rate B/C

. Ifeauurement

( - SGMPtat Ftr.31 pntf or t yen e fG a 9

. - - - - --. J 6 _ _j i._.. - . t.- - - . . _ . . . . - .

i

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A R

N 3.2.K (Continued)

N s RA1)IDACTIVE CASE 0HS EFFLUDIT ttONITORINi:' INSTRUtfENTATION D

A

% } fin ir.uu 1

g, Channels Instrument Operable Applicability Parameter Action

4. Radwaste Building '

Ventilation '

a. Hoble Cas (1)

• Ac t ivity !!oni tor Reicase Rate A/C

b. . lodine Monitor *

(1)

Release Rate B/C 03 licasurement q c. Particulate }fonitor (1)

• Release Rate B/C

!!ea s u remen t s.k . 6MLER FUW (AIF N(ma,a (Q k 9

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aDuring releases via this pathway.

ACTIO!! A

'71th the number of channels CPEP13LE less than required by the

!!inimu- Channels Operable requirement, effluent releases via the affected pathway may continue for up to 7 da!.3 provided a ten-perary conitoring system is installed or grab samples are taken and analyzed at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTIO!! 3 .

With the number of channels CPEF).BLE less than required by the 5ini=ue Channels Operable requirement, e f fluen a. releases via this pathtay may continue for up to 28 dcys, provided samples are centinuously collected with auniliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period.

ACTIO'l C A conitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing te=porary monitor or initiating grab sampling.

ACT16'l C,

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<.' mriNT D t.I!!ITI!:C CC :DITIC:!S FCP. OPE?ATIO!! SUR'!EILLA;;CE REQUIRF!!E!iTS 3.8 PAD ICACTI'/E !GTERI AL3 4.8 PADICACTIVE '! ATERI ALS B. Airborne Effluents B. Airborne Effluents

l. The doce rate at any 1. The grcss S/Y and time in the unre- particulate activity of stricted areas (see gasecus wastes released Figure fS'S 1 ) due to to the environment shall radicactivity released be monitored and recorded in gaseous effluents frcm the site shall be limited to the follow-ing values:

a. The dose' rate a. For effluent linit for noble streams having con-qaren chill be tinuous monitoring

- 500 mrem /yr to capability, the the total bcdy activity and flow and 43000 rate shall be nrem/yr to the monitored and skin, and recorded to enable release rates of gross radicactivit'.

to be determined or

\> an hourly basis

.' using instruments specified in Table 3.2.K.

)

9 b. The dose rate b. For effluent strear limit for all without continuous 9 -

radioicdines for monitoring capa-NN all' radioactive bility, the activit materials in shall be monitorec particulate form. and recorded and and for radio- the releases throuc nuclides other 'hese streams shal.

than noble gases be controlled so with half lives that the release

~

greater than 8 , rates from all days shall be streams are within 1500 mrem /yr to the limits speci-any organ. fied in 3.8.3

c. Ir TN. L!rt!._ 2C_r 2. Radioactive gaseous waste 3.B n-1 ==c =ver='="

~------- * *U U * ' '.I APPROPRIATE CCRRECT!iE '7" 3 ^3 . . - 42"'3 .-

"'"b a ' 1~~ b.'

.~

perform-p T ! u".1 "'aAf ' c_ c ..,~_3!-

in accordance w3.th ,*.,2Dlc OTELY INITI ATED TO ED IN'; 4*0 3*

T'E r RELE05EE U!iHI's L It1! T3. -

0CV!OE FCDrPT NCT!FI- '

CATICH TO TWE NRC 1OCn f /JU [ (7.U n PUREUANT TO SECTICN I 5.7.2.n.

I83 4

1

/*]iMst.o .We t I

b. - - - - -- -

ATTvCHtiny y U s.J. y'i-, -

L:!!ITI*:G CC':DITIO::S FOR OPE.UTIO:I SUR'/EILL/J:CE REQUIRE:E!TS

.3 i,n. D s,,,,,,w,, ......: ..n. . ,. . <

wg n.g .nnu.

. n . c n C *. .* '.m "n'..""..*s'w'"a B. AirScrne Effluents B. Airborne Effluents

1. The dcsc rate at any 1. The gross E/7 and time in the unre- particulate activity of stricted areas (see gasecus eastes released F :.g c re f.E S. I ) due to to the environment shall radioactivity released be monitored and recorded in gasecus effluents from the site shall be limited to the follow-ing values:

a. The doce' rate a. For effluent limit for noble streams having con-gases shall be tinuous monitoring d500 mrem /yr to capability, the the total bod"1 activity and flow and d-3000 rate shall be mrem /yr to the =cnitored and skin, and recorded to enable release rates of v gross radicactivit'.

-D to be determined or 9 $ an hourly basis using instruments 9(i\ s '

specified in Table 3 . .,. . t. .

b. The dose rate b. For effluent strear limit for all without continuous radioicdines for monitoring capa-all' radioactive bility, the activit materials in shall be monitored particulate f o r.r, and recorded and and for radio- the releases throuc nuclides other *.bese streams shal.

than ncble gases be controlled so with half lives that the release greater than 8 , rates from all davs shall be streams are within 15d0 mrom/yr to the limits speci-any organ. fied in 3.8.B ar er:. , l ii l .,.

,.. ia ,,Jr

2. P.adicactive gaseous waste . -

s a m c ,. i n 0 a :1, a c t iv l ...

, ,, - -e 2.0.=.,. 4 R E t A.:t. - 7. t D . a ,,. a 3. ,., ,;, ,- o;s1 3 ,, g ,, o ,. c ,, ,. -'

p pp e. r p o

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m .iist a , .T a 3 5, r ,,, ,,

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ATELY INITIATED TO EPING 4.3.3.

THE PELEASE3 L.!! THIN LIMIT 3. -

PQV!DE PROMPT NOTIFI-COTICN TO THE NRC eqssNTToseCr1C" 6.. 2.A. l950 22I A,enJ % f ,U0 3 U/

LI::III: r, 6.mlC::S FCR Osid.[*0!i S*JR*!EILL/e;C E hE.rJ1REliE::IS J.8 PADICACT!*!E !L' STERI AL3 4.8 PR)ICACT: lE ".ATEr! ALS Apolicability Apo:icability Applies to the controlled release of Applies to the pericdic test and ecord radioactive liquids and gases from requirements and sa pling and monitorin; the facility. tetheds used for facility effluents.

Cbjective Obiective To define the limits and conditions To ensure that radicactive liquid for the release of radioactive and gaseous releases from the facility effluents to the environs to assure are maintained within the limits that any radioactive releases are specified by Specifications 3.8.A and as low as reasonably achieveabic and 3.8.3.

within the limits of 10 CFR Part 20.

Smcification Snecification A. Licuid Effluents A. Liquid Effluents

1. The concentration of radio- 1. Facility records shall be active material released at naintained of radioactive any time from the site to concentrations and volume unrestricted areas (see before dilution of each Figure 4.EA.] shall be batch of liquid effluent linited to the concentrations released, and of the average specified in 10 CFR Part 20, dilution flow and length of Appendi- B. Table II, Co lunn time over which each discharge 2 for radionuclides other occurred.

than dissolved or entrained

, noble gases. For dissolved 2. Radioactive liquid waste or entrained noble gases, the sampling and activity analysis concentratien shall be of each liquid waste batch to linitad ec 2E-4 pCVal total be discharged shall be performed activity. prior to release in accordance with Table 4.S.A.

2. IF THE LIM!T3 CF 3.8.A.1 ARE EXCEEEED. APFRCPRIATE ACTION SHALL EE IMi'EDI ATELY INIT! ATED

. TO BRING THE RELEASE UITHIN .

LIMIT 3. PRCVICE PFCMPT NOTI-CICAT*ir9 TO TP~c NRC DURSUANT 3.

TO SECi!CN 6.7'A*

THE LICUID EFFLUENT RADI AT!CN MCNITCR SHALL DE CALISPATED AT LEAST CUARTERLY BY t'EANS OF A ENDUN rADICACTIVE SOU:CE 5) .

3. The doce or doce comr.itment THE pcNg7co gyALL AL30 pnVE AN INSTRUMENT to an individual from radio- CHANNEL FUNCTICNAL TEST "S'THLY AND AN active n,terials in liquid INSTRUMENT CHECK :n!LY. TFE FUhCTIONAL effluents released frcm each TE3T 5 HALL CEMONSTECTE THAT CCNTRCL unit to enrestricted areas RCCt1 GNNUNC I A TICH CCCURS IF THE !NSTRU-(See Figure 4. T. A / ) shall MENT lND !C ATES ME A5URED LEVEL 3 CF be limited: pnD:nTrcN Ago E Tag Ataq urR p sETp3rNr DR TbE lNSTRUMENT INDICATED A DCUN5CALE i

h FAILURE.

'Dj Ok Okg bhd 1950 222 A n.d w f i%.

s/

n i..n w i , ,7 -

Li !1T1::C CC'iDITIC:iS FCR OPE?>. TION SUR'IE!LLM;CE RCQUIRE:IE::T3 3.3 MDIC ACT:'l "ATF7IALS 4.3 RAD!cACT:VE mTEn:ALs Applicability Amelicability Applies to the controlled release of Applies to the periodic test and record radioactive liquids and gases from rcquircmenta and sampling and monitorfn; the facility. methods used for facility effluents.

Cb i ec t ive Objective i

To define the limits and conditions To ensure that radioactive liquid for the release of radioactive and gaseous releases from the facility effluents to the environs to assure are naintained within the limits that any radioactive releases are specified by Specifications 3.8.A and as low as reasonably achieveabic and 3.3.3.

within the limits of 10 CFR Part 20.

Smcification Saecification A. Licuid fflunnts A. Licuid Effluents

1. The contentration of radio- 1. Facility records shall be active material released at maintained of radioactive any time f rca the site to concentrations and volume unrestricted areas (see before dilution of each Figure 4.P.4 lshall be batch of liquid effluent limited to the concentrations released, and of the average specified in 10 CFR Part 20, dilution flow and length of Ap;'end i:- 3, Table II, Column time over which each discharge 2 for radionuclides other occurred.

than dissolved or entrained noble gases. For dissolved 2. Radioactive liquid waste

, or entrained ncble gases, the sampling and activity analysis concentration shall be of each liquid waste batch to limited to 2E-4 pC1/nl total be discharged shall be perfor=ed activity. prior to release in accordance with Table 4.8.A.

2. IF THE LIMITS CF 3.8.A.1 CPE ' '

EXCEEDED, APPPCPRIATE ACT!ON '"

SHALL EE IMMEDIATELY INITIATED D "" D "D Tl I r O

, TO ERING THE RELEASE UITHIN . C9 <> J C# ]'" "

LIMITS. PRCVIDE PRCMPT NOTI-F IC A T' W" TO THC" NRC PURCUANT

,0 c_C, 4 *c ION 6.7*2.A* 3. THE LICUID EFFLUENT RADI ATICH MCr[hbb?

EHALL EE CALISPATED AT LEAST CUARTERLY BY MEANS OF A K.NCUM FADICACTIVE SOURCE (5),

3. The dose or doce commit =cn 7pE ncNgTCR SHALL ALSO HAVE AN INSTRUMENT to an individual f rom radio- CHONNEL FUNCTIONAL TEST MONTHLY QND AN active materials in liquid INETRUMENT CHECK DA:LY. THE FUNCTICNAL effluents relcaced f r n m. each TE3T SHALL DEMONSTF ATE THAT CCNTRCL unit to unrestricted areas RCCM ANNUNCIATION CCCURS !F THE INSTRU-(See Figura 4. T.J . / ) shall FENT lNDICArE3 MEA 3URED LEVELS C.:

be limited: DAD : ATICN AECVE THE OL AR",'TR :P 3ETPO INT OR THE INSTRUMENT INDICATED A DCUNSCALd FAILURE.

,, o 1950 223 O df fa'ef);t-f at f

.4 r ,y 4- * *

/l./C,

6.Q iG ' . '. .n ?A T l '. . n .Gh5

• '3".*~

()N ? . 1 r, 2.

2. Prepare and subnit to the Cen:sission within 30 days, a Special .eport which identifies the cause(s) for excec ling TE LI'11T (s ) and defines the corrective action (s) to be taken to reduce the releases of radioactive natorial in

. liquid cffluents durinr, the remainder of the current calendar quarter and durin;, the subsequent three calendar quarters so that the average dose or dose ec nitnent to an individual f ron such releases durin:; these four calendar

~

quarters is within 3 neen ta the total body and 10 mren to any organ. This Special Report t, hall also include:

~

(1) the results of radiological analyses of the drinking

~

wa t e r s ou rc e s T&57 p M7:'nWJf , a nd ( 2 ) the radiological impact on finished drinking water supplies with regard to the requirements t: 40 CFR 141, Safe Drinking Water Act. f.WlltalW:tNnTT:ITu r1% inm terwm pp4y~iaren ieu md?r-we ~wr. w so mita A.be w .

3- Prepare and subnit to the Co nission within 30 days, a Special Report which includes the followinp, inf ormation:

a. Identification of equipment of subsystens not OPEPAULE and the reason for nonoperability,

b. Action (s) taken to restore the non operabic equip-ment to OPEFABLE status,

c. S u-- a r-/ description of action (s) taken to prevent a recurrence. -

4 Prepare and submit to the Conniscion within 30 days, a Special Report which identifics the cause(s) for exceeding the limit 3nd defines the corrective actions to be taken to reduce the releases of radiciodines, radicactive materials .

in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gasceus effluents during the renainder of the current calendar quarter and d u r in:: the subsequent three calendar quarters so that the averanc dose or dose commitment to an indi-/idual frer such rcIcases during these four calendar quarters is within (15)

. mren to any organ. -See item 6 below.

5. Preparc and nubmit to the Commission within 30 days, a Special Report which identifies the cause(:;) for excccding the limit (s) and defines the corrective actions to be, taken to reduce the releasen of radioactiec noble a,ases in ganccus of fluents durim; the remainder of the cur:ent calendar qur.cr

.nd durin, the cutscquent three calendar quarters so that the averar,c Jose durii..; these four calendar quarters is within (10) mr:d for ;enra radiatien and (2)) mrad for beta radiation.

See iten 6 below.

]*fj g 3'] h wL wh R. %

300" 1950 224 ItN en elm< a l Alo .

~

6.0 AL:!I :ISTRATIVE CC::TRO S MTACMEM F bh O O 2- Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding THE LIMIT (s) and defines the corrective actidn(s) to be taken to reduce the releases of radioactive material in

. liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose ccamitment to an individual from such releases during these four calendar

~

quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include:

~

(1) the results of radiological analyses of the drinking water sources TA~tspMG&iM, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, saf e Drinking 'a'accr Act. M18CerM:*:b1tlyf t T:2ic1Mirm weDemuppey-inxce:eMN we attr.__m semdmen- aseww.

3- Prepare and submit to the Commissica within 30 days, a Special Report which includes the following information:

a. Identification of equipment of subsystems not OPERA 3LE and the reason for nonoperability.

b. Action (s) taken to restore the non operable equip-ment to CPERABLE status.

c. Summary description of action (s) taken to prevent a recurrence. -

4. Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit 'and defines the corrective actions to be taken to reduce the releases of radiciodines, radicactive materials in particulate f orm, and radionuclides other than noble gases with half-lives greater than S days in gasecus effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an incividual fren such releases during these four calendar quarters is within (15)

. mrem to any organ. See item 6 below.

s

5. Prepare and submit to the Commission within 30 days, a Special Report which identifics the cause(s) for ex ceding the limit (s) and defines the corrective actions to be taken to reduce the relcaces of radioactive noble gases in gaseous effluents during the remainder of the current calandar quarter and during the subsequent three calendar quarters so that the average dose during these four calendar quarters is w;;hin (10) , rad for gamma radiation and (2)) mrad for beta radiation.

See item 6 below.

D" D *M w" w - .. A LL.d s. 1950 225 3asa

M '~/Litt*.t. & , . . ' i -

I.1MITING Co*:DITIONS FOR OPERATICN SUR'iEII.LidiCE RICUIRDINTS 3 '.C (Continued) 4.5.C (Continued)

4. 4 When it is deternined that y one of the RHr.SW pt.?p s sup-One of the D1 or D2 RHRSW plying standby coolant is pumps may be inoperable icoperable at a time when for a period not to cperability is required, the exceed 30 days provided cperable FFJtSW pu=p on the the operable pump is sa=e header and its asso-aligned to supply the RHR ciated diesel generator and heat exchan:;er and the the RRR heat exchanger associated diesel gen- header and associated essen-erator and the essential tial control valves shall control valves are oper- be de=onstrated to be able. operable i==ediately and every 15 days thereafter.

5. The R!iR servica water radiation monitors shall be calibratec at least quarterly b means of a known radioactive source (s). The monitors shall also have an instrument enannel functional test monthly and an ins tru:nent check dailv.

[ 5. If Specification 3.5.C.2 through 3.5.C.4 are not =et.

V an orderly shutdovn of the unit 1 shall be initiated!

and the unit placed in cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6. During operation of an RiiR loop having RiiR system pressure greater than service water pressure, the effluent from that loop's service water line shall be continuously monitored. If sampling systems are not available, temporary monitors or analysis of grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shall be used to monitor the j etfluent.

153 O

- 1950 226

s. . - - -

LIMIT!!;G C0!!DI!!C!15 FOR OPERATIOti SURVEILLMICE REQ"1REME :TC 3.5.C (Continued) 4.5.C (Continued)

4. '.' hen i t is determlncd that one of t he RHt:.".w pun p 3 s,m-

'v plying standby coolant L:

inoperable at a ime when operability is required, the operable FFJISW pu.mp on the same header and its asso-ciated diesel generator and the TdlR heat exchanger header and asnoriated essen-tial control v.tives shall be de=cnstrated to he operable i= mediately and every 15 days thereafter.

a. Three of the Dl, D2, Bl . 3 The RHR service water B2 RHRSW pu=ps may be in- radiation monitors shall be operable for a period not calibrated at least to exceed 30 days pro- quarterly by means of a vided the operable pu=p known radioactive source (s).

is aligned to supply the The monitors shall also FJ1R heat exchanger header .

have an instrument channe.3 and the associated diesel - ,

generator and essentiai , runctionaA test monthly control valves are and an instrument check operable. daily.

5. If specification 3.5.c.2 through 3. 5.C.4 are not =et, y an orderly shutdown of the affected unit shall be initiated and the unit placed in cold shutdown condi-tion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6. During operation of an RHR loop having RHR systen pressure greater than ser-vice water pressure, the effluent from that loop's service water line shall be continuousl< onitored.

If sar.pling systems are  !

not available, temporary acnitors or analysis of grab samples taken evers

'. hours shall be usc.' to monitor the effluent.

153 P 1950 227 m

,f !? ? C .'{ V ~. /J T & ,

a , f l ., .,-

. ~

LIMITING CONDITIONS FOR OPERAT!CN E*JRVEILLANCE RE0' !REMEN'!S r r

1. 5 CoR E MjD COtTTAINMENT 4. 5 COia ASD CONTAIUMEt.'T CCC LING COOLING SYSTEMS S Y ST EF;S 4 One of the B1 or B2 4 When it is determined RHPSW pumps may be that the al or B2 inoperacle for a RHRSW pump is period not to exceed inoperable at a time 30 dayr or Med the when operability is operable p. ap is required, the aligned to supply the operable RHRSW pump PHR heat exchanger on the same header header and the and its associated associated diesel diesel generator and generator and the RHR heat essential control exchancer header and valves are operable, associated essential control valves shall

5. If specifications be demonstrated to be 3.5.C.2 througn operable immediately 3.5.C.4 are not met, nd every 15 days an orderly shtttdown thereafter.

^ shall be initiated and the unit placed 5. The RHR ser d e water in the cold shutdown radiation monitors shall be condition within 24 calibrated at least quarterly hours. by means of a known radioactive source (s). The monitors shall

6. There shall be at also have an instrument channel least 2 RilRSW pumps , functional test monthly and associa ted with the an instrument check daily, selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing irradiated fuel.

7. During operation of an KliR loop having RHR systen pressure greater than service water pressure, the effluent fran that loop's service anter line shall be continucusly manitored. If sampling

^

systems are not avail-able, terporar'; menitors q cr analysis of grab samples ta' en every + 157 hours0.00182 days <br />0.0436 hours <br />2.595899e-4 weeks <br />5.97385e-5 months <br /> shall be usec to

=cnitor the effluent. i950 228