ML18043A955

From kanterella
Jump to navigation Jump to search
Advises That Propesed Amends in 781113 & 790312 Submittals Do Not Cover Items of Model Radiological Effluent Tech Specs Sent to Util in .Forwards Request for Addl Info & Guidelines.Revisions Should Be Submitted by 790914
ML18043A955
Person / Time
Site: Big Rock Point, Palisades  File:Consumers Energy icon.png
Issue date: 08/08/1979
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Bixel D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 7908210068
Download: ML18043A955 (13)
v • d • e


Text

......

I AUG s*

Docket N.os. 50-~5l *,

-~ 50- 5~~

Mr. Qav1d Bixel

.~

Nucl'ear licensing Adm1n_1strator

  • Consumers Power *comp*ahy 212 West Michigan Avenue Jackson,.:-Mi ch1 g'an - 49201 -

Dear Mr. Bixel:

.,'/.'..

I.'

1:

i I*.

~.-1 In your letter dated January.15; 1979, _you indicated that* on*

November 13~ f978 Consumers Power Company (CPC) subrnitte_d a.license amendment application for Big Rock Point in resp~ns_e to our July 11, *

  • 1978 request.

You, fu,rt~er indfCat~ that CPC has reviewed their*/

November 13, 1978 submittal and concluded that no changes were necessary to incorporate the addftiona.1 iss_ues discussed -*in our November 15, 1978 letter pr,oviding gu1dance on.Radiologi'cal Effluent

  • Technical*SpeCffications. *.

~

.In a letter from o *. lfaffman dated Marc*h 12, 1979,.you*. fnd1cat~d that on June -4, 1976 CPC submitted a 1 iCense am~ndment app li c~tiori for *

You further'*

indicated that you had reviewed. yQur June 4, 1976 su.bmittal and * -

conc;l~1ded that although.the dose pathway had changed for airborne*

~ffluents {for which an *.update was attached to the* March 12, 1979 letter). the objectives of the proposed chimge dated* June--4, 1976 *

  • remained the same.

The March 12, J979 letter stated that the proposed c,hange fn~orporated requirements* requested by our July. 1J,- *1978 letter, but made. no re f~rence to our. November 15-, 1978 1 etter *. ~ *.* * :

Iri the letter from B. Grime~ to all Power Reactor Licensees dated November 15, 1978, we fnd*1cated. that the forniat for the revised

  • .Technical* Specifications may be that presently used for your existing* -

-* Appendix A Technical Spedficat1ons provide_d al 1 applicable-areas of,, 2 the model Technical Speciffc~tions a_re.accepta_bl_y address.ed..

~/

_&q.

'1908210:06~ '.

l t..

I w::::: l****::::::::::: :::: * : *t~*:.*....-.*.*.*.**.*.....-.*.*:.:.. -............ *.:*_,_.. _*:*.*.::.. ~::::::: *:** *** ~*** *** ::. J::::::::::::::::::::::::O::. '::*.::::::*,:

DA:Tll~

QC J.IOBM 318 (9*76) NRCM 0240

  • U.S. CIOVUR.NMllNT PRIN'?"_ING Ofl',..ICU:: t971 *IOI* 7*9 *.

---*-~--

~

!.'.:.\\

Mr. David Bixel

  • AUG 8 1979 We h~ve review~~. your:: November 13, 01978 submftt~l for Big Rock Point

. and the March 12~;: 1:.979.~~ubmtttal\\ for PaHsades and fitid that these proposed amendments are\\*not resp*cmsive to our request since they do not cov.er all the:.Jtems contained 1n the model Radiological Effluent Technical Spedfi<;ations *:forwarded to you in our letter of November.15,

.1978.

1*

- lo t'his.. letter 'lists some of the major items contafried in

. the model Radiological Effluent TechniGal *Specifications *and* not acceptably addressed in your submittals *.

".*., By letter 1of July 18,, 1979, we provided you with the latest *revisions

.\\ \\, }; to !110del Rad,1o*log1cci~i'Effluent Technical 'Specifications.

We request

-.~.)';c{ tha*t yo~ s'tbfuit_revi~ed R~~iologkal Effh~ent Technical Specif~cations

.';/

/

1 which __.acceptably address all applfcabl_e ar~as of our model and.

/T specifically address11 those_,: items listed i.n Enclosure 1 to this letter.

He request _that you~: revisions be submitted by Septem~er 14, 1979.

\\

~

~-

Shouldyou need any additional guidance, we are available to meet with you.

Enc 1 osures: *

1. *Request for Additional*

! Inronnation

2.

ODCM Contents

3.

PCP Contents.

  • cc 'w/enclosur.es:.*

See next ~ge Sincerely, a.Orriginal *Sig.lied by

_ Richard D. Silv~r~*.:.

. ~-~

Dennis L. Ziemann,. 'Chief -

Operating Reactors -Branch f12

  • Division of *operating Reactors*

DISTRIBUTION:

Docket 50-l 55

  • 50-255 NRC PDR.

Local PDR ORB#2 ROG NRR ROG.

DEisenhut RVollmer* *

  • BGrimes WGarronill JMiller
  • . LShao
  • TCarter.

liJRussel l OELD OI&E(3)

OLZ:iemann RSilver HSmith PVJagner RBangart.

JRBuchan~n TERA ACRS(l6) 0,.,.,c.... DOR*:*ORB#2 :......... ooR*:-srss.. ;..... DOR*~ORB#2.....

I euR"~... *;;. *R5i~ver*:*s'h.........p.tya~fl-el"'*........ Dl:l;*emarm............ _........................................................ '.........

DATB.,_'. -8/.'J.f ].9'.... -* '.'. '. g.J,g.J:].g.......... Sl -K*J.7*9*......... :. '.;. '~'....... '.'. -'..... -..... '..... -'.... '-* '. - '. .. '. '.' --~...

-,(

IGC PORM 3i8 (9*76) NRCM 024e.

  • U,G, GOVl!RNMGNT l'AINTING o...... ICll: 1-.71 - 1115 - 719

M.r. David* Bixel cc M. 1. Miller, Esquire Isham, Lincoln & Beale Suite 4200

  • one First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Con~umers Power Company 212 West Michigan Avenue

.Jackson, Michigan 49201

. Judd L. Baco~, Esquire Consumers Powe~ Company 212 West Michigan Avenue

  • Jackson, Michigan 49201 Myron M. Cherry, Esquire.

Suite 4501 One IBM.plaza Chicago, Illino~s 60611 Ka 1 amazoo *Public Library 315 South Rose Street *

,Kalamazoo, Mi chi gari 49006

~unton & Williams George C. Freeman, Jr., Esquire P *. o. Box 1535 Richmond, Virginia 23212 Peter.*w. Steketee~ Esquire 505 Peopl~s Building G*rand Rapids, Michigan 49503 Charlevoix Public Library 107 Cli*nt.on Street Charl~votx, Michigan 49720 Ms. Mary P. Sinclair

~reat. Lakes Energy Alliance 5711 Surrimerset Drive

"""'-.. - ----.---;-* ~ August 8, 1979

....... _ ___..., *--.-:.!!...- *---......... ~.. -- * -*-*--* *-'*

.9.......,,._, -.**.

    • --- --* -:***-:-*----*** ~~ -~--- -* ---

IINl:LOSllRE I REQUEST FOR ADDITIONAL INFORMATION BIG ROCK POINT AND PALISADES PLANTS RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS

  • Listed below are some of the major items contained in the model Radiological Effluent Technical Specifications and not acceptably addressed in the CPC submittals. *
1)

Proposed specifications that address the maintenance and use of radwaste treatment equipment {liquid, gaseous and solid) pursuant to 10 CFR 50.36a.

2)

Proposed specifications that address the action to be taken when radwaste treatment equipment and instrumentation becomes inoperable.

3)

{See Enclosure 2 on ODCM contents).

4)

Proposed specifications that addres*s-sollcfificafion of wet solid r~dwaste and the packaging of dry sol id radwaste.

To assure

. adequate sc>>li cHfi cation procedures, ii Proc-es*s Control Program is to be provided.

(See Enc 1 osure 3 on PCP con tents)..

5)

Figures that* define the site boundary for radioactive liquid and gaseous effluents.

. 6)

Details on the site meteorological station providing data used in determining dose impact to real individuals.

7)

Proposed sampling and analysis program for all site effluent release.*

points having the potential for radioactive *releases, the sampling.

and analysis frequency, the type of analysis, and the nuclide LLD capability.

8)

The method to be used in calculating alarm and :trip set points on.

radioactive effluent monitoring systems in the ODCM.

-.~*-.-- *:-. -- ----*

ENCLOSURE 2 Section 1 - Set Points Provide the.eqliations and methodology to be used at the station or unit*

for each alarm and trip set point on each effluent release point according to the Specifications 3.3.3.8 and 3.3~3.9. The instrumentation for each alarm arid trip set point, including radiation monitoring and sampling systems and effluent contrbl features, should be identified by reference to the FSAR (or final Hazard Summary).

This infor~ation should be con-sistent with the recommeridations of Section I of Standard Review Plan 11.5,

  • NUREG-75/087, (Revision 1). If the alarm and/or trip set point value is va~i~ble~ provide the equation to determine the set point val~e to be use.d, 'based on actual _re lease condit iO~s, tllat. wil 1 assure that the *Speci""'

fi~ati6n i~ met at e~ch release point; ~nd provid~ the value to be used when releases are not in progress. If dilution or dispersion is used,'..

srate the on-site equipment and measurement method used during release,*

the site related parameters and the set points used to assure that the Specification is met at each ielease point. The fiied and varia&le s~t_points should consider the radioactive effluent to have a radio-:

. nuclide; distribut1on reptesented. by normal and antiCipated operational occurrences.

Se~tion.2 - Liquid*Effluent Concentration Provide the equations and methodology to be used at the station or unit

  • Tilel"orm~tl'Or~e ODCM.is. left up to the licensee and may be simplified by tables and grid_printout. Each page should be numbered and indicqte the facility app~oval and effective date.

... r...

LNCLllSlHH: /

for each liquid release point according to.the Sp~c~fic~tion 3.11.1.1;

  • For systems with continuous or b~tch releases, and for systems designed

. to monitor and control both continuou~ and batch releases, provid~ the

~~si.Jmptions.and parameters to be used to compare the output-of the mon*itor with the liquid concentration specified. State the limitations

  • . for combined discharge~- to the same release point.* In addition, describe*

the method_ and assumptions for obtai~ing *representative samples from each batch and the use of prevHrus post-release analyses or composite sample analyses to meet the Specification.

Section 3 - Gaseous Effluent Dose Rate Provide the etjuations and methodology to be used at the station of unit (o~ ~~ch gaseous release point according to. Specificaticri 3.11.2.1.

Con-sider the various pathways, release point ~levations, site related para-meters and radionuclide contribution to the dose impact limitation *.

Provide the equatioris and assumptions used, stipulating the pathw~y,

.receptor location and receptor age.

Provide the dose factors to be used for, the identified radionuclides released. Provide the annual average dispersion values (X/Q and D/Q), the site specific parameters and release point elevations.

s-ec*tiori 4 - Liquid Effluent Dose~,
  • Provide. the equat.ions and methodolo,gy to be used at the station or unit
for each liquid release point according to the dose objectives given in.

Specification 3;11:1.2.

The section should describe how the dose contri-bti1i6ns are to be calculated for the various pathways and release points,

>~*. -~~*--

.*. ~-----~-

... :-:-*,----:*---~-- '-.:7'---**--****-*---.. --* --..-

. -~-*------

  • -*:_---~---:-:.

- 3**-

ENCLOSURE 2 the_equation.s and_ a~sumptions to be used, the sHe spec Irie pd1*<t111cter~

to be measured and used, the receptor locatfon by direction** and. distance*~

and the method of estimating and updating cumulative doses due to liq.uid

  • re1eases.

The dose factors, pathway transfer factors, pathway usage factors, and dilution factors for the points of pathway origin, etc.,

should be given, as.well as receptor age group, water and food consump.:..

tioh rate and other factors assumed or measured.

Pr6vide the ~ethod of determining the dilution *f~t:tor at the discharge during any liquid effluent

  • re lease and any~s i te speti fi c parameters used in these determinations.

S~ctiori ~

Gaseous Effluent Dose *

  • Provide the equations and methodology to be used at the station or uilit-

.. for e:ath gaseous release point according'to. the dose objectives giv*en i.n SpeC:ifications 3.11.2.2 and J.11.2.3. The section should describe how the. dbse contributi ans are to be calculated for the vari*ous. pathways and retease. points, the equations and. assumptions to be used, the site specific.

parameters-to be measured and used, the receptor location by direction~.. *

.,and dist~nce, and the method to be used for estimating and updating cumula*

.*ti~e doses due to gas~ous releases.

The loca.tion)direction and d'istance.

  • to the; ~earest residence, cow, goat, meat animal, garden, etc., should
be**gi~en~ as well as receptor age group, crop Y
ield, grazing time and*".

).ther *factors ass.urned or me_asured __ Pro.v_ide *t~e method of determinfog : *

~iip~~~ion values (X/Q and D/Q) fo~ relea~es and any site specific par~~

meters and relE.~ase point elevations used in these determinations.

,=.

. -~- - -~-------,c-.--1

  • I I i

. i i

,-~~**:*..

~: ~.~*-~.~~.~~**-----... *: *-:*-. --, -_,..,-,.-r-,,.,

.... <... *.*... *._:, ~-.

4-. - -. -- -~--":~~:-~ ---~----~-* - -.*.

.ENCLOSURE*2

. ~.....

l..

I

~:

I l '*

  • i
  • .. {*_
  • Sec_tion 6 - Pn1jected Doses Fur 1 iyuiJ c111d

~.i~1.*ous riHh*Jasle treatment systems. provide the rnr~thod of projecting doses due to effluent releases for the normal and alter~

. *. *.*.. nate pathwaY.s of treatment according to the s'pecifications 1 describing the components and subsystems to be us~d

  • Section 7 - Operability of Equipment Provide a flm'I diagram(s) <:refining the treatment paths and the components of th~ radioactiye liquid, gaseous an~ solid waste management systems that at~*to be.maintained and used, p~rsuant to 10.CFR 50.36a, to meet Technieal Specifications 3.11.1.3, 3.11.2.4 *and 3~1L3.1.. Subcomponen,ts

. of packaged equipment.. can be identified by a *1 ist. For operating reactors

.\\;Jhose<c'onstruction permit applications were-fi,led prior to January 2,'* 1971, the f16.w diagram(s) shall be_ consistent with the information provided in

~onformance with Section V.B.1 of Appendix I to 10 CFR Part 50. *For OL

  • .-applications whose construction perm_its were *filed after January 2, 1971,
  • the f_low diagram(s) shall be consistent with. the information provided_.*

in Chapter 11 rif th~ Final Safety Analysis Report (FSAR} _or amendments

.theretQ* *.

Sec.ti on_,? - Sample Locat i6ns

. ~ ':

.. Pro.vi de.a map of the Radiologica1*£nvironmenta:l Monitoring S.ample Loc:a-tion~- iodicating the nu~~ered samp~!ng locations given in.Table 3.12~1~

  • .Further clarificatiqn on these numbered sarnpling locations can be provided 1*

_..,.-_,_*.;:.. -~ ~:~- _

--- -- A I

  • --~-_,........ **--.

~---.. - -.

--~--

e-.-~

.. ---:**---**--~*-~-.~----=~---*

  • I I*

!f ::*.*.

.:1 _

  • 1**
  • .1.'*

I\\.*.

~-*.

.,'j.

. :s* *.'

  • 1..

.. -.}..

  • ... - s** -*.

ENCLOSURE 2 by a* list, -indicating -the direction and distance from the center of the

  • building complex of Jhe unit or station, and may include a discriptive name for identification purposes.

-~

...,.~. -:**--'~*-----. -----: *****--9-*** *--'"'""~.-,~~,.~*-*---.---7*--*----*-e-------*--*-"----.. --.. --:*

  • ~.:'.
    • ~ "

ENCLOSURE 3

. '~.'*'

'r.

I

acceptable solidified* waste product.

The PCP shall identify. inter-face~ ~ith other plant systems (e;g., liquid ~nd ~aseous radwaste s~si~ms),

identify equipment (interlocks, alarms, monitors, etc'.) which are required

  • to. be.functional before processing can comme_nce, identify administr~tive contra.ls or equipment features to as.sure. that operating procedures wi 11 :
  • .be _follo\\'Jed, identify the sampling requiremen.ts prior to process*ing and':

identify the various processing steps and process parameters* \\'1hfrh provide boundarY*conditidns within which th~ solid radwaste.system ~hall be;operated.

Depending upon the type of waste *!bead resins, pm'lered resins, filter*

'\\..:

sludge*,;.evaporator concentrates, sodium sulfate solutic;m.s, boric* acid

  • .solutions, etc.) to be solidified-and the kind of solidfffration* agent..*:

. (.i.Jreci foi*maldehydE:, cement, cement \\'lith sodium silJcate, asphalt, poyli;ster, et~.) employed, the process parameters shall incl~de but are not limited

.:.. 3 -

. e *

  • ENCLOSURE 3 to, the type of waste, requirements for sampling prior to processing, pH,
  • .oil content, water content, temperature, -ratlo of solidification a-gent to influent ~~ste and the ratio of solidification agent to chemical additive *

..*:*.~

MOTE:

For operating reactors which have systems* insta*lled that are not capable of solidifying the categories of i*wet" \\*1aste as defined in SRP 11.4,

. BTP...;ETSB 11-3 or NUREG-0133 the licensee s}Jall define the limitations of his present system 'and provid,e a Process Control Program to cover the

. \\vaste that can be processed by his existin~ system~.The licensee shall

.identify those \\'Jastes which catmot be solidified and indicate the method bf packaging currently being employed (d~\\-Jatered resins, ~ermiculite, *etc~}.

In additfon, the licen.see shall provide a schedule for. upgrading his solid

\\:raste system to provide the capability to process 'aJl types. of "wet"

_\\*1as:te.s as defined i.n these reference doct:imerits ~

'\\

r i'

I, '

..,~

  • r I:.

i.

r*

.NCLOSURE 3

. -~...

. f<EFl:RENCES

  • r-....

(l)

  • Standard Review-Plan 11.4~ Revision l~ Solid _Waste Management Systems,. NUREG-75/087 *..

(2)

Branch Technical Position*~ ETSB 11-3, Revision 1, Design Guidance for So=tid Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Po0er Re~ctor Plants, NUREG-75/087.

(3)

Dr~ft Radiological Efflu~nt Technical*Specifications for PWRs and BHRs, NUREGs 0472.and 0473.

(4) *Preparation of Radiologfcal Effluent Technic*a1.Spe,cifications for

. Nucl~ar Power Pl~nts, NUREG~Ol33 *

...

Retrieved from "https://kanterella.com/w/index.php?title=ML18043A955&oldid=5026227"