ML100550812

University of Utah - Copy of the Markedup Current TS: Only the Chapter 6.0 Titled Administrative Controls (the Rest of the TS Document Was Not Changed and Is the Same as the One Submitted as Part of the SAR Documentation Dated Jun 2009)

ML100550812
Person / Time
Site:	University of Utah
Issue date:	02/11/2010
From:	Univ of Utah
To:	Office of Nuclear Reactor Regulation
References
Download: ML100550812 (22)

Text

50 S Central Campus Dr. Room MEB 2298 Salt Lake City, UT 84112 Phone: 801.587.9696 Web site: http://www.nuclear.utah.edu/nep.html February 11, 2010 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Mail stop: 12D03 Washington, DC 20555-0001

REFERENCE:

Docket 50-407 The University of Utah -TRIGA Research Reactor (UUTR)

License No. R-126 SUBJECT 1): Copy of the markedup current TS: only the Chapter 6.0 titled ADMINISTRATIVE CONTROLS (the rest of the TS document was not changed and is the same as the one submitted as part of the SAR documentation dated Jun 2009)

The University of Utah TRIGA research reactor (UUTR) is submitting the clarification in administrative controls, especially clarifying the organizational chart shown as Figure 6.1, Pg. 26 in the current TS Chapter 14, Chapter 6.0. The organizational chart is redrawn to more clearly show the organization and management, lines of communication and lines of responsibilities and reporting. This is designed to be in full compliance with the ANSI/ANS 15.1-2007, ANSI/ANS 15.4-2007 and NUREG 1537 Part 1 & 2. The wording of the textual part of the Chapter 6.0 was revised as markedup, and in compliance with the ANSI/ANS 15.1-2007, ANSI/ANS 15.4-2007. According to our line of communication and reporting, the Chair of the Reactor Safety Committee and the Associate VP for Research, have approved the clarifications provided in the markedup document.

-IStyle Definition: Heading 2 1 Style Definition: TOC 2: Space Before: 0 pt, Tab stops: 6", RightLeader:.

clarAB 14 Ted~ncal Spedfitaons Note: changes from the current 1S are highlighted, crossed-out and in red text Only Chapter 6 is revised: IGHLIGHTED. CROSSED-OUT. ADD IN RED TEXT / under the Amendment 7.

This Document therefore contains ONLY Chapter 6.

i

FACILITY LICENSE R-126 TECHNICAL SPECIFICATIONS AND BASES FOR THE UNIVERSITY OF UTAH TRIGA REACTOR DOMEr50-407 Amendment No. 5

TECHNICAL SPECIFICATIONS AND BASES FOR THE UNIVERSITY OF UTAH TRIGA NUCLEAR REACTOR This document constitutes the Technical Specifications for the Facility License No. R-126 and supersedes all prior Technical Specifications. Included in these Technical Specifications are the "Basis" to support information the selection and significance of the specification. The bases are included for information purposes only. They are not part of the technical Specifications, and they do not constitute limitations or requirements to which the licensee must adhere.

Furthermore, the dimensions, measurements and other numeric values given in these specifications may differ slightly from actual values because of normal construction and manufacturing tolerances, or normal degree of accuracy of the instrumentation.

Amendment No. 5

TABLE OF CONTENTS

..................................

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.... Formatted: Do not check spelling or grammar Formatted. Do not check spelling or grammar Formatted: Do not check spelling or grammar Formatted: Do not check spelling or grammar odaianal TS docu~ment Mcnumbellno/this document Do iumberlng 6.1 OroanizaWn ...26/4 6.1.1 StrLicture ,

. 28/5 6.1.2 ResponsitAlity .............. u~n ... .n i -.....

6.1.3 Staffina ...

6.1.4 Selecidon and Trahing f ~ IMMMM Personne .............. 29/7 6.2 Reactor 5ah& Commfttee 6.2.1 Furicton .. ~W44WMMW~

~4~IMU4M~I~... 29/7 6.2,2 Composibon and Oual 6.2.3 Ooerafim 6.2.4 Review Funcdon .......... ..... 30110 6.2.5 &jdits ......

. 31112 6.2.6 ReCDrds ... ,31/12 63 Radiation SafiM ..............

6.4 Opffatina Procedures ......

k~ASAmaAM................ ........ 321 6,S E=Timents Review and 6.6 Readred Actions .............. ....

32/13 6.6.1 AcUon To Be Taken In 6.7 Reports ........

62 Fadfity Operatina Records l~UJ~M 44J ~ in................

U4~w 36/14 0; Qr'h-ialitv AQm imne-P~~~~~~.................. INNNNNN -

47I11l-Amendment No. 5 Hi

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6.0 ADMINISTRATIVE CONTROLS Formatted: Font: 12 pt, Bold, Not Strikethrough, Condensed by 0.2 pt, Not Raised by / Lowered by, Kern at 14 pt, Highlight TFormatted: Font: 10 pt, Not Bold, Strikethrough, Not Expanded by / Condensed by

, Not Raised by / Lowered by 0 .2 .. . . .

........ . ... . .... .. .... ----------- . . -ý 4 Cm ad [j :T i eo e 6. 1--

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6.1 Ogagnization

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_pf _ -4 Formatted: Font: 10 pt, Not Bold, E Strikethrough, Not Expanded by / Condensed by Tnf te f y m Formatted: Font: 10 pt, Not Bold, nda y ofea chm ember ofte operatin sff Strikethrough, Not Expanded by / Condensed by shall be defined i n writing.

2) As indicated in Fig. 6.1. the Reactor Safety Committee si repot to Leve[ - Formatted: Numbered + Level: 1 +

Radiation safety personnel shall report to Level 2. Additional description of levels Numbering Style: 1, 2, 3, ... + Start at: 2+

folos f tAlignment: Left + Aligned at: 1P + Indent at:

1.25" aLt 1 of Iof tahe.rector diriletrshlly lrco ofteUa the r ulaetno niwrn rthea facilwtsItes,frm Le., the h

c. LetW 3' Indivdual aresonble for day~-todav ggca'aon or shift shiall be the reactor sugerLsor (RS)h. This nerson shall be a sCenor reactor on~eratpr (SRO).

I Amendment No. SP 4

d. LeOd 4ý oerarino staff shall be senior reactiorooffators. reactor coeratoi-s. and

3) Transition plan shall be defined as follows: Formatted: Numbered + Level: 1 +

Numbering Style: 1, 2, 3, ... + Start at: 2 +

Alignment: Left + Aligned at: 1" + Indent at:

1.25" Formatted: Numbered + Level: 2 +

Numbering Style: a, b, c, ... + Start at: 1 +

.S.N.R.C: Radiation 5afety pesonnel shall [W= to RA U13es Leyel I dedes Alignment: Left + Aligned at: 1.31" + Indent difffndy. at: 1.56" b, In the absence of the Levei 3 individual rsabbatial leave. suidden leAyg]: Level most senior Level 4 individual (SRO).

- - F-ormatted: Strikethrough t,!j wnen me reftwe 09met seeurea, " FAinimum 9mit 9nm eens" (a) Reseter Operater (RG) at the eentFelg (may be the SRG er P-E+.

(b) Senier Reaeller (*epallop (SRO) en eall bot met neeeswrily en site-.

(e) AfleUer pFgenW preget at the feeilit, eamplex whe 19 able to eemy et*

b

- - JI mert[j1 OrWudr612

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- " Formatted: Body Text, lustified

• he fashty 9M11 be tineim We dreet eamm! of a 1:omwd Senim Reaekor Qwpolor deslamied by the Rememp Supervisor (RS) who is also a lkerAed Semigm RMdgtjkMWtM

Fhe SRO 9hall be pesimnsibie to the RG for the evepail fadlity ao&ehom ind"el seeimalSom orA walmWilvirm e# the faegity and a9geeialiNd eakdom"t: ;he SRO reaBeftmble far crawine that all awrobons are awdHefed In a

- - I Comi.m. [tjG], This ori" I bmd clarilied as 6.1.2: 1 Resoonsibilitv for the safe ooeration of the reactor facilitt shall be with the chain of command established in Fla. 6.1 following ANSUANS 15.1-2007:

1) Individuals at the various manaoemnt levels. in addition to having resoonsibillit for the oolicies and operation of the reactor fadlity, shall be resoonsible for safeguarding the oublic and facility personnel from undue radiation exposures and for adhering to all reduirements of the ooerating license or charter and technical soecfications.

2) In all instances. resoonsibilities of one level may be assumed by designated alternates or by higher levels. conditional upon aporooriate gualifications.

3) The reactor faility shall be under the direct control of a licensed Senior Reactor Ooerator (SRO) desianated by the Reactor Supervisor (RSI who is also a licensed Senior Reactor Operator. The SRO shall be responsible to the RS for the overall I Amendment No. &-Z 5

facility ogeration indudino the safe operation and maintenance of the facility and associated eauioment. The SRO shall also be responsible for ensurina that all ogerations are conducted in a safe manner and within the limits orescrbed by the facility license, federal and state regulations. and requirements of the Reactor Safety I... Foa.tted: Strikethrough C63 ia" i-' in'Formatted:

Qi Body Text

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fq~~~~~~~iý4ýt~~~~~sh! reeedtemnm!tet~~~ fA -f -if-of -- Formatted: Font: 0 pt, Not Bold, 15A " - - - - Strikethrough, Not Expanded by / Condensed by

]Formattd: Font: 10 pt, Not Bold, 6.St.kethrough, Not Expanded by / Condensed by

1) When the reactor Osnot secured. the mldn9mum staff shall consist of,

a. A licensed reactor operator In the control room. e.o.. Reactor Operator R' (may be the SRO or RS).

b. A esnated Senior React Ooerat SRO on call but not ne* rjlv on site.

c. Another person present at the fadlltv complex who es able to car'v Gu Formatted: Numbered + Level: 2 +

Numbering Style: a, b, c, . + Start at: 1 +

Alignment: Left + Aligned at: 1.31" + Indent 2)l A list of reactor failit personnel by name and telpnhone nwbw hall be IV at: 1.56" available in the control room] &b use by the onertor. Level 112Te list shail Indude:

a. maad+ge nt er-sonnel.

c. ode ooerafons personnel:

3) Events redrina the presence at the fadlity of the senoor reagtr operator are:

a. Initial startb and aooroadi to power.

b, all fuel orcontrol-rodrelcations within the reactor core realon.

c. refoa of any exoetiment with read*tVt worth oreatE than one dollar,

d. repyr from Lmdnned or uniheied shutk morsifiat I-Formatted: Stnikethrough

-- -7 Formatted: Font: 12 pt, Bold, Strikethrough, Emeziteaetof bwpc!;z' .l !srzpensisie fr' aie faeonity~s (gIlzltf rnrg Condensed by 0.2 pt, Kern at 14 pt Preeirain and 9 - - 1.ari.i....Pmwafon - Formatted: Strikethrough Formatted: Strikethrough I Amendment No. 7-Z 6

6.1.4 Selection and Trainina of Personnel The selection, traininm. and reaualification of operations oersonnel shall meet or exceed the reouirements of American National Standard "Selection and Training of Personnel for Research Reactors." ANSIOANS-15.4-1988 "-R1999. Sections 4 through 7.

The Reactor Supervisor shall be responsible for the facility's Reoualification Training Program and Qoerator Training Program.

- -4 Formatted: Stikethrough I 6.. FRactoimon Formatted: Indent: Left: 0' 6.2 Reactor Safety Committee Formatted: Heading 3, Indent: Left 0" C2.1 Fund J Formatted: Font: Bold

ew The Reactor Safety Committee (RSCshall function toprovide an independent _- Formatted: Strikethrough i review and audit of the facility's activities including:

(1) reactor operations (2) radiological safety Formatted: Strikethrough Formatted: Strikethrough

- Formatted: Strikethrough ,3 SFormatted: Strikethrough ~1 J

-J

. - - j Formatted: Strikethrough 7 Formatted:

- - Formatted: Strikethrough Formatted: Strikethrough Formatted: Strikethrough Formatted: Strikethrough I Amendment No.7 77-

Fornatted: Strikethrough Reactor Operators - Foratted: Strkethrough

- - Formatted: Strikethrough

-Une of Responsibility Formatfted: Strikethrugh

........... Line of Communication

- 4 Formmtted: Strikethrough

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!Figure 6 1 Un'- ___L_ - -A M ý1_ A MOn wtion for Nuelear Rea-r s

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1 *S I Amendment No. 5-Z 8

F Formatted: Font: 10 pt, Not Bold, Not Expanded by / Condensed by I~7 Lai SW -

T -- -- > Line of communication

-0 Une of responsibility I L

and reporting b

am Comm* M12): C3arIW Organtzational II Chart University of Utah Administrative Ofanization for Nudear Reactor O Uons MClarified - December 2009: in comrpliance with ANSI/AN; 15.1-20071

3) general safety

4) testing and experiments

5) licensing and reports

6) quality assurance Amendment No. 57 9

6.5.2 compasrdon and Quiallficationg - - -f Comment [VU]: PzpWW wM 6.2.2 , _j 6..opsinadOaiiai

-- - - j Formatted- Indent: Left: 0" The RSC shall be composed of at least five members knowledgeable in fields that relate to- - - rormatted: Indent: Left: 0.75" nudear reactor safety. The members shall collectively reoresent a broad soectrum of J expertise in the aooroonate reactor technoloyv.

The members of the committee shall include the Reactor Supervisor and faculty and staff*--- [ Formatted: Indent: Left: 0.75" members designated to serve on the committee. The University's Radiation Safety Officer shall be an ex officio member of the mmieeS. .. ..... - Foratted: Strikethrough

÷- *Fr* net et 0" Members and alternates shall be aooointed by and reoort to Level 1 manaaement.,-

4Formatted: Indent: Left: 075" Individuals may be either from within or outside the ooerating organization ( univ. Qualified and aooroved alternates may serve in the absence of reoular members.

I

.5. Operation

- - Frmatted:

o- Heading 3, Left

. IFormatted: Font: Bold The Reactor Safety Committee shall operate in accordance with a written charter, including.--- I Formatted: Indent: Left: 0.75" provisions for (1) meeting frequency: )he............. shall Fneet at least semiannually a_,f.d_- - j Formatted: Strikethrough

..bc...m... thz..f shall meet z....... - not less than once oer calendar year and more freauentlv as circumstances warrant. consistent with effective monitoring of facility activities f.2) Vetintm*. - - f Formatted: Strikethrough

3) QUeFrFAS ehalmfla eF his designat and twe members

2) voting and ouorums: a qUorum shall be made uo of the chairman or his desionate and votino members such that at least half of the voting body is represented. and where the Level 2 facility director and anyone who re=orts directly to him/her (such as Level 3 and Level 4 oersonnel) does not constitute a voting majority Q34) fzetoz z)f submiszr.e -and _eeontcntf _presentatiens te the- eeffiffli Lt *-* "* PFormatted: Strikethrough rcoemittees Formatted: Normal, No bullets or numbering (15) review, approval, and dissemination of minutes in timely manner

.6.5.4 Revlevý C..ent [0161, RWbd Mh 6.2-4 6.2.4 ReWm Furicdon

-- -- i Forat  : Indent: Left: 0" The responsibilities of the RSC or designed Subcommitteew thereof shall include, but is not-- - -

limited to the following:

ormatted. 7ndet: Left: 0.75" i

(1) review and approval of all new experiments utilizing the reactor facility I Amendment No. 5-7 10

(2) review and approval of all proposed changes to the facility license by amendment.

and to the Technical Specifications (3) review of the operation and operational records of the facility (4) review of significant operating abnormalities or deviations from normal and expected performance of facility equipment that affect nuclear safety-f5) review of approval of all determinations of whether a proposed change, test, or experiment would constitute a change in the Technical Specifications or on unreviewed safety questions as defined by 10 CFR 50.59.

I Amendment No. 5,-Z 11

(-6)- review of reportable occurrences and the reports filed with the Commissions for said occurrences (7) review and approval of all standard operating procedures and changes thereto

- - Formatted: Normal, Justified, Indent: Left: 1",

(8) biennial review of all standard procedures, the facility emergency plan, and the' Hanging: 0.25", Space Before: 10.3 pt, Une facility security plan. spacing: At least 11.75 pt, No widow/orphan control, Don't adjust space between Latin and Asian text, Don't adjust space between Asian A written re=ort or minutes of the findinas and recommendations of the review erouo shall text and numbers be submitted to Level 1 and the review and audit arouo members in a timely manner after the review has been completed.

- - Formatted: Indent: Left: 0", First line: 0" J 6.2.5 Audits Formatted: Body Text The RSC or a subcommittee thereof shall audit reactor operations semiannually, but at intervals not to exceed 8 months. The semiannual audit shall indude at least the following:

(1) review of the reactor operating records (2) inspection of the reactor operating areas (3) review of unusual or abnormal vents (4) radiation exposures at the facility and adjacent environs Formatted: Body Tex The activities of the RSC shall be documented by the committee and the RSC shall maintain a file of the minutes of all meetings.

6.3 Radiation -J-i The Radiation Safety Office of the University of Utah shall be assigned resogrisibilitf implementing the radiation protection oroaram at the reactor using the guidelines of American National Standard "Radiation Protection at Research Reactor Facilities." ANSIIANS-15.11-1993 (R20041. The Radiation Safet Officer shall report to Level 2 [Fig. 6.11.

I Amendment No. 5-Z 12

&S EmMments ReWew and Approval Aporoved =riments shall beqmJjd out in accordance with established and aonr6yed 6.9 0uality Assurance

-- Formatted: Indent: Left: 0" In accordance with Regulatory Guide 2.5 and ANSI 402, "Quality Assurance Program- - ormatted: indent: Left: 0.69-Requirements for Research Reactors," Section 2.17, the facility shall not be required to prepare quality assurance documentation for the as-built facility. Quality assurance (QA) requirements will still be limited to those specified in Section 2.17 as follows:

"All replacements, modifications, and changes to systems having a safety related function- - Formatted: Indent: Left: 0.75", First line: 0" shall be subjected to a QA review. Insofar as possible, the replacement, modification, or change shall be documented as meeting the requirements of the original system or component and have equal or better performance or reliability."

"-he required audit function shall be performed as specified in Section 6.5.5." . - Formatted: Indent: Left: 0", First line: 0',

Space Befocre: Opt

,7 Acti To BTaken In the Evet a Safety Irn* Is Exceed Comn tZ1 ene 6.6 Reauired Actions 6.6.1 Action To Be Taken in the Event a Safety Limit is Exceeded

-- - - I Formatted: Indent: Left: O" I In the event a safety limit is exceeded:

(1) The reactor shall be shut down and reactor operation shall not be resumed until authorized by the U.S. Nuclear Regulatory Commission R u . ....... - - Formatted: Strikethrough

-- - - - Formatted: Indent: First line: 0' I I Amendment No. 5-7 13

(2) An immediate report of the occurrence shall be made to Level 2 and to the Chairman of the Reactor Safety Committee, and reports shall be made to the N .inu- - Formatted: Strikethrough I acerdir.an with Scztfzn 6.10 U.S.N.R.C in accordance with Section 6.7 of these specifications.

(3) A report shall be prepared that shall include an analysis of the causes and extent of possible resultant damage, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Reactor Safety Committee for review and then submitted to the PK_ U _when authorization is sought to resume operation of the reactor.

-- Formatted: Strikethrough I (4) A report shall be made to the U in accordance with Section 6G6§2 of these specifications.

6.4i Un Prmdures fl) performing irradations and experiments (2) strbp operation', and shujtdown of the reactor radiation emergencies, fire or explosin, personal injury, cvld4isode, and bomb threat f4) core canges and fuel movement f5) coto elemnwt removal and replacement (W) performing preveive maintenance and calibration tests on the reacor and assocedequipment f7 pwreup nt Carnmat ItJ23].- Bewmes 6.4 J

Cm*Mwt [tIZ4].Bewmes 6.8 ii ii*Siiii!i 6.8 Faclitv Ooeratina Records In addition to the requirements of applicable regulations, and in no way substituting for those requirements, records and logs shall be prepared for at least the following items and retained for a period of at least 5 years for items f1) through (6) and indefinitely for items (7) through f11).

Amendment No. -24 14

(1) normal reactor operation (2) principal maintenance activities (3) abnormal occurrences (4) equipment and component surveillance activities required by the Technical Specifications f5) experiments performed with the reactor (6) gaseous and liquid radioactive effluents released to the environs (7) offsite inventories and transfers (8) fuel inventories and transfers (9) facility radiation and contamination surveys (10) radiation exposures for all personnel f11) updated, corrected, and as-built drawings of the facility matted: Heading 2, Left 6.7 eortsr In addition to the requirements of applicable regulations, and in no way substituting for those requirements, reports shall be made to the NtC-U.S.N.R.C FS--follows:

(1) A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone a,*"*teqleaph_-to the 'R......ol Adminitm*.,,

Protect Manager, Regien WV,U.S.N.R.C., of (a) any accidental release of radioactivity above permissible limits in unrestricted areas whether or not the release resulted in property damage, personal injury, or exposure; (b) any violation of the safety limit; (c) any reportable occurrence as defined in Section 1.1, "Reportable Occurrence," of these specifications.

(2) A report within 10 days in writing to the Document Control Center, U.S.N.R.C.,

Washington, D.C., with a copy to the Regz.enl Admini*tr.ato, Region PU.S.NL.R.C Operations of (a) any accidental release or radioactivity above permissible limits in unrestricted areas whether or not the release resulted in property damage, personal injury, or exposure. The written report (and, to the extent possible, the preliminary telephone or telegraph report) shall describe, analyze, and evaluate safety implications, and outline the corrective measures taken or planned to prevent recurrence of the event.

I Amendment No. ý5-1 is

(b) any violation of safety limit, (c) any reportable occurrence as defined in Section 1.1, "Reportable Occurrence," of these specifications.

(3) A report within 30 days in writing to the Document Control Center, U.S.N.R.C.,

Washington, D.C. with a copy to the R;gl,..-l Adn-'.-ater-, Re9'ez, 1V'JPAS.N Operations of (a) any significant variation of measured values from a corresponding predicted or previously measured value of safety connected operating characteristics occurring during operation of the reactor, (b) any significant change in the transient or accident analysis is described in the Safety Analysis Report, (c) any significant changes in facility organization, (d) any observed inadequacies in the implementation of administrative or procedural controls.

(4) A report within 60 days after completion of startup testing of the reactor (in writing to the Director, Office of Nudear Reactor Regulation, USNRC. Washington, D.C.

20555) upon receipt of a new facility license or an amendment to the license authorizing an increase in reactor power level describing the measured values of the operating conditions including:

(a) an evaluation of facility performance to date in comparison with design predictions and specifications, (b) a reassessment of the safety analysis submitted with the license application in light of measured operating characteristics when such measurements indicate that there may be substantial variance from prior analysis.

(5) An annual report within 60 days following the 3 0 th of June of each year (in writing) to the Document Control Center, U.S.N.R.C., Washington, D.C. with a copy to the Reg,*.l Admi*str*tor, Ragian IPU.S.N.R.C. Operations. providing the following information:

(a) a brief narrative summary of (i) operating experience (including experiments performed), (ii) changes in facility design, performance characteristics, and operating procedures related to reactor safety and occurring during the reporting period, and (iii) results of surveillance tests and inspections:

(b) tabulation of the energy output (in Megawatt-days) of the reactor, hours reactor was critical and the cumulative total energy output since initial criticality; (c) the number of emergency shutdowns and inadvertent scrams, including reasons for them; I Amendment No. 5-7 16

(d) discussion of the major maintenance operations performed during the period, including the effect, if any, on the safety of the operation of the reactor and the reasons for any corrective maintenance required; (e) a brief description, including a summary of the safety evaluations of changes in the facility or in procedures and of tests and experiments carded out pursuant to 10 CFR 50.59; (f) a summary of the nature, and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or before the point of such release or discharge:

Uouid Wat (summarized on a monthly basis)

(i) radioactivity discharged during the reporting period

" total estimated quantity of radioactivity released (in curies) an estimation of the specific activity for each detectable radionudide present if the specific activity of the released material after dilution is greater than 1 x 10-7 giCi/cc.

" summary of the total release (in curies) of each nuclide determined just above for the reporting period based on representative isotopic analysis,

" estimated average concentration of the released radioactive material at the point of release for the reporting period in terms of pCi/cc and fraction of the applicable MPG DAC or Effluent concentration (ii) total volume (in gallons) of effluent water (induding dilutant) released during each period of release.

Gaseous Waste (summarized on a monthly basis)

(i) radioactivity discharged during the reporting period (in curies)

" total estimated quantity of radioactivity released (in curies) determined by an appropriate sampling and counting method,

" total estimated quantity of argon-41 released (in curies) during the reporting period based on data from an appropriate monitoring system.

I Amendment No. -577 17

" estimated average atmospheric diluted concentration of argon-41 released during the reporting period in terms of ijCi/cc and fraction of the applicable M--DA(_value.

" total estimated quantity of radioactivity in particulate form with half-lives greater than 8 days (in curies) released during the reporting period as determined by an appropriate particulate monitoring system.

" average concentration of radioactive parliculates with half-lives greater than 8 days released in gCi/cc during the reporting period, and

• an estimate of the average concentration of other significant radionudides present in the gaseous waste discharge in terms of giCi/cc and fraction of the applicable MP_26-value for the reporting period if the estimated release is greater than 20% of the applicable MPGDAC.

Solid Waste (summarized on an annual basis)

(i) total amount of solid waste packaged (in cubic feet),

(ii) total activity in solid waste (in curies),

(iii) the dates of shipment and disposition (if shipped off site).

(g) An annual summary of the radiation exposure received by facility personnel and visitors in terms of the average radiation exposure per individual and greater exposure per individual and greater exposure per individual in the two groups.

Each significant exposure in excess of the limits of 10 CFR 20 should be reported, including the time and data of the exposure as well as the circumstances that led up to the exposure.

(h) An annual summary of the radiation levels of contamination observed during routine surveys performed at the facility in terms of the average and highest levels.

(i) An annual summary of any environmental surveys performed outside the facility.

I Amendment No. S-Z 18