ML20058N232

Proposed Tech Specs 3/4.21, Environ/Radiological Effluents, 6.5, Station Reporting Requirements & 6.5.1.C.2 Re 10CFR50.59(b) Rept

ML20058N232
Person / Time
Site:	Cooper
Issue date:	12/10/1993
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20058N229	List: ML20058N226 ML20058N232
References
NUDOCS 9312210299
Download: ML20058N232 (23)

Text

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]..If11 Tit;c r:nNDITInNs rnR r PEIMTIOfi EEQ_QlEE!1EtiTS 6 ? Peview and Auclit 220

'.). l.A Statinn Operationn l'evi ew Commi t t.cc (50RG) 270 A.1  !!emoe t sh ip 220 A./ Meeting Ftequency 220 A.3 Quo rtun 220 A.4 Responsibilities 220 A.3 Aut hori t y 271 A.6 Recor<ls 17l A./ Proccituren  ??l 6.2.1.B TIPPD Safety Review and Audit Board (SRAB) 222 B.1 tietnhe r shi p 222 B.? 11ee t i nr, F equenev 222 B.3 Quo t tun 222 l'. 6 Review  ???

P. 'i Autbority 223 B.6 Recorris 721 h./ Audits 223

6. 3 l'i ncedu res atul Programs 225 6.1.1 Introduction 225 6 1.2 Procedores  ? ? r,

6. 5.1 Maint enance and Test P roc edtt r e r, /?S

'6.','. Radiation Control Procedures 225

.A liigh Radiation Areas 226 6.1.5 Temporary Changes 227 I 6.3.6 Exercise of Procedures 22/

6.3./ Programs 22/

.A S vs t eme. Inter,rity Monitoring Program  ??7

.B Iodine !!onitoring Program 227

.C Post-Accident Sampling System (PASS) 227 6.4 Record Retention 228 6.4.1 5 year retent-ion 228 6.4.7 1.i f e retention 728 6.4.3 2 year retetit.lon 229 6.5 Station Reporting Requirements 230 6.5.1 Rout ine Reports 230 l

.A Introduction 230

.n Startop Report 210

.C Annuti l itepo ri r. / 10

.D tionthly Operatitig Report 231

.F A i ',d i nl ogi ca l Env i ronmm a eport 731

[n()t)3 f .F b'-- Radioact ive flater al$ Re case Report 232

.G Core Operating 1 imi ts Report 232 O

05/22/91

' :MITING CONDITICN FOR CPERAT: "

15ty',E:.,ancy 1;ct:gryre73 2.21 ENVIRCNMENTAL/ RADIOLOGIC /L :FFLUENTS 4. 21 EV!EC" ENTAL /RADICLC'GICAL EFrLUENTS A. Instrumentation A. Instrumentation

1. Liquid Effluent "enitoring 1. Licuid Effluent Monitoring Anolicabilitv: As shown in Table a. Each :adioactive liquid effluent 3.21.A.I. conitoring instrumentation chan-nel shall be demonstrated OPER-Specification: ABLE by performance of the CHAN-NEL CHECK, SOURCE CHECK, CHANNEL

a. The radioactive liquid ef fluent CALIBRATION and CHANNEL FUNCTIONAL monitoring instrumentation chan- TEST cperations during the modes nels shown in Table 3.21.A.1 shall and at the frequencies shown in be OPERABLE with their alarm and Table 4.21.A.I.

trip setpoints set to ensure that the limits of 3.21.3.1 are not b. Radioactive liquid effluent moni-exceeded. tor alarm and trip setpoints shall be determined in the manner

b. '41th a radioactive liquid effluent described in the ODAM.

monitoring instrumentation channel alarm and trip setpoint less con-servative than required, reset without delay to meet Specifica-tion 3.21.A.I.a. suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservative,

c. '41th less than the minimum required number of radioactive liquid effluent menitorine instrument'-' -

gA%{

channelsConerablY take the h.CM ON shown in Table 3.21.A.l.

d. If the minimum number of instrument g channels is not returned to OPERABLE kg M

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g status within 31 days, in lieu of any other re ort, explain in_the _

nex h Radioactive ,

bQS

.eport why the instrument was not repaired in a timely manner.

e. The provisions of Definition J are not applicable. The reporting provisions of Specification 6.5.2 are not applicable.

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LIMIT!! C r^ :DITION r?R "PERAT P:  !  !!'R7E!Li.:CE EO":EE'!ENTI 3.21.A (Cont'd) 6.:'.A . Cont'd)

2. '3aseous Ef fluent Monit: ring 2. lasects Effluent Monitoring Anolicabilitv- As shown in Table 3. The setpoints shall be deter-3.21.A.2. mined in accordance with the -

l method described in the ODAM.'

Specification:

! b. Iach radioactive gaseous efflu-

a. The radioactive gaseous effluent ' ent monitoring instrumentation monitoring instrumentation chan- I channel shall be demonstrated nels shown in Table 3.21. A.2 OPERAELE by performance of the shall be OPERABLE with their CHANNEL CHECK, SOURCE CHECK, alarm setpoints set to ensure C1A';NEL CALIERATION, and CHAN-that the limits of Specification NEL FL'NCTIONAL TEST operations 3.21.C.1 are not exceeded. during the modes and at the frequencies shown in Table

b. With a radioactive gaseous ef- 4.21.A.2.

fluent monitoring instrumentation channel alarm setpoint less con- '

servative than a value which will ensure that the lin.its of 3.21.C.1 are met, reset without delay to comply with Specification 3.21.A.2.a. declare the channel llJ inoperable; E dictell suspend 4ggggQ f release; or change the setpoint &

so it is acceptably conservative, k'

y c. With less than the minimum re-CL quired number of radioactive O gaseous effluent monitoring instrumentation channels sear.aaTD. take the ACTION shown in Table 3.21.A.2.

d. If the minimum number of instru-ment channels are not returned l to OPERABLE status within 31 days.

in lieu of any other_ report Y hl -

explain in chl aextC g.;g m21 Radioactive E+shem Report vny the instrument Teas not repaired in a timely manner.

L iedals blc458

e. The provisions of Definition J are not applicable. The reporting provisions of Specification 6.5.2 are not applicable.

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MOTZE ' T AELE . 11. 2. .O nt;nuec (5) A batch release is the discharce of liquid vastes af i discrete volume. Prior to sampling for analyses, eaca batch snall be isolatec and than tnoroughir mixed. '

(6) A grab sample of plant service water effluent shall be analy::ed at least once each week in accordance with Tabla ! tem

-o 2.A. In the event the radioactivity concentra-tion in a sample exceeds 3 - 10 aci/ml, or in the event the plant service water effluent monitor indicates the presence of an activity concentraticn greater than

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3 x 10 ' uCi/ml, sampling and analysis according to Table Item 2.3. shall commence and shall be performed as long as the condition persists.

(7) The principal gamma emitters for which the LLD specification will apply are exclu-sively the following radionuclides: Mn-34, Fe-3 9, Co-3 8, Co-60. ;'n-63, Mo-9 9, 2s-134, Cs-137, Ce-141, and Ce-144 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's hi her than required, the reasons shall be documented in the Scz.anual Radioactive Q ~. ca Release __?enort m_ GAaterialD $

/8) If an isotopic analysis is unava11aole, batch releases may be made for up to 14 g ys provided the gross beta / gamma concentration to the unrestricted area is <,,1 x 10 ac/mi and the sample is analyzed when the instrumentation is once again available.

(9) Analysis may be performed after release.

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

FREOUENCY NOTATION:

S = At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. A = At least once per year.

D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. R = At least once per 13 months.

W = At least once per 7 days. S/U = Prior to each reactor startup.

M = At least once per 31 days.  ? - Completed prior to each release.

0 = At least ence per 92 days. NA = Not applicable.

SA = At least once per 184 days.

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2. Temporarr, Outside Eternge .'. Temporary, Outside Eterage Tanks af ?.adicactive Liquid Tanks af Radicactive Liquid

a. In the event temporary, 3. When radicactive liquid unprotected tanks are is being added to a used outsiae to store :emporary, unprotected radioactive 11auid, outside storage tank, the i the contents of each liquid shall be sampled tank shall not exceed and analyzed for radio-10 curf es, excluding activity at least once H-3 and dissolved per 7 days.

noble zas.

5. If the quantity of radioactive material in i

a temporary, unprotected storage tank cutside exceeds 10 curies,

excluding H-3 and dissolved noble gas, immediately suspend addition of r$dioactive I

material and oegin measures to reduce the content to 10 turies or less without delav and describe the even'ts jjang6f leading to the n dition in the next C3 ... 9 7~ 21

/.

Radioactive Materials Release Report.

c. The provisiens of Definitien J are not applicable.

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ta) Analyses shall also be perf:rmed f:llcwinz :n increase as incicated ;y the gaseous release menitor :f greater than ICT in the stcacy strte release, after factoring out increases cue :: power changes or c:her :peratirnal occurrences, which could alter :he mixture of radionuclides. :Chen samples ecliected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less are analyzed, the corresponding L'_0's may be increased by a f actor e

of 10.

(5) The ratio of the sample flow rate to the sampled stream flew rate shall be known for the time period covered by each dose er dose rate calculation made da accor-dance with Specifications 3.21.C.1, 3. 21.C.2 and 3. 21.C.3.

/6) The principal gamma emitters for which the LLD specificatien will apply are exclusively the following radionuclides: Kr-87, Kr-?8, Xe-133, :~e-133m Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, 0o-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the

/Wh8gh5 analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances cause LLD's higher than required for more than 31 days, the reasons shall be documented in the .cni;r url Radioactive NQ:L&2) Release Report. >= -

(7) A quarterly composite particulate sample shall include a portion of each weeks particulate samples collected during the quarter.

(8) The noble gas continuous monitor shall be calibrated using laboratory analysis of the grab samples from A and 3 on Table 4.21.C.1 or using reference sources.

(9) A H-3 grab sample will also be taken when the reactor vessel head is removed.

This sample vill be taken at the ERP or Reactor Building vent whichever vill be representative dependent upon the head removal vaccum procedure.

FREQUENCY NOTATION:

S =

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D =

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W =

At least once per 7 days.

M =

At least once per 31 days.

Q =

At least once per 92 days.

SA =

At least once per 184 days.

A v At least once per year.

R =

At least once per 18 months.

S/U =

Prior to each reactor startup.

? =

Completed prior to each release.

"A =

Not applicable.

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' :MIT!SC C0!!DIT:CX FCR 'JERATION I SURVE L'_ASCE EEOUTREMENTS i

2.21.3 (Cont'd) 4.21 (Cont'd) informatien specified in 'O CFR i

? art 190.11(b) is included. In that event, a variance is granted until NRC  !

, Staff action on the item is complete. E. Solid Radioactive 'iaste l I

. 2. The provisions of Definition , are 1. Operating parameters and limits

not applicable. for the solidification of radio-i active vaste were established dur j

. E. Solid Radioactive Waste 'I ing preparational testing of the '

system. Radioact've waste solid-I ification shall be performed in Applicability: During solid radwaste processing. accordance with established para-2 meters and limits. In addition, Specification: every 10th batch of dewatered waste will be sampled prior to l 1. The appropriate equipment of the solidification and analyzed for j solid radwaste system shall be oper- pH.

3 ated to process radioactive waste containing liquid and liquid des- 2. Each drum of solidified or eined for disposal subject to 10 dewatered radioactive vaste will CFR Part 61 to a form that meets be inspected, prior to capping, t applicable requirements of 10 CFR insure that there is no free Part 61.56 before the vaste is standing liquid on top the shipped from the site. solid waste. j(({ggj

, 2. Suspend delivery to a carrier for 3. The Refia nuq' Radioactive Mate-l transport of any container of ri.tst-lease Report in Specifi-waste subject to Specification ca ion 6.5.1.F shall include the

', 3.21.E.1 which does not comply following information for radio-with 10 CFR Part 61.56. active solid waste shipped off-J S site during the report period:

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6.5 STATION rep 0RTIMG REOUIREMENTS 6.5.1 Poutine Reports A. Introduction - In addition to the applicable reporting requirements of Tirle 10, Code of Federal Regulations, the following identified reports shall be submitted to the individual (s) designated in the current revision of Reg. Guide 10.1 unless otherwise noted.

B. Startup Report

1. A summary report of plant startup and power escalation testing shall be submitted following:

a. Receipt of an operating license.

b. Amendment to the license involving a planned increase in power level.

c. Installation of fuel that has a different design or has been manufactured by a different fuel supplier.

d. Modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values ith design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

2. Startup reports shall be submitted within (1) 90 days following completion of the startup test program. (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If all three events are not completed, supplementary reports shall be submitted everv three months.

C. Annual Reports $ and 6.5.1.C.{

Routinerep@ortscoveringthesubjectsnotedin6.5.1.C.1 6.5.1.C.2, 6.5.1.C.3f for the previous calendar year shall be submitted prior to F n 1 of each year.

Play 1

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updaies as reguired by loCFA'50. "H(e).  ;

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.5.1.C (Cont'd)

1. A tabulation on an annual basis of the number of station, ut 11i ty and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and j ob functions, if e.g. , reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty Iunctions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less t.han 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received

from external sources shall be assigned to specific major work functions.

2. A summary description ot facility changes, tests or experiments in accordance with the requirements of 10CFR50.59(b). %

3. Pursuant to 3.8.A, a report of radioactive source leak tes.L ing.

This report is required only if the tests reveal the presence of 0.005 microcuries or more of removable contamination.

4 Documentation of all challenges to relief valves or salety valves.

D. Monthlv Quera t i tut Report Routine reports of operating statistics, shutdown experience, .ind a narrative summary of operating experience relating to safe operation of the facility, shall be submitted on a monthly basis in the manner specified by 30CFR50.4 no later than the 15th of each month fullowing the calendar month covered by the report.

E Annual Radiolocical Environmental Report

1. Routine radiological environmental reports covering ihe surveillance activities related to the Station operation during the previous calendar year shall be submitted to the NRG bef ore May 1 of each year.

2. The Annual Radiological Envirorunental Report :.ha l l i nc l uile the following:

a. A summary of doses to a Member of the Public utfsite due to Cooper Station aqueous and airborne radioactive effluents, calculated in accordance with methods compat ible with the ODAM.

b. A summary of the results of the land use census respii red in Specification 4.21.F.2.

1/ This tabulation supplements the requirements of 520.407 of 10CrR rart 20.

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j 6.5 i.E (cont'd)

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c. Stimmarir.ed and tabulated results in the format of Table 6.5 1-of- analyses of samples required by' the radiological' environmental monitoring program, and taken during t he-report period. In the event that some result s are nor avnllable for )

i ncl iis i on with-the 3 eport , the.iepor chalI ho nnhmittod noting nnd explaining the reasons for tbo minning rennits. ;I The mi ssing data sha ll he snhmi t.ted an soon an possible in -]

a supplementary teport. l l

d. A. summary description _ of the ' radiological env i ronment a l l

-- moni toring program lueloding nny changem; a map ni all nampiing locatinun keyed-1o a tahic r,i v i t en d i n i .ince., and A['j7 directions from t.be reactor; and t.hn results of part leipat.lon d 'in the inter-inhorntory Comparison Progrnm. respii rcel by i SpeeiflenLion 3.2I.G 1

.[' .O f l F C

.@ Radinactive !!ateria Reicase Repott- J j

l. A repore of rndionctivehrerints released' f rom ihe Sinrinn anring the tireceding Q: --

SQ shall be i submi tted to the-MRC i (im

- 0o each yea O.L .)

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2. E r- c.D Radl onc tive finterin t Re ease Report. nhall includo the g-foilowing:  ;

kh0YO a. A summnry by ca l enti?ir <!H arter of the ynnut i t inn n l. )

h-- -- radioactive liquid and gnseous effluents relennert Irom thn- 1 Station. The data- should be reported in the inimat recommended'in Regulatory Guide 1.21, Appendix g. Tables 1 '!

and 2.

h. A summary of ' radioactive solid waste shippeel from- the Station, i u c I u rli n g i n f o rin n t _i o n unmed in-Specification 4.21.E.3. ~g]'

l c A summarv of merenrologicali rdntn co l lec t ed du r i ne. rho venr I shall be i nc l ueled i n t he(Sc --- ; .. J Repoit submitied M I

k $ .- -- '

_Qof each year.

d. A list and brief description of each unplanned relenne of' gnscons nr lignld rndionceive cf fluent that cannes a limit i

in Specification 3.2.1.B.1.a. 3.21.B.2.a. =E?l.C.I.n.

3.21.C.2.a, or 3.21.c.2.a to be exceeded. ,

c. Calculated of fst re dose to homnns resni t ing from the relense ni el i Inent n and their nuhncquent dinpeieinn in the atmosphere reported in accordance vi th Regulatorv Gnido 1.21.

6.', I.c Core npernt inn I.imi t n Report.

Core nperating limi ts shall he established and documented in t he Cnro nperatine, f.imit s Report prinr t.o ench reload cycle, or prior to nny remaining port ion ni a reinael cycle, for t.be following:

n. The Average Planar 1,inear llent Generat ion Rates ( API.IlGH ) for-l Mpecifleation 1.ll.A.

f it cho u be not.cr i t this d a as not n lv heen , ble to in i int rict t t hin i 6n a n .n an , i i,n i e x t e,, ,,,i i n . ty, ally h.cn re tired rom ne mu . c- c ro i e,. i

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lim ir,e s

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s. i ?rocess Control Program (?CP) '

l 6.6.1 I The PCP shall be a manual detailing the program of sampling.

analysis and for=ulation determination by which SOLIDIFICATION of radioactive waste from liquid systems is assured consistent  !

vith Specification 3.21.E and the surveillance recuirements of these Technical Specifications. l i

6.6.2 District Initiated Changes  !

i A. Shall_b ub=itted to the Commie ion by inclusion in the i h ai M . pal Radioactive Material Release Report for the period- ,

in which the change (s) was made effective and shall contain: '

Ap(1E{

P 1. Sufficiently detailed information to totally support the .(

rationale for the change without benefit of additional or  ;

supplemental information;

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2. A determination that the change did not reduce the overall -)

l conformance of the solidified waste product to existing  !

criteria for solid wastes; and -

1

3. Documentation of the fact that the change has been reviewed i and found acceptable by the SORC.

[

B.

Shall become effective upon review and acceptance by the SORC.  !

6.7 Of f site Dose Assess =ent Manual (ODAM) l i

l 6.7.1 The ODAM shall describe the methodology and parameters to be used in th= calculatica of offsite doses due to radioactive gaseous and'11guid effluents and in the calculation of gaseous.and liquid effluent monitoring instrumentation alarm / trip setpoints.' consistent with the applicable LCO's contained in these Technical Specifications. The ODAM also describes the Environmental Radiation Monitoring Program.

6.7.2 District Initiated Chances ^

A. Shall_be submitted to the C . mission by inclusion in the @

l a dm a) Radioactive Material Release Report for the period in which the change (s) was =ade effective and shall contain:

i hMO 1.

! Sufficiently detailed information to totally support the.

l rationale for the change without benefit of' additional'or-supplemental information.

Information submitted should consist of a package of those pages'of the ODAM to be changed with each page numbered and provided with a signed approval and date box, together with appropriate. analyses of evaluations justifying the change (s).

2.

A deter =ination that the change vill not reduce the' accuracy-or reliability of dose calculations or setpoint determinations.

3. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

B.

Shall become effective upon' review and acceptance by the SORC.

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1 APPENDIX "B" l

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TABLE OF CONTENTS (Cont'd.)

Pare No.  ;

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS <

6.2 Review and Audit 220  :

6.2.1.A Station Operations Review Committee (SORC) 220  ;

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A.1 Membership 220 A.2 Meeting Frequency 220  !

A.3 Quorum 220 A.4 Responsibilities 220-A.5 Authority 221 ,

A.6 Records 221 1 A.7 Procedures 221 l

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1 6.2.1.B NPPD Safety Review and Audit Board (SRAB) 222  !

B.1 Membership 222  !

B.2 Meeting Frequency 222 B.3 Quorum 222 B.4 Review 222 B.5 Authority 223 B.6 Records' 223 B.7 Audits 223 6.3 Procedures and Programs 225 6.3.1 Introduction '225 6.3.2 Procedures 225 6.3.3 Maintenance and Test Procedures 225 j 6.3.4 Radiation Control Procedures 225

.A High Radiation Areas 226 6.3.5 Temporary Changes 227 6.3.6 Exercise of Procedures. 227 6.3.7 Programs 227 )

.A Systems Integrity Monitoring Program 227

.B Iodine Monitoring Program 227 L

.C Post-Accident Sampling System (PASS) 227 6.4 Record Retention 228 6.4.1 5 year retention 228 6.4.2 Life retention 228 6.4.3 2 year retention- 229 6.5 Station Reporting Requirements 230 6.5.1 Routine Reports 230 j .A Introduction 230 i .B Startup Report 230 Annual Reports

.C .230

.D Monthly Operating Report 231

.E Annual Radiological Environmental Report 233

.F Annual Radioactive Materials Release Report 232- l

.G Core Operating Limits Report 232

-iv-

LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMEh7S 3.21 ENVIRONMENTAL / RADIO 1DGICAL EFFLUENTS 4.21 ENVIRONMENTAL / RADIOLOGICAL EFFLUENTS A. Instrumentation A. Instrumentation

1. Liquid Effluent Monitoring 1. Liquid Effluent Monitoring Applicability: As shown in a. Each radioactive liquid.

Table 3.21.A.1. effluent monitoring instrumentation channel shall Specification: be demonstrated OPERABLE by performance of the CHANNEL

a. The radioactive liquid CHECK, SOURCE CHECK, CMNNEL .

effluent monitoring CALIBRATION and CHANNEL instrumentation channels FUNCTIONAL TEST operations-

shown in Table 3.21.A.1 shall during the modes and at the l be OPERABLE with their alarm frequencies shown in l and trip setpoints set to Table 4.21.A.l.

ensure that the limits of 3.21.B.1 are not exceeded. b. Radioactive liquid. effluent monitor alarm and trip

, b. With a radioactive liquid setpoints shall be determined- .;

! effluent monitoring in the manner described in the.

l instrumentation channel alarm ODAM, and trip setpoint less conservative than required, reset without delay to meet l Specification 3.21.A.l.a.

j suspend the release of -

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radioactive liquid effluents

! monitored by the affected  ;

! channel, declare the channel '

inoperable, or change the  !

setpoint so it is acceptably conservative. s

c. With less than the minimum required number of -

radioactive liquid effluent l monitoring instrumentation i j channels OPERABLE, take the ACTION shown in i

Table 3.21.A.l.

d. If the minimum number of

' instrument channels is not returned to OPERABLE status within 31 days, in lieu of any other report, explain in the next Annual Radioactive Materials Release Report why the instrument was not repaired in a timely manner.

e. The provisions of Definition J are not applicable. The reporting provi s ionr o f Specification 6.5.2 are not applicable. I i

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENTS l 3.21.A (Cont'd) 4.21.A (Cont'd)

2. Gaseous Effluent Monitoring 2. Gaseous Effluent Monitoring Applicability: As shown in a. The setpoints shall be Table 3. 21. A. 2. determined in accordance with  ;

the method described in the Specification: ODAM.  ;

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a. The radioactive gaseous b. Each radioactive gaseous effluent monitoring effluent monitoring instrumentation channels instrumentation channel shall shown in Table 3.21.A.2 shall be demonstrated OPERABLE by-be OPERABLE with their alarm performance of the CHANNEL setpoints set to ensure that CHECK, SOURCE CHECK, CHANNEL the limits of Specification CALlBRATION, and. CHANNEL 3.21.C.1 are not exceeded. FUNCTIONAL TEST operations during the modes and at the

b. With a radioactive gaseous frequencies shown in effluent monitoring Table 4.21.A.2.

instrumentation channel alarm setpoint less conservative than a value which will ensure that the limits of j 3.21.C.1 are met, reset I without delay to comply with l Specification 3.21.A.2.a, declare the channel l inoperable; IMMEDIATELY suspend release; or change the setpoint so it is acceptably conservative.

l c. With less than the minimum required number of radioactive gaseous effluent l

monitoring instrumentation channels OPERABLE, take the l

ACTION shown in Table 3.21.A.2.

d. If the minimum number of instrument channels are not l returned to OPERABLE status

! within 31 days, in lieu of any other report, explain in the next Annual Radioactive Materials Release Report why l

the instrument was not repaired in a timely manner.

e. The provisions of l

Definition J are not applicable. The reporting previsions of Specification 6.5.2 are not applicable.

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l-l NOTES FOR TABLE 4.21.B.1 (Continued)

(5) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed.

(6) A grab sample of plant service water effluent shall be analyzed at least once each >

week in accordance with Tabge Item 2. A. In the event the radioactivity concentration in a sample exceeds 3 x 10~ pCi/ml, or in the event the plant service water effluent  :

monitor indicates 6

the presence of an activity concentration greater than  !

3 x 10 pCi/ml, sampling and analysis according to Table Item 2.B. shall-commence and shall be performed as long as the condition persists, t

(7) The principal gamma emitters for which the LLD specification will apply are. ,

exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,  ;

Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the 5 reasons shall be documented in the Annual Radioactive Materials Rele.ase Report. l [

(8) If an isotopic analysis -is unavailable, batch releases may be made for up to 14 days provided,7 the gross beta / gamma- concentration -to the unrestricted area is s 1 x 10 pc/ml and the sample is analyzed when the instrumentation is once again-available.  ;

(9) Analysis may be performed after release.

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

FREQUENCY NOTATION:

S - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. A - At least once per year.

D - At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. R - At least once per 18 months.  ;

W - At least once per 7 days. S/U - Prior to each reactor startup. '

M - At least once per 31 days. P - Completed prior to each release.

Q - At least once per 92 days. NA - Not applicable.

SA = At least once per 184 days.

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f j LIMITING CONDITIONS FOR OPERATION auRVEILLANCE REOUIREMENTS ,

)

3.21.B (Cont'd) 4.21.B (Cont'd) l l

3. Temporary, Outside Storage 3. Temporary, Outride Storage Tanks of Radioactive Liquid Tanks of Radioactive Liquid

a. In the event temporary, a. When radioactive liquid unprotected tanks are is being added to' a used outside to store temporary, unprotected radioactive liquid, the outside storage tank, the contents of each tank liquid shall be sampled ,

shall not exceed and analyzed for 10 curies, excluding radioactivity at least H-3 and dissolved noble once per 7 days, gas.

i

b. If the quantity of radioactive material in a temporary, unprotected storage -

tank outside exceeds ~

10 curies, excluding H-3 and dissolved noble. '

gas, immediately suspend addition of  ;

radioactive material and begin measures to  ;

reduce the content to ,

10 curies or less without delay and i describe the events leading to the condition in the next l Annual Radioactive Materials Release Report.

c. The provisions of  ;

Definition J are not applicable.

l

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- - . - - - - . . - , , _ _ . . - . __ _ , . . . . . . . . m -. . . . . . ,

(4) Analyses shall also be performed following an increase as indicated by the gaseous release monitor of greater than 50% in the steady state release, after factoring out increases due to power changes or other operational occurrences, which could alter the mixture of radionuclides. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less are analyzed, the corresponding LLD's may be increased by a factor of 10.

(5) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.21.C.1, 3.21.C.2 and 3.21.C.3.

(6) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances cause LLD's higher than required for more than 31 days, the reasons shall be documented in the Annual Radioactive Materials Release Report. l (7) A quarterly composite particulate sample shall include a portion of each weeks particulate samples collected during the quarter.

(8) The noble gas continuous monitor shall be calibrated using laboratory analysis of the grab samples from A and B on Table 4.21.C.1 or using reference sources.

(9) A H-3 grab sample will also be taken when the reactor vessel head is removed. This sample will be taken at the ERP or Reactor Building vent whichever will be representative dependent upon the head removal vacuum procedure.

FREQUENCY NOTATION:

S -

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D -

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W -

At least once per 7 days.

M -

At least once per 31 days.

Q -

At least once per 92 days.

SA -

At least once per 184 days.

A =

At least once per year.

R -

At least once per 18 months.

S/U -

Prior to each reactor startup.

P -

Completed prior to each release.

NA -

Not applicable.

l l

l l

l l

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~

• p LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.21.D (Cont'd) 4.21 (Cont'd) information specified in 40 CFR Part 190.11(b) is included. In that event, a vaciance is granted until NP.C Staff action on the item is complete.

2. The provisions of Definition J are not applicable.

E. Solid Radioactive Waste E. Solid Radioactive Waste Applicability: During solid 1. Operating parameters and radwaste processing. limits for the solidification of radioactive waste were Specification: estab1ished during preparational testing of the

1. The appropriate equipment of system. Radioactive waste the solid radwaste system solidification shall be shall be operated to process performed in accordance with radioactive waste containing established parameters and liquid and liquid destined limits. In addition, every for disposal subject to 10 10th batch of dewatered waste CFR Part 61 to a form that will be sampled prior to meets applicable requirements solidification and analyzed of 10 CFR Part 61.56 before for pH.

the waste is shipped from the site. 2. Each drum of solidified or dewatered radioactive waste

2. Suspend delivery to a carrier will be inspected, prior to for transport of any capping, to insure that there container of waste subject to is no free standing liquid on Specification 3.21.E.1 which top of the solid waste.

does not comply with 10 CFR Part 61.56. 3. The Annual Radioactive Materials Release Report in Specification 6.5.1.F shall include the following information for radioactive solid waste shipped offsite during the report period:

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6.5 STATION REPORTING REOUTREMENTS l 6.5.1 Routine Reports A. Introduction - In addition to the applicable reporting requirements of ,

Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the individual (s) designated in the current revision of Reg. Guide 10.1 unless otherwise noted.

B. Startup Report

1. A summary report of plant ctartup and power escalation testing shall be submitted following:

a. Receipt of an operating license.

b. Amendment to the license involving a planned increase in power level.

c. Installation of fuel that has a different design or has been manufactured by a different fuel supplier.

d. Modifications .that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

The report shall address each of'the tests identified in the FSAR and rhall include a description of the measured values of the opetating conditions or characteristics obtained during the test program and a comparison of these values with_ design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any j additional specific details required in license conditions based cn other commitments shall be included in this teport.

1

2. Startup reports shall be submitted within (1) 90 days following l completion of the startup test program, (2) 90 days following )

resumption or commencement of commercial power operation, or  !

(3) 9 months following initial criticality whichever is earliest.

If all three events are not completed, supplementary reports shall be submitted every three months.

C. Annual Reports Routine reports covering the subj ects noted in 6. 5.1.C.1, 6.5.1.C.2, 6.5.1.C.3 and 6.5.1.C.4 for the previous calendar year shall be submitted  ;

prior to May 1 of each year, j l

l l

i

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1 r u s l l

6.5.1.C (Cont'd)

1. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure ,

according to work and job functions,1/ e.g. , reactor operations and surveillance, inservice inspection, routine maintenance,.

special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be  !

estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be -assigned to specific maj or work f

functions.

l .

2. A summary description of facility changes, tests or experiments in accordance with the requirements of 10CFR50.59(b). -This_ report may be submitted annually or along with . the Updated Safety Analysis Report (USAR) updates as required by 10CFR50.71(e). ,

3. Pursuant to 3.8.A, a report of radioactive source leak testing.  !

This report is required only if the tests reveal the presence of 0.005 microcuries or more of removable contamination.  :

4. Documentation of all challenges to relief valves or safety valves.

D. Monthly Operatine Report  !

Routine reports of operating statistics, shutdown experience, and a narrative summary of operating experience relating to safe operation of  :

the facility, shall be submitted on a monthly basis in the manner specified by 10CFR50.4 no later than the 15th of each month following the  ;

calendar month covered by.the report. '

E. Annual Radiological Environmental Report

1. Routine radiological environmental reports covering the ;

surveillance activities related to the Station operation during the previous calendar year shall be submitted to the NRC before May 1 of each year. 4 1

2. The Annual Radiological Environmental Report shall include the '

following:

I

a. A summary of doses to a Member of the Public Offsite due to Cooper Station aqueous and airborne radioactive effluents, I calculated in accordance with methods compatible with the ODAM.

b. A summary of the results of the land use census required in Specification 4.21.F.2.

i 1/ This tabulation supplements the requirements of $20.407 of 10CFR Part 20.

l

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]

s ** ,?

6.5.1.E (Cont'd) j

c. Summarized and tabulated results in the format of l Table 6.5-1 of analyses of samples required by the radiological environmental monitoring program, and taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

d. A summary description of the radiological environmental monitoring program including any changes; a map of all sampling locations keyed to a table giving distances and ,

directions from the reactor;. and the results of participation' in the Inter-laboratory Comparison Program, required by Specification 3.21.C.

F. Annual Radioactive Materials Release Report l

1. A report of radioactive materials released from the Station during the preceding year shall be submitted to the NRC by May 11 of each l year.

2. The Annual Radioactive Materials Release Report shall include the l following:

a. A summary by calendar quarter of the quantities of radioactive liquid and gaseous effluents released from the Station. The data should be reported in the format recommended in Regulatory Guide 1.21, Appendix B, Tables 1 and 2.

b. A summary of radioactive solid waste shipped from the Station, including information named in Specification 4.21.E.3.

c. A summary of meteorological data collected during the year ,

shall be included in the Annual Report submitted by May 1 of l each year.

d. A list and brief description of each unplanned release of gaseous or liquid radioactive effluent that causes a limit in Specification 3.21.B.l.a. 3.21.B.2.a. 3.21.C.l.a, 3.21.C.2.a, or 3.21.c.2.a to be exceeded.

e. Calculated offsite dose to humans resulting.from the release of effluents and their subsequent dispersion in the atmosphere _ reported in accordance with Regulatory Guide 1.21.

6.5.1.G core Operatine Limits Report Core operating limits shall be established and documented in the Core Operating [

Limits Report prior to each reload cycle, or prior to any remaining portion of '

a reload cycle, for the following. j

a. The Average Planar Linear Heat Generation Rates (APLHGR) for j Specification 3.11.A.

]

l l

1

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~.

P 1

o * ,t 6.6 Process Contrgl Procram (PCP) l 6.6.1 The PCP shall be a manual detailing the program of sampling, analysis and l formulation determination by which SOLIDIFICATION of radioactive waste from  !

liquid systems is assured consistent with Specification 3.21.E and the j surveillance requirements of these Technical Specifications.

6.6.2 District Initiated Chantes l l

A. Shall be submitted to the Commission by inclusion in ' the Annual i Radioactive Materials Release Report for the period in which the change (s) was made effective and shall contain:

t 1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental ,

information;

2. A determination that the change did not reduce the overall  !

conformance of the solidified waste product to existing criteria for solid wastes; and l 3. Documentation of the fact that the change has been reviewed and l l found acceptable by the SORC.

I B. Shall become effective upon review and acceptance by the SORC. ,

i 6.7 Offsite Dose Assessment Manual (ODAM) i 6.7.1 The ODAM shall describe the methodology and parameters . to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents l

and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. The ODAM also describes the Environmental Radiation Monitoring Program.

6.7.2 District Initiated Chances ,

l A. Shall be submitted to the Commission by inclusion in the Annual Radioactive Materials Release Report for the period in which the change (s) was made effective and shall-contain:

1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental  !

information. Information submitted should consist of a package of i those pages of the ODAM to be changed with each page numbered 'and I provided with a signed approval and date box, together with appropriate analyses of evaluations justifying the change (s).

2. A determination that the change will not reduce the accuracy or j reliability of dose calculations or setpoint determinations, j l

3. Documentation of the fact that the change has been reviewed and found acceptable by the SORC.

B. Shall become effective upon review and acceptance by the SORC. l 1

l

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_ ,