ML20079P398

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Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively
ML20079P398
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 10/31/1991
From:
LONG ISLAND POWER AUTHORITY
To:
Shared Package
ML20079P396 List:
References
NUDOCS 9111120397
Download: ML20079P398 (25)
v • d • e


Text

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Et: CLOSURE 2 To LSNitC-1857 Mark-Up Of The Administrative Controln Port. ion (Section 6)

Of The Shoreham POL Technical Lpecifications i111120397 911031 PDR ADOCL 030003;f2 P PDR e_ ___ . _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ .

INDEX ADMININSTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.................................................... 6-1 6.2 ORCANIZAT10N...................................................... 6-1 6.2.1 NUCLEAR ORGANIZAT10N......................................... 6-1 6.2.2 UNIT 5TAFF................................................... 62 6.3 UNIT STAFF QUALIFICATIONS......................................... 6-2 6.4 TRA1NING.......................................................... 6-3 6.5 REVIEW AND AUDIT.................................................. 6-3 s rtc (S AC) 6.5.1 A REV I EW ff-0PERA110NS ek COMMITTEEd R00) f. . . . . . . . . . . . . . . . . . . . . . . 6-3 FUNCT10N..................................................... 6-3 COMPOSIT10N.................................................. 6-3 ALTERNATES................................................... 6-3 MEETING FREQUENCY............................................ 6-3 QU0 RUM....................................................... 6-4 RE0F0NSIBILITIES............................................. 6-4 REC 0RDS...................................................... 6-5 tu ot tiuptur At.VWW tbNEL (CA P) 6.5.2 AVfMAR-REVIEW-00ARDr(NRB):7.'.'...............................

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FUNCTI6N.....-c.......

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J-6 Q U 0 R U L c,. . . . . . . . . . . . .' . . . . . . . . . . . . . '. . . . . . . . . . f. . . . . . . . . . . . . . . .

6-7, 1,/ /. / ,,

REVIEW.....T ,........................' ,.................... .-6 6-7l; .

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AUDITS.................... d.......................s....... .

7 7 REC-QRDS6.......,4 ....... 6 b...... 4. .......d [..._6-B, SHOREHAM - UNIT 1 vi l 1 . _ _ _ _ _ _ _ _ _ _

  • l INDEX ADMININSTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACT10N.......................................... 6-9 6.7 P ROC E D U R E S AND P R0G P. * '.a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-9 6.8 REPORTING REQUIREMENTS........................................... 6-13 6.8.1 ROUTINE REP 0RTS............................................. 6-13 AN NUA L R E P0 RT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - 13 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.......... 6-13 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.............. 6-14 6.8.? SPECIAL REP 0RTS............................................. 6-14 6.9 R E C O RD R E T E NT 10 N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - 14  ;

l 6.10 RADI AT I ON P R OTECT I ON P R0G R AM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-15 i 6.11 H I GH R AD I AT I O N A RE A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - 16 6.12 PROC E SS CONT ROL PROGRAM ( PCP ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-17 6.13 0FFSITE DOSE CALCULATION MANUAL (0DCM).......................... 6-17 4

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SECTION 6.0 l

ADMINISTFATIVE CONTROLS i

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4 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIB R M h d 6 The-PhtgManagershallberesponsibleforthemanagementcfthe

/{,,;Mov.1.1 erall plant and ensuring the safe storage and handling of irradiated u fuel. T Qe -P+enkManager shall delegate in writing the succession to this responsibility during his absence.

e s coriikj 6.1.2 The Watch Engineer (or during his absence from the Control Room -

des @atR-14 cme ++perator) shall be responsible for the Control Room (vel t

command function. A management directive to this effect, signed by the ce Nee h ko#*$

- President,_Difdcs-of-Nuolead(shall an annual basis. ,,, % g,j ,

be reissued to all station personnel on

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6.2 ORGANIZATION 6.2.1 Nuclear Organization An organization shall te established for the unit in the DEFUELED MODE and for corporate management, This organization shall include the positions for activities affecting the safe storage and handling of irradiated nuclear fuel,

a. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all organization positions involved with the safe storage and handling of irradiated fuel. These relationships shall be documented and updated, as appropriate, in the form of organizational charts, f unctional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivaler.t forms of de~umentation. These requirements shall be documented in the DSAR ond updated in accordance with 10 CFR 50.71(e).

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b. Th ~'tpent h lg Vice Presidentishall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and proviaing technical support to the plant to ensure the safe storage and handling of irradiated fuel,
c. The. m ershallberesponsibleforoverallunitsafetg opereth s and shall have control over those onsite activities necessarp'for safe maintenance of the plant and storage and handling of irradiated fuel.

ou rstion s

d. The individuals who train the4perat4gstaff and those who arry out health physics and quality assurance functions may repo. 3 l the appropriate onsite manager; however, they shall have sufficient organi;stional freedom to ensure their inoependence j from operating prestures.

SHOREHAM - UNIT 1 6-1

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ADMINISTRATIVE CONTR0ts UNIT STAFF 6.2.2 The station organization shall be a', follows:

a. Each duty shift shall be composed of at least the minist.um shift crew consisting of three operators, one of which shall be a Watch Engineer. The Watch Engineer shall hold a Senior & 4ctory F v t Hav.dli.)

OperJtatiMMcens n' SNPS Unit 1.

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b. One of the operators, as specified in 6.2.26, other than the c" @ *dy Watch Eng h ilafiiiss In.ineer t all Control the Main beJ-14u,ns4and Room. Thisqualified operatortoshoulet respond to ally nori.. any

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be in the Main Control Room when f w l is in the Spent Fuel Pool.

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c. All fuel handling operations shall be observed and direct M1c.,. W i f )

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  • suptrvise the handling of h ractated fuel, and~fIiperviTed who has no other by alMeensf operator e concurrent responsibilities during this operation.
d. A Health Physics technician shall be on site when irradiated fuel is being handled on site,
e. Adequate shif t coverage shall be maintained withcut routine heavy use of cvertime. The objective shall te to have operating I personnel work a normal 8-hour day, 40-hour week. However, in the event tnat unforeseen problems require substantial unour.ts of overtire to be used, or during extended periods of fuel movement, n.ajor maintenance, or r.:ajor unit modification, on a temporary basis the following guidelines shall be followed:
1. An individual should not be permitted to work more thin 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-h sur period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour pericd, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed betwt.en work pericds, including shift turnover time.

Any deviation from the above guidelines shell be authorized by the41 ant [*8;hd Manager or his deputy, or higher levels of management.

6.3 UNITSTAFFOVAllFICAT10NJ 6.3.1 Each member of the unit staff shall meet ur exceed the minimum qualificaticns of the program and precedures as outlined in Section 13 -

  • CediUcait, cf persennel pofermiq des e. b c H en s sh11 k is nuo</an, whk 4ke licusee ,

N^t aprve.ed orti%.H, trep m .

SHOREHAM - UNIT 1 6-2

ADMINISTRATIVE CONTROLS _

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Conduct of Operations, of the Defueled Safety Analysis Report for comparable positions.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the station staff shall be maintained under the direction of the Training Supervisor, shall neet or exceed the requirements of the programs and procedures as outlined in Section 13.2 - Training Program, of the Defueled Safety Analysis Report.

6.5 REVIEW AND AUDIT 3 crc (.t rt c)_

6. 5. GMVI EW.OF-OPMATIONS, COMMITT E E AME)2 FUNCTION y Rc s ideat 6.5.1.1 Th -%shall function to advit.o .1thgdlangManager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 Th shall be composed of 6 e airma or alternate chairman and (8'* " #

-hr members y or alternate members of the lant taff as designated by the chairman. F ALTERNATES ,

6 70 . Rel 6.5.1.3 All alternate membeTs shall be appointed in writing by th h Chairmen; however, no more than g alternate'f.. hall participate as.ayvoting member]ing tivities at any one time.

HEETING FRED t CY 6.5.1.4 T shall meet at least once per calendar month and as convened by t (Chairmanorhisdesignatedalternate.

9ff* *ike. terms " o/ e tatita " and " opt /afice s" g g us.' ( h e /e in er{c e to a c Ne a f by licensee pto cane l an d u fili s.afic a cf .3h rec kam . e s and eg vi/ ~eaf to sujpert' activifies which Ave r eg,ir,/ ia fke O E. F V E L. E P Fi ck er eihte non.pferadiej / lant (anil urA+ifM, 3

iocluding, but' apf )*mitti f o, 3.t 4 8 fuel St* 3f Awd handlin$,radiala3i cal centret,

,y SHOREHAM - UNIT 1 6-3

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APPINISTRATIVE CONTROLS QUORUM (SRC 6.5.1.5 The quorun of th ROLnecessary for the performance of theh0CA Q&

responsibility and authurity provisions of these Technical Specifications shall consist cf the Chairnan or his designated alternate andrtwo,other inember s iricluding alternates.

RESPONSIBILITIES 6.5.1.6 Th (shallberesponsiblefor:

a. Review of (1) all proposed procedures required by Specification 6.7 ar.d changes thereto, (2) all proposed programs required by Specification 6.7 and changes thereto, arid (3) any other proposed procedures or chariges thereto as deterrr.ined by tg. Plant Manager tu affect nuclear safety;
b. Review of all proposed t:sts and experiments that affect nuclear safetx- (s.,s....,,;..ca,u......nn
c. FeviewofallproposedcEangesto[AppendixATechnical Specificatter.s;
d. Review of all proposed changes or incdifications to unit systeras or equipment that af fect riuclear saf ety;
e. Investigation of all violations of the Technical Specifications, including the preparation ara forv6rding of reports covering evaluation and recomendations to prever.t recurrence, to the Es ce wWe,.xasWigVice President { of here6 f r.ie c+;
f. Review of all REFORTABLE EVENTS;
g. Review of stat.icn operations to detect potential hazards to nuclear safety;
h. Performance of special reviews, investigations, or analyses and

. reports thereon as requested by the R1 ant;' Manager; (6 Tel e n t

i. Review of the Security Plan and'EpTEY).enting procedures;
j. Review of the Emergency Plan and implementing procedures;
k. Review of the fire Protection Plan and implementing procedures; SHOREHAli - UNIT 1 6-4

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ADil1NISTRATIVE CONTROLS -

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1. Review of the proposed changes to the Process Contiti Program (PCP);
m. Review of the proposed changes to the Offsite Dose Calculation ,

Manual (0DCM); l

n. Review of the proposed Major Chenges to Radioactive Waste Systems;
o. Review of Personnel Radiation Records annually to determine how exposures might be lowered consistent with ALARA principles.

Document such considerations; and l l

p. Review of any accidental, unplanned, or uncontrolled radioactive i release including the preparation of reports covering evaluation, recommer.dations, and disposition of the corrective action to ,

i Eyee.,4:n, prevente4recurrence and the forwarding Vice President of St.ecek.of these /,,pe4,reports to the -

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6.5.1.7 Th shall: (q- i,a,. a y.n,a

  • u rend rece==.'ssq a...,e 4. a<

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Ae s;4e a.- Recommend in writing to t g  %.Hanager approval or disapproval of items considered under Specif < cation 6.5.1.6a. through d. and n prior to their implernentation.

b. Rendct determinations in writing with regard to whether or not each item considered under Specificatior 6.5.1.6a. through e.

above constitutes an-unrevicwed safet estion. m. .

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c. Provide written rictification within 2 [ ours to ChEJW Vice PresidentAuf disagreement betweenTR%end the +1entiResidewi

,, ,,, Manaaer; however, the-W4'4anager shall have responsibilit e for resolution of such disagreemen s pursuant to Specification $ 1.1.-

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RECORDS rec sac SRC 6.5.1.8 Th Esha11 raaintain written minutes of each E meeting that,  :

at a rainimum, document the results of all . activities performed under the responsibility provisions of these Techn cal Specifications. Copies shall be provided to therresponsitrgVice Presidentfand the4weleetg~iew foM),

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SHOREHAM - UNIT 1 0-5  !

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I At't:1N!STRAT1YE C0hTROLS p

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TE2 NUCLTd[~REV1frBOARD~(PE)' a 7

FUNCTION /

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6.5.2d The NRB'shall function to provide independent review and audit of, ,

fesigiiated activities in' the areas of:

,/ eb.c...[ Nuclear ~ engineer.ing, Chemistry and' radiochemistry,

' Radiological safety ,

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..d. Mechonical and electrical engineering, and

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Quality assurance practices.

TheJRB shall report to and advise the Vice President, Of fice of Nuciver/

,orr'those arcos t,f responsibility in Specifications 6.5.2.7 and 6.SI.B. ,.

COMPOSITION /

6d.2.2 The NLB shall be composed of the permanent NRB Chairman ind a minitaum of four permanent NRB members. The chairman and all.-rembers of NRB shcIl have qualifications that meet the requirements--of Section of4d,thft L ANS1/Ah5 3.1-1978. '/ 3~

fThe mer.bership shall include at least one ir lividual f rom outside LILC(Ps,s; j

or its contractors organizations and at lee, t one individu61 with,subston-tial nuclear experies.ce. ThL nuclear experv$nce may- be provided by the  !

'incividual who is f rom out;,ide LILCO's or iih contractors' org6nizations./

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ALTERfikTES /

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6.5.2.3 All alternate trenbers shalT be app (V,1ted 'in wt iting-bj the NRS,/i _

Chairran to serve on a temporary basis; howthr, no more than one aljernatti s, hall participate as votirg members in NRB aItivities at any one,tde.

CONSULTANTS E /

~ eg (E(2.4 Consult' ants shall.be utilized as deterrnned bj the NPB ChNrman to provide e'xpert advice'to the NRB.

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MEETIhGFRE00ENCY' f / -

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.h tSJ1Jhi_ NRB shal}rEet at leap'6nce per,st( months./'

SHOREHAft - UNIT 1 6-0

l, IMURT_A 6.5.2 ltWEEElWIFT REVIFLrminL_UEE1 The licena o shall retain an Independent Review Panel to serve as an adv. ory body to LIPA's Board of Trustees, and to provide LIPA's Board of Trustees with an independent basis for evaluating the conduct of licensed activities with respect to nuclear safety, regulatory compliance, and overall management effectiveness. The responsibilities of the IRP shall be delineated in a written charter approved by the licensco's Board of Trustees.

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ADMINISTRATIVE CONTROLS i

QUORUll

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.2.6 The-quorum of the NES riecessary for,th perforinance of the'd5 review and audit functiobs-of these Technical Specifications,shall consist of th4' Chairman or his"' designated alternate and at least thfee but not,less

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t ,han one-half of-the NRB rnenbers-prisent including alternates. No more.

than 6 rninorit'y of the quorum-shall have line responsibility for operation of the-otiit, f' / -

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I, REVIEW '

p l6. 5.2.?'/p/ The NRB shall, review:

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The,safetyevaluations_for'(1)changestoequidentorsystems a.

arid (2) tests or experinents completed under tie provis, ion-bf 10 CFR 50.59 to verify that such actions did not consitit0te an 4

unreviewed-safety question;~ ' /

Pr0,/posed " anges _- to. procedures, ,

equipo.ent, or systen:s w be p/yinvolve an unreviewed safety question es defined in 10'CTR - 50.59;

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c. Proposed' tests or experinei,its which involvu ati'unreviewed safetf

,quLstion as defined-in 10 CFR 50.59;'. / / '

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/ d. Proposefchanges to Technic 61 Specifications gf this Possession,,/

Only-Lfcense; *

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Vio16tions of, codes, / ,/

regulationsyorders, Technical /,/

/cf,/ Specificctichs, license requirenents, or of internal procedures or instr'uctions having,puclear safety significante; -

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/'f .'7 Significant deviafions from norvial'ahd expected perforniance of station equipment-that affect-liuclear safetypy'

/ 7p-A11'/,REPORTABLEEVENTS1 -

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/ ,h. All recognized indications of-an unanticipated deffciency in so,me,/

aspect'bf design or operations of structures,' systems, or

, components that could affect nuclear safety; ar.d f'-

Reportsandmit ing minutes of the ROC.

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AUDITS / / / '

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6,5:2.8 Audits of stati6 n, activities shall'be performed under the /

Tognizance of theJiRB. These audits-shin 11 encompass: / /

The conformance/

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of-station operation /'to provisions,co ,ntained

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within the Techriical Specifjcatlons and ap/plicable license

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, conditiops 'at least on,ce-pfr 12 months; f l

SHOREHAM - UNIT 1 6-7 i

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ADl11NISTRATIVE CONTROLS AUDITS 6nued) g/(Cor1 b.

,at'least once per'12 months;The,perfornance, training and q /ualifications of

c. The results factionstakin o correct deficie cies occurring unit-equipnent, struct6res systems, or method of operation'that l p affect nuclear, safety, at least once per year; d'. The performa/nce of activitieb required by the Quality Assurance Program to meet the criteria of Appendix B,'10 CFR Part 50, at ,/ ,

l least once per 24, months

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e./,The fire protectiori prograrunatic' controls iricluding the implen$nting procedures, equipuent and program implementation aty Itast'once per 24 months' utilizing either,a qualified offsite/

licensee fire protection engineer (s) or en outside independent

/ fire protection-consultant. '

  1. f. Any ott)erirca of station o)srotion considered ap[rc riate by the ,

NRB,-Presiderit or the. Vice > resident , Of fice'of Nuclear;

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p ,./The Radiologica1' Environmental Monit6 ring Program and tbrresults Q f thereof at least once per 12 months; f'

h. The-ONSITE DOSE CALCULATI0I HANUAL and impler6In ng procedures /

/p -ft least once per 24' months; and/ f

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,/ 1. The FROCESS C6NTROL PROGRAM and-ifnplementirig procedures for i solidific'atiori of radioactive' wastes et least-orice per 24 ',.'

onth's. /

Theperfurrar3ce'lIfactivitiesrequiredbytheQuality'Asburance

/, 4 Program for'ef fluent and envircinmental monitoringit least once g[

per 12-months. '

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/,e RECORDS / p

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.9 Records-ofIRBactivitiessha1Ibeprepared,'appfoed,and distributed as 4ndicated below:p / f /'/

. Minutes of each NRB ineeting shalbbiprepared, approvell, and forwardedto-tfiePresidentand-theVicePresident70fficeof

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Nuclear within 14 days fulltiwing each meeting 7 /

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b.

p/_ Reports of reviews'Irlcompassed prepared, appecsed VicePrpident, Office and forwarded to the President'ind utlear within 14 ays following by,$pGilfication the 6.5.J corryJetion of the rep .

SHOREHA!! - UNIT 1 6-8

4 i . .

i ADMINISTRATIVE CONTROLS 7

MFTContys$ , [~ /'~ 7 Audit reports encomp'asstid by Specifjestion 6.5.2.8 shill be

/ c; forwarded to the, President, Vice-President, Office of Nucle ]- -

-and to the mana~gement posttions responsib.Wfor the areas-e dited

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within )D-days af ter ,corrpletion of the-audit by the, auditing o_rpanigation. _f _/ _ , . ' ,_,g 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The cor:rnission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 LILPart 50, and
  1. 1
b. Each REPORTABLE EVENT sh611 be reviewed by h ROCDodthe resultsofthisreviewshallbesubmittedtop.respontihlgVice President g of Shers% Preint - gee 6.7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a. The applicable procedures recorrrenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
b. The applicable procedures required to implenient the requirements of NUREG-0737.
c. Fuel handling operations.
d. Surveillance and test activities of safety-related equipnent.
e. St.curity Plan implementation.
f. Eciergency Plan implementation,
g. Fire Protection Program implementation.
h. PROCESS CONTROL PROGRAM implementation,
i. OFFSITE DOSE CALCULATION MANUAL implementation.
j. Quality Assurance Program for effluent and environtrental monitoring.

SHOREHAM - UNIT 1 6-9

ADPflilSTRATIVE C0fiTROLS w i,) ( Res'de 6.7.? Ecc(hIpocedure of Specification 6.7.1, and'chEE@ges thereto, u.e'l be reviewedbythSR0qqriortoimplementation. Thec PlanL Menager shall approve Station Adniinistrative Procedures, Security Plan impleinenting Procedures and Defueled Emergency Plan Irrplementing Procedures prior to implementation. Other procedures of Specification 6.7.1 shall be approved by the appropriete-f,4ank.. Division Manager or by the Platetfhanager prior to impleme nta tion. EachJ4 ant, Division Manager shall be responsible \for a designated set of procedure ~s'. These procedures shall be reviewed N m.

pericdically es set forth in administrative procedures. (#3i/M 3

~ .s 6.7.3 Temporary changes to procedures of Specification 6.7.1 may be made provided:

a. The ir, tent of the original procedure is not altered;
b. The change is approved by two member; of the unit management staff, at least one of whom holds 6 Senior} Reactor Operators c u4iora h L b ast on the unit affected; e L__n g(.H e.d sk)
c. The chafde is documented, reviewed by thq-ROC'r ar.c approved by dhe@4as+t3^ Manager within 14 days of implementation.

(2 es id e.Q 6.7.4 The Gilcwing programs shall be established, implernented, and maintained:

a. Fadioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the contrul of radioactive etfluents and for maintaining doses to MEMBERS Of THE PUBLIC from radioactive effluents as low as reescnabl The program (1) shall be ccntained in the ODCM, (2)y achievable.shall be ir.plemented by operating procedures, and (3) shall it clude rettedial actions to be taken whenever tie progrorn linits are exceeded. The program shall include the following eierents:
1) Limitations on the operability of radioactive liquid and caseous monitoring instrumentation including surveillance

.ests er,d setpoir.t determination in accordonce with the methodology in the ODCM.

SHOREHAM - Uti1T 1 6-10

ADMINISTRATIVE CONTROLS t

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS ,

conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and g6seous ef fluents in accordance with'10 CFR 20.106 and with the methodology and p6raneters in the ODCM,
4) Limitations on the annu61 and quarterly doses or dose comtiitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released itcm each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,
5) Determination of cunulative and projected dose contributions from radioactive ef fluents for the current celendar quarter and current calendar year in accordance with the nethodology and pararneter s in the ODCM at leact every 31 days,
6) Limitations on the operability and use of the liquid and gaseous effluent treatment systtms to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guicelines for the annual dose or dose coonitment conforming to Appendix 1 to 10 CFR Part 50,
7) Linittations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated witi 10 CFR Part 20, Appendix B. Table II, Colunm 1,
8) Limitations on the annual and quarterly air doses resulting ,

from roble gases released in gaseous effluents from each unit to breas beyond the SITE BOUNDARY conforcing to Appenoix ! to 10 CFR Part 50, I

l SHOREHAM - UNIT 1 6-11

ADMINISTRATIVE CONTROLS i 9) Limitations oa the annual and quarterly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
b. Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and rodionuclides in the environs of the plant. The progtam shall provide (1) represt:ntative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure athways. The program shall (1) be containe.d in the ODCM, 2)conformtotheguidanceofAppendixI to 10 CFR Part 50, and 3) include the following:

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1) Monitoring, sampling, 6nalysis, and reporting of raoiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.
2) A Land Use Census to ensure that changes in the use of areas at and beyono the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
3) Participation in a Interlaboratory Comparison Program to -

ensure that independent checks on the precision and accuracy of the nieasurements of radioactive materials in envirunmental sample rustrices are performed as part of the quality assurance program for environmental monitoring.

SHOREHAM - UNIT 1 6-12

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ADMINISTRATIVE CONTROLS 6.8 REPORTING REQUIREMENTS R0lnINE REPORTS 6.8.1 In addition to the appifcable reporting requirements of Title 10, )

Code of Federti Regulations, the following reports shall be submitted to )

the Regional Adu.snistrator of the Regional Office of the NRC unless  !

otherwise noted. l ANNUAL REPORTS 6.8.1.1 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of- ,

each: year. The initial report was submitted prior to March I of the year l that followed initial criticality, l

l 6.8.1.2 Reports requirea on an annual basis shall include a-tabulation on

! an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their 6ssociated manrem exposure according to work and job functions * ',

L (e.g., operations and surveillance, inspection, routine maintenance, specialmaintenance(describemaintenance),wasteprocessing,andfuel handling). The dose assignments to various duty functions ma L

based cn pocket dosimeter, thermoluminescent dosineters (TLD)y be estimated

, or film badge measurements. Small exposures totalling less than 20% of the-individual total' dose need not be accounted for. In the aggregate at i

least 801 of the total wholebody dose received from external source,s should be essigned to specific major work functions.

l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 The Annual Radiological Environmental Operating Repcrt covering the' operation of the unit during the previous calendar year shall be submitted before May 1!of each year. The report shall include summaries, interpretations, and analysis of trends of tie results of the Radiological ,

Environmental Monitoring Progrcm for the reportir4g period. The material l provided shall be ccnsistent with the objectives outlined in (1) the ODCM l and (2) Sect'c: s !V.B.2,'IV.B.3, and !Y.C of Appendix 1 to 10 CTR Port 50.

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-*This tabulation supplements the requiremmts of 20.407 of CFR Part 20.

SHOREHAM - UNIT 1 6-13 I

4 ADMINISTRATIVE CONTROLS l

SEM1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of oper ation shall be submitted within 60 days af ter January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid ^e released from the unit. The material providedshallbe(1)consi' a. with the objectives outlined in the ODCM and PCP anc (2) in conformance with 10 CFR 50.36a ar.d Section IV.B.1 of Appencix 1 to 10 CFR Part 50.

SPECIAL REPORTS 6.8.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the hRC within the time period specified for each report.

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,6 . 9 RECORD RETENTION 6.9.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.9.2 The following records shall be retained for et least 5 years:

a. Records and logs of fuel handling operations.
b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
c. All REF0FTABLE EVENTS.
d. Records of surveillance ottivities, inspections, and calibrations required by these Technical Specifications,
e. Records of changes made to the procedures required by Specification 6.7.1.
f. Records of radioactive shipments.
g. Reccrds of scaled source and fission detector leak tests and results.

SHOREHAM - UNIT 1 6-14

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,1, ADMINISTRATIVE CONTROLS

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h._ Records'of annual physical inventory of all-sealed _ source material of record.

6.9.3 The following records shall be retained for the duration of the unit

.-OperetfgLicense:

a. Records and drawing changes reflecting station design modifications made to systemc and equipment described in the e

-F4r4 Safety Analysis Report,

b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup_ histories,
c. Recurds of radiation exposure for all individuals issued nMtoring devices in accordance with 10 CFR 20.202.
d. Records-of gaseous and liquid radioactive material released to the-environs,
e. Records of training and qualification for current members of the unit. staff.
f. Records of quality assurance activities required by the Quality Assurance Manual which are not listed in Section 6.9.2.

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g. Records of reviews performed for changes made to procedures or equipment-or reviews of tests and experiments pursuant to 10 CFR 50.59.

h._  : Records. of meetings of the-600-nd-NRBy SAC 6d 3 % a d ' f ""+ i"fd d n,e uteaa w of c,><r w e s c e-i tt ee a.J % sea < wic~ Gosd h*'d % %

i. Records of analyses required by the Radiological Envirorunental "W r _ Monitoring Program that would permit-evaluation of the accuracy of-the analysis at a later date. . This shoulcf include procedures-effective at specified times and-QA records showing that these

-procedurec were followed.

j. Records of. reviews performed for changes made to the OFFSITE DOSE i- CALCULATION MANUAL and the PROCESS C0llTROL DR0 GRAM.

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l_ 6.10 . RADIATION PROTECTION PROGRAM ,

6.10.- Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, j_ maintained, and adhered to for all operations involving personnel radiation L

exposure.

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SHORrHAh - UNIT 1 6-15

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ADMINISTRATIVE CONTROLS 6.11 HIGH RADIAT10M AREA 6.11.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrems/h but less than 1000 mrems/h shall be barricaded and conspicutusly posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring uevice which continuously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiatien dose rete iri the area and clarms when a preset integrated dcse is r+ceived. Entry into such areas with this mcnitoring device w be made after the dose rate levels in the crea have been estat ;4hed and personnel have been made knowledgeable of then..
c. A health physics qualified individual (i.e., qualified in radiction protection procedures) with a radiction dose rate tronitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specifieo by the Health Physics Engineer in the RWP.

6.11.2 Ir addition to the requireeents of Specification 6.11.1 areas accessible to persor.nel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrems shall be provided with locked door s to prevent unauthorized entry, and the keys (

shall be traintained under the administrative control of the Watch Supervisor-on duty end/or the Health Physics Engineer. Doors shall remain locked except during period > of access by personnel under an approved RWP which shall specify the dose rate levels in the innediate work area and the maximum allowable stay time for individuals in thct area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems** that are located within large areas, such as the containment,

  • Health physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
    • Measurenent made at 18 inches from source of radioactivity.

SHOREHAli - UNIT 1 6-16

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6 .

ADMINISTRATIVE CONTROLS t

where r.o enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, continuous surveillance, direct or rcmote (such as use of closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide exposure control over the activities within the area.

6.12 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.3.j. This documentation shall contain:
1) Sufficient informution to support the change together with the appropriate analyses or evaluations justifying the change (s) and
2) A determination that the c.hange will maintain the overall conformance of the solidified waste product to existing requirements of federal, State, or other applicable regulations.
b. Shall become effective af ter review and acceptance by the ROC and the approval of an Manager.

6.13 0FFSITE DOSE CALCULATIM .ANUAL (0DCM)

Changes to the ODCM:

d. Shall be documented and records of reviews perforned shall be retained as required by Specification 6.g.3.j. This documentation shall contain:
1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and SHOREHAM - UtilT 1 6-17

ADMINISTRATIVE CONTROLS (Continued)

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations, falc)
b. Shall become effective af ter review and acceptance by-R0gand the approval of_the # 3a Manager Qe siseoe)to the Commission in the form of a complete, Shall be subdit c.

legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the 00CM was made. Each change shall be identified by inarkings in the mergin of the affected pages, cle6rly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was intplemented.

SHOREHAM - UNIT 1 6-1P

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APPENDIX B TO FACILITY OPERATING LICENSE NO.

SHOREHAM NUCLEAR POWER STATION, UNIT 1 fowER AvT'H ct rry LONG ISLAND 4:4GHT1HG-COMPAN DOCKET NO. 50-322 ENVIRONMENTAL PROTECTION PLAN (NON-PADIOLOGICAL)

SHOREHAM NUCLEAR POWER STATION UNIT 1 dl[YIEGliPINTAL-PROT 6GT40N-PLAN %

ck

- (NON-RADIOLOGICAL-)

-June-141-1991 I

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