ML20236S249

Proposed Tech Specs for Reactor Model AGN-211P (S.N. 102)

ML20236S249
Person / Time
Site:	05000112
Issue date:	11/19/1987
From:	OKLAHOMA, UNIV. OF, NORMAN, OK
To:
Shared Package
ML20236S247	List: ML20236S245 ML20236S249
References
NUDOCS 8711250011
Download: ML20236S249 (11)

Text

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APPENDIX A 1,ICENSE NO. R-53 TECilN I C AL_ S PEC I F I CATIONS _

FOlt Tile UNIVERSITY OF OKI.AllOMA R! ACTO![ MODEL_ AGN--211 P (,S.N. 1021 November 19, 1987 3

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TABLE OF CONTENTS PAGE 1". 0 ' DEFINITIONS. .

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'2'.0 SAFETY. LIMITS.AND LIMITING SAFETY SYSTEM SETTING . . . 1-E

. 3.0 LIMITING. CONDITIONS FOR OPERATION. .. . . . . . . . . 1 4.0- SURVEILLANCE REQUIREMENTS. .. .. . - . . . . .. . . . . . 2-4.1 Facility Support and' Protection' System .- . . . . .- 2

, 4 5.0 DESIGN FEATURES . . . . . . . . . . . . . . . . . . . 3

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5.1 Mothball Status of the Reactor.. . . . .. . . .. . 3

' 5.2 Fuel. Storage . . . .. .- . . . .. . . . . . . . . . 3

' 6. 0' ADMINISTRATIVE CONT'ROLS... . . . . . . . . . . . . . . 3 P[

6.1 Organization.... . . . . . . . . . . . -. . . . . . 3 6.2 Reactor Safet.y Committec . . . . . . . . . . . . .- 5 6.3 Reportable Occurrences . . . . . . . . . . . . . . 7 6.4 Proebdures , . . . . . . . .. . . . . . . . . . . 8 6'.5 Records Retention. . .- . . . . . . . . .. .. . . . 9 l

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L ~* '1.Os ' DEFINITIONS Uw l u +v . .

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guarterly - is defined.an.3 months not.t.o exceed 4 mont.hs.

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S e m i '- An n u a l 1,1 ' -- is defined'as 6 months but.not t.o exceed 7 W l- months.

l AnnuaJll. .AnnuallyLis defined as 12 months but not to I j E < exceed 14 monthsv j H '

K Shutdown Margin . - The shutdown margin is defined as the amount of negative reactivity by which the reactor is .

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' shutdown with the most reactive rod stuck out of t,he core.

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4 Reactorjiecured - The reactor shall be considered secured r

.when:

. (1 ). It contains insufficient fissile mat.erial or moderator

.presentiin the reactor, adjacent, experiments or control rods,ito at,tain criticality under opt.imum available conditions of moderation and reflect lon, or

. ( 2 )- No work.ls~in progress involving core fuel, control

. rods or. control rod drives unless they are physically decoupl ed .f rom , t,he reactor, and (3)5 The console key switch is in the off position, the key is removed from the lock and the reactor console has been disconnected from the power supply.

SAFSTOR or Mothball - The' reactor facility i.s considered to beLin a SAFSTOR or mothballed condition when the facility is lin a state of protective ' storage. The facility may be left intact except that all fissionable materials shall be removed from t.he reactor pool. The reactor fuel shall be in storage containers locat.ed in a fuel storage area. Appropriate

-surveillance, radiation monitoring, and security procedures are established un' der a possession-only license to ensure

t. hat, the henith and safety of the public is not, endangered.

2 . 0' SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Not, Applicable._ The reactor shall remain secured and the

' facility shall be in mothball status.

3.0 LIMITIt{G CONDITIONS EOJLOfEIMT_I.ON

Not App 11icable. The reactor shall remain secured and the facility shall be in mot.hball status.

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.C 64'.0 SURVEIhbANCR REQUIREMENTS' Actions specified in this section are applicabie to the mothballed condition of the facility and shall be performed .

withinithe~.speelfled survel,llance period.

. '4.1 Facility Supporti and protection Systems A placability J

1 This specification applies:t.o the facility. support and

' protection systems such as physical. barriers, and radiation monitoringi activities.

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To assure that the public health and safety are not

'" . endangered as a result;of physical degradation of the facilit,y'during,the.-term of the' possession-only license

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Specification-ln. . . physical barriers to unauthorized entrance into the reactor' facility and fuel storage area, e.g., building,

' rooms,; doors, and access openings, shall be visually

+. inspected!at-least once quarterly.

b. -Fuel. storage containers ~and container locking rings shall be-visually inspected at, least. quarterly.

'c.- A; radiation survey of the. react,or faci 1ity and fuel  !

storage' area shall;be performed at least. semi-annually.

.d.: . Radiat, ion survey instruments.shall be calibrated semi-annually.s

, ,! Bases The physical barriers, e.g. building, rooms doors, and access openings are inspected to assure t. hat these barriers have not deteriorated and that locks and locking apparat.us are intact..

Storage containers and container locking rings are inspected j to assure ' int.egri ty o f the containers. This inspection, in conjunct. ion with the annual fuel inventory and radiation

. survey'of the fuel storage area will verify that radioactive y

mat,erial has not been removed from t.he cont.ainers or is not, l' escaping'or being' transported through the containment 1: barriers. In addition, t,h e radiat, ion survey provides cassurance that radiation doses to facility personnel and to L the public are maintained at. a leve] below 10 CFR 20 limits.

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.h i :5.0': DESIGN' FEATURES f:

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~ 7, . r 5.1 ; Mothball Status of the Reactor (g f Duringia mothballed state of protect.ive storage:

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a. The reactor fuel-is removed-from the pool, b', All . fissionable material used in connection with

! , . operation .of . t.he. reac tor is stored in approved st.orage s ' containers lwith k<0.8, containing less than 400 grams of U-235 each, and is located in a designat.ed, controlled

, T* fuel storage area in accordance with paragraph 5.2 of.

these technical specifications.

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. 5 '. 2 : Fuel St.orage-i Fuel,. Including fuci devices, shall be stored in locked roomsLin the reactor building. The storage array shall be such that K g7p is'no greater than 0.8 for all conditions of m f, moderation and reflection.

W 6.0 ADMINISTRATIVE CONTROL.S a <

, , 6 ' 1 . Organi zation ; of Responsibi 1 i ty for the University M Oklahoma Nuclear Reactor - Administrative control of the reactor is. diagrammed.in Figure 1.

j-i6.1.1 President - Chief Executive Officer of-the University y 6.1.2 Provosty- Chief l Academic Officer.

6.1.3 V.P. for Administrative Affairs - Chief Administrative

!- -Officer 6.1.4 Dean.of Engineering - Administ.rative Officer in charge of the College of Engineering i

, 6.1.5 . Director a School of Acr_ospace', Mechanical and Nuclear.

'l Enfincering (AMNH) - The Director is the head of the three degree programs, Aerospace, Mechanical and Nuclear Engineering. The Director will provide proper financial and technical support. Lo ensure the mothball s t.at u s of t.he

! facility in maint.ained in accordance wi th all requirements.

p. .L L - 6.1.6 Reactor Di reetcg - Responsible for the general administra-L . tion of the facility. In this capacity the Director shall have the authority and responsibility for the faciilty and, within the limitations set forth by the facility license, K .. i shall make policy decisions on all matters concerning the

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safety of the' mot.hball status of the fuel and is advised by the Reactor Safety Committee, the Radiation Safety Commi t. Lee and the Universi ty Radiati on Safet.y Officer.

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c 6.~1.7f Rdactor Su6ervisor -' Position not needed :during time the

,l reactor ismin:a mothball status. .

?6.1.8fUniversity' Radiation Safety Officer (RSO) -.llas over-all e

1 responsibili ty . for radiological safet.y at' the University and shall assure.t. hat necessary radiation. surveys are conducted

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in:the. Reactor,-fuel storage,! 'and other associated labora-( t'ori es D D TheLRadiation Safety. Officer shall review the radio logical safety' aspects of the fuel. storage and shall advise, Lt.he Reactor Director in all matt.ers relative to-radiologi-calisafety...The RSO will be a' member of-the Reactor Safety

• . , Committee and the Radiation Safet.y Committee.

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' 6,.1~. 9.; Reac t,or Staf f Quali fications The React.or Director and any i 1, ,

reactor technicians shall meet the minimum qualificat. ions

"" . set forth in'ANS 15.4, " Standards for the Selection and

, Training of Personnel for Research Reactors." The

, qualifications: of a . certified henith - physicist shall be acceptable.-- ,

6.2 Reactor' Safety' Committee s

, n 6.'2.1. .The' Reactor. Safety Committee (RSC) shall be composed of

- not less than four members appoint.ed by the Vice-

), w President for. Administrative' Affairs, two of whom wi.ll

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?be the Radiation Safety Officer and the Reactor m < '

. Director.-

y 6.'2.2.~ A minimum of fif ty percent (50%) of the membership j shall const.itute'a' quorum. A' minimum quorum shall not 1 be const,ituted with more than t.wo commit. Lee members s

s ,y from the operating staff, w

'... - 6 . 2 . 3 .. ' The committee shall'have a maximum of three members appointed from the reactor operating staff.

' 6 ; 2. 4. -  : Minutes of the meeting shall be taken and submit.ted to

< 'ench member'of the committee along wit.h report.s j

V ', , present.ed t.he commit. tee.

16.'2.5. 'Ad hoc subcommittees may be convened at the request of the' chair and will report their findings to the committee.

)6.2.6. .The chai'r shall be appoint.ed by the Vice-President for

' Administrative Affairs. The chair shall be responsible to call'the committee into session at least semi-annually and shal'1 make assignments as-necessary to the members of the-committee. The chair will be responsible for ,the recording.of the minut.es and the dissemination of commi t tee ' report.s and mi nutes. The chair or chair's designate shall have signature authority for the n commi t. tec .

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.G'.2f7'. . ,'! Committee members shall have duties and aut.hority as

; assigned by?the chair.

76. 2. 8. . The committee'shall review and approve the

. comprehensive safety aspects of t,he fuel storage.

g . Review and approval by the RSC will. include a determination that, any previously unreviewed safety i question does not pose.a hazard to the reactor, reactor W, '

' . personnel,,or the environment as defined in 10CFR 50.

P Its duties shall' include, but not, be limi ted to the ig c K "

s following:

A) Review and approve safety standards associated

-wit.h.the' mothballed status of the reactor facility which are consistent with the' technical l" specifications of.the' reactor, b B) -Review and approve procedures.as required by the l+ >> t.echnical1 speci fi cati on for rearrangement of fuel, surveillance, and security of the fuel.

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C) Review and approve procedures for the: modification

' 'and/or test.ing of replacement. components

? - associated with the radiation monitoring and J l' fuel storage' security systems.

Review and approve standard procedures for auditp' p; ' .

D).

t and review:of the surveillance procedures required L -by the technical speci ficat. ions 'and securi t.y plan.

- E) . ' Audit performance at'least annually of,the reactor h 3 st,af f in the areas ; facilities manual (piccedures),

maintenance-1ogs and t. cat procedures,' survei11ance tests,.and' physical security plan.

1 F) Review all. abnormal' occurrences and violations of the technical specifications, evaluating the

' causes of'such events, the correct ive' action takEn and recommending measures to prevent the-

> . recurrence of the incident. Report their findings

D to all authorities as required by the technical specificat, ions and University aut.hority. >

G.3. = Reporting Requirements' n ng t%

6 ; 3,1, Annual Report.. An annual report. describing the stat.us of

" the facility, the resulta of environmental and faci 1ity radiat. ion survyes, an evaluat. ion of t,he performance of

l. -security and surveillance measures, personnel exposures to radiation, and any abnormal occurrences during the prev"oun calendar year shall be submitted to the Direct.or of Nuclear Reactor Regulation prior to May 31, of each calendar year.

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' 6.3.2 Reportable' Occurrences. Report.nble' occurrences shalI be

.j repcrt.ed as expeditiously as possible by telephone and

confirmed by t.elegraph , mailgram or facsimile transmission to';the~NRCl Operations Center (202) 951-0550, no lat.cr than

, t.he first work ^ day following t.he event. A wri t, ten followup report describing t.he reportable occurrance including causes, probable. consequences, corrective y . act.i ons , . und , measures to prevent recurrence shal.1 be

< submi t ted within 14 days. 'Informat. ion provided shall contain ~ narrative lmnterial 'for a complet.e explannt. ion of I' The foilowing the:q!,rcumstances surrounding'the event.

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shall 'cy report.ed :

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g ya'.' Discovery of'significant,. unexplained increase in L ^ radiation or cont.aminat. ion levels within or around the kD4 o+ t reactor, facility de fuel st.orage aren.

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'b. Abnor, mal degradation discovered in prot,ective barriers

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" for the reactor facilit.y or fuel storage area which would compromise the physical security est.ablished for

}f :t protect.iverstorage of t.he react.or and react.or fuel.

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o 6.3'.3 Special RAport s r, Spb,ciaf ,,r~poics e which may be required by

, .Q , .-t.be Nuclear RegulatorycC<Gmissida shall be submitted to t.he

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Director offthe appropriate NRC Regional Office within the t.ime period specified for.ench report.

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' 6'. 4 -procedures. There shall be wri t. ten p'rocedures for t.he

'following. TA. -

y g 1. Surveillance and' testing.of. equipment, and syst.cma

-required for(protective st.oruge of the reactor and i

reaator fuelf . .

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Pertsonnel radiation protection consistent. with 10 CFR s20.

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reactor frmi[, t.y arui fuel and

3. 'Accesu. control t.o the storage aren. '

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4. Implementat. ion of the security pInn 3

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'S'. . Notification of the proper authorities in the event of f'

nignifh nnt changes in the radiati on or cput.aminati on levels within t.h e facility.

\J'g e 3 P Record Ret.ention

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9 6.5.1'SARSTOR Records.. lbtont. ion records or logs relative t.o the 4 following itemn(Lhall be kept and retained until the y license is terminated, unl ess ot.herwi se specified by the

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Y ,. :  % $ $ Y.$ Facility-radiation' surveys.

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Environmental Syrteys

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,a e, e, N ;a: Roc 6rds or logs re\lative to the following items shall e

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• k h Yetained :fo'rj( a period of at least ten years:

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i. h in. 'Uperat.ing N Uga or data which shall-identify:

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j, f . l'. Completion' of -pre-startup checkout, start-up,

'ppwer chan;;es,. and shutdown of the reactor.

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control rods,-or experiments that could J$@f Mg N 7[ affect core . react.ivity. .

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@ installation l or removal of . jumpers , special

.. i tagn'on notices, or other temporary changes jg , 't <

3 to1 reactor safety circui try.

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naasurements.

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b. Principal maintenance operations.

c. Reportable occurrences.

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"I d . Survei thdice o apeci.fient. I'ons . activi ties 4'. .s %m e ? Facility / radiation and contamination surveys.

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P f. , Experiments performed with the reactor.

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'* Changes to-operating procedures.

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' 4 V i. Record [ or' logs relative to the followinr, items shall

~ iie' retained for the life of the facility, unless otherwise specified by the NRC:

a. Gascous.and liquid radioactive effluents released Tio,the' it >

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• b. Appropriate of f-site environmental moni toring

.o , surveys.

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ME ~L c. Fuel inventories and iucl transfers.

if 9-t i d. Radiation exposures for all personnel.

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e.,  ; Updated'as-built' drawings of the facility.

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,7: < , 'f. .-Records'of. transient or operational cycles for

, ,,;' WF - , those components designed for a limited number of transients.or. cycles.-

c!WJ 'g. Records of training and qualifications'for membern (W

'of the facility: staff.'

h. Records'.of reviews performed for changes made to procedures or'~ equipment lor reviews of tests:and

experiments. pursuant to.10 CFR 50.59.

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. i'. - Records of meetings of the Reactor' Safety

' Committee.

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