ML17333A465

Proposed Tech Specs Re Administrative Controls Related to QA

ML17333A465
Person / Time
Site:	Cook
Issue date:	06/11/1996
From:	AMERICAN ELECTRIC POWER CO., INC.
To:
Shared Package
ML17333A466	List: ML17333A465 ML17334B589
References
NUDOCS 9606180607
Download: ML17333A465 (135)

Text

INDE+

ADMINISIRATIVECONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organization.................

F~~t

~~lty Staff.

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

o 6 I

~

~

~

~

~

o

~

~

o 6 I 6.3 FACILITYSTAFF UALIFICATIONS

~

~

~

~

~

~

~

. 64 6<<4 TRAINING

~

~

~

~

~

~

~

o Q'.5 EVIEQPA'%$-AUDIT 6.5. I PLANT NUCLEAR SAFETY REVIEW COMMITTEE 6D.2 F

a unetlon

~

~

~

.......e e

~

~

~

o o

~

~

~

~

oo\\ v~

Co~ signa<<

~

~

~

~

~

~

~

~

~

~

~ <<. ~

~

~

~

~

~ 64 AI vg" aaa tCmatCS

~

~

~

g a

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ og ~

~

~

~

~

~

~

~

~

o 6 5 Meetmg Frauen

~...-,.............. 'o............,i........ ~.... 6-5 Quorum

~

~

~

e,

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ <<eo

~

~

~

~

~

~

~

~

~

~

~

~

~

~ 6 5 Responsib'tlcs

~

~

~

~

~

~

~

~

~

~

oooo

~

~

~

~

~

~

~

~

~

~ og

. 6-5 Authoritjj

~

~

~

~

~

~

~

'oaao

~

~ <<~~ e

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

Records

~

~

~

~

~

~

~ gee

~

eaaq o

~

~

e

~

~

~

~

~

~

~

~

~ 6<<6 NUCLEAR SAFETY AND DESIGN'RIcVIEWCOMhEITEE~.,

Funetlon

~

~

~

~

~

~ ~, ~

o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ eve

~

~

~

~

~

~

~

~

o &6 Composition...

~

~

~

~

~

o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

o

~

~

~

~ 6 7 r

Alternate MCmbCIS

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ e

~

~

~

~ ~ ~ o ~ ~

~

~

~

~

~

~

~

~

~

oa ~

~ 6 7 I

~

I r"

I 960Ei80607 96Dhii PDR ADOCK 050003i5 P

PDR COOK NUCLEAR PLANT-UNITI AMENDMENTQl, ~, ~, Ig9 J

~

ls 0

,Pg

VE CO 0

SF~/ON 6-8

.,5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE (Continued)

Caa-aaltaata................................

6-8 Meeting Frequency........................

~

rr+

QUODllo ~

~

~

~

~

~

~ ~ ~ ~ ~ ~ o 6 o

~ ~

~ ~ ~ ~ ~ ~ ~ ~ o<t

~

~

o ~ ~ ~ e ~ ~ ~ o ~

o ~ ~ ~ e i~

Revi eve

~ ~

~

~

~

~

~

~

~

~ ~

~

~

~

~ ~

~ oar o

~ oat

~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o o o o e ~ o 6

8 Audits........... -....,..............

6-9 Aut>ority/i~

~ ~ ~ ~ ~

~

~

~

~

~

~

~

~ ~ ~

~ ~

~

~

~

~

=

~

~ o

~

~ ~ ~

~ ~ o o o>o

~ ~o ~ ~ ~ ~ ~ ~ ~ ~ o 6 10 Records.1

~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ \\o ~ E..j 6-10

.6~5.3 TECHNICAL REVIEW AND CONTROL..............................

6-XO~,

6 6

EPOR BEE EVE CTION 6

S 5

L T

0 ION

~ ~ ~ ~ ~ ~ ~ ~ e

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ o ~ ~

6 ~roooo 6

8 P

OCEDURES AND ROGRAMS............................

6 9

POR G

E ENTS....

6.9.1 ROUTINE REPORTS...........................................

6-~ V 6.9.2 SPECIAL REPORTS...........................................

6&v /3 0 ~E TEg 6

0

/

ECORD ET O

~ ~ ~ ~ ~ ~

~ ~

~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ ~

~

~

~

O e eoe'eoreeeaoroeoa'r eoe rr e oa

~oooo~

RAD ION PRO ECT ON 0

6-20 GH D

0 6

3 OC SS CO 0

OG l5 C.............................

6/

6 4

OFFS TE DOSE C L 0

OD 6+2 t 5 COOK NUCLEAR PLANT - UNIT 1 XVII AMENDMENT NO. 69, 4QO, 454, 189

ATTACHMENT 2 TO AEP:NRC:80027 EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED TO REFLECT THE PROPOSED CHANGES

0-

MIN STRATIV CO 0

6.3 FACILITY STA UALIFICATIONS 6.3.1 Each member of the facflfty staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, excepe for (1) the Plant Radi.ation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shfft Technical Advisor, who shall have a bachelor's degree or equivalent in a scieneific or engineering discipline arith specific training in plant design, and response and analysis of the plane for transients and accidents

and, (3) the Operations Superintendent who must hold or have held a Senior Operator License as specified in Secti.on 6.2.2.h.

6.4 TRAINING 6.4.1 A retraining and replacement tzaining program for the facilfty staff shall be maintained under the direction of the Training Manager and shall meet or exceed ehe requirements and recommendations of Section 5.5'f ANSI H18.1-1971 and 10 CFR Part 55.

6. 5 R

~OXZ, 9 FLEW' 5

P NUCLEAR SAF REV EP CO EE NS C

ON 6.5.1.1 Th PNSRC shall function to advise the Site Vi.ce President/Plant Manager, or de

'e, on all matters related to nuclear safeey.

COMPOS ON 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reportf'ng dfrectly to the Site Vice President/Plant Manager, Assistant Plant Manag~es oz Departmene, Superfntendenes.

The membership shall repzesent the functfonsl areas of the plant, including, but not limieed to Operations, Technical Wu port, Licensing, Maintenance and Radiation Protection.

The PNSRC membership shall consist of at least one individual from each of the areas designated.

Allmembers,.fncluding the Chairman and hfs alternates, the membezs and their alternates, shall be designated&by the Site Vice P esfdent/Plant Manager.

PNSRC members and aleernates shall meet or exceed the minimum qual~catfons of ANSI N18.1-19+7+Section 4.4 for comparable positions.

The nuclear power pLant operations Pndfvfdual shall meet the qualifications of Section 4.2.2 oG ANSI N18.1-19+1 except foz the requirement to hold a current Senior Operator License.

The operations indivfdual must hold or have held a Senior Operator License at. Cook Nugceaz Plant or a similaz reactor.

The maintenance individual shall meet the

~

~

~

qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT - UNIT 1 6-4 AMENDMENT NO. 40, 63, 434, 454r --6 t

192

~ g l

<aegir y)

XSTRtLTKV CONTROLS 6..I,.3 No more than tvo alternates shall participate as voting members Qx PN C activities at any one time.

HtE UEHCY 6.5.1.4 Tha PHSRC shall meet at least once per calendar monthiand aa convened b

the PHSRC Chairs or his designated alternate.

QUORUM 6.5.1.5 h quorum of the PHSRC shall consist of the. i~ or his designated alternate and at least three membazs including alternates..

RESPONSIEZLZTZ S

6.5.1.6 The PHSRC shal be responsible for:

a.

Reviev of aU. Plant Manager Zxxstmctions (2KB) and revtsions the eto.

b.

Reviav of safety evaluations for (1) plant sita procedures and revisions thezeto vhich~af+act che nuclear safety of the plant; (2) changes or modificatibas to nuclear safety-related s~~es, systems or components; and (3) tests oz experiments vhich affect plant nuclear safety to vert y, that such ac ions did not const'tuta an unrevieved safe question as defined in 10 CH. 50.59.

c.

Reviev of (1) proposed procedures anc3I revisions to procedures, (2) changes to equipment,

systems, or facQ.itias, and (3) proposed tests or experiments vhich may involve an unraviaved safety question as defined in 10

~c 50.59.

r d.

Reviev ofyproposad changes to hppendix "4" Technical Spec~~ications or the Operating License and rendering determinations in vziting virh regard to vhether or not the proposed change'constit"tas a

Signi icant Hasazds Consideration.

/

e.

Znvce'stigation of all violations of the Technical Speci"icat'ans including the preparation and fozvazdixxg of reports cove~g evaluation and recommendations to prevent recur=ance to zhe"-,

Cha~ ~ of the HSDRC.

Eaviev of all RHORTABLE EVENTS.

g.

Raviav of facility operations to detac" potential nuclear safety ha=ards.

~l~

VAP COOK HOCH P~~

->>UNXT"'L 6-5 "hHRKHENT.HO,.)), >g 15$

~ g

ONTROLS h.

Performance of special reviews, investigations of analyses and reports thereon as requested by the Chairman of the NSDRC.

Deleted.

DeLeted.

k.

Review of any accidental, unplanned, or unconeroll radioactive xelease i.ncluding the preparation of reports covering evaluations, recommendations, and disposition of the corrective action to prevent xecurrence and the forwarding of these repores eolthe Senior Vice PxesSdent

- Nuclear neraeion and to ehe NSDRC.

Reviewjof changes to the PROCESS CO OL PROGRAM, OFPSITE DOSE CALCULATIGH MANUAL, and xadwaste eatment system.

AUTHORITY 6.5.1.7 The PNSRC shal3.:

ae b.

Cn Reoornend to the Eire Vine President/Plant Manager, or designee, j

written approval orldisappxoval of items considered under 6.5.1.6

/

(a) throngh (d) aho e.

Render deeermin~ions n writing with regard to whether or not each item ccnsgfered un r 6.5.1.6 (a) through (c) and (e) above constitutes an unreviewe safety question.

Provide wr tten notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice

/

President - Nuclear Generaei n and the NSDRC of disagreement between~the PNSRC and the Si@ Vice President/Plane Manager;

however, the Site Vice Pre si nt/Plane Manager shall have responsibility for resolution of ch disagreements pursuane eo 6.Z'.1 above.

CO 6.5.1.8 The PNSRC sha11 maintain written minutes of eac meeting and copies

~ be provided to the Chairman of the NSDRC.

6 CL DES GN SD C

/

~CXXON

.2.1 The HSDRC shall function to provide independent review and a it of designaeed activities in the areas of:

nuclear pogger plant operations nuclear engineering COOK NUCLEAR PXANT - UNXT l '-6.,-,.:,.-AMENDMENT.NO.

'92 n e

KLNISTRATIVE CONTROLS LC'hemistry and radiochemistry d.

metallurgy e.

instrumentation and control radioI'ogical safety mechanical~and electrical engineering h.

quality assurance practices f

f 6.5.2.2 The NSDRC shall be composed of the 'following regular members:

l l.

Senior Vice President

- N lear Generation (NSDRC Chairman) 2 0 Manager

- Nuclear Safe@,

Licensing, 6 Fuel Division (NSDRC Secretary) 3 o Site Vice President/Plant Manage

- Donald C. Cook Nuclear Plant

/'

4 ~

Vice President

- Indiana Michigan Power Company 5.

Executive Vice President

- Engineering 6 Construction a

6.

Vice President/

Transmission and Distribution Services 7 o Senior Vice President - Fossil and'Hydr Generation 8.

Zanager - Nuclear Engineering Department 9

Vice President

- Civil Engineering 1O.

Nanagor/

Nucloaz plant gnginooring Support iviaion 11.

Manager - Nuclear. Suppox't Sexvices Department 12.

Manager - Quality Assurance Department 13.

Manager - Production Support and Administrative Services Section Additional members and Vice Chairman may be appointed by the President and Chief Operating Officer.

f anuu -

6.5.2.$

Designated alternate members shall be appointed by the Presidexxt and Chief Operating Officer or. such other person as he shall designate.

In addition, temporary alternate. members may be appointed by the

/

NSDRC Chairman to serve on an interim basis, as required.

Temporary alternate meabers are empowered to act on the behalf of the regular or designate

/alternate members for whom they substitute.

~o~~~

~

t~~% t~

COOK MJCLEAR PLANT - UNIT l J

6-7

"'""'~"-AMENDM~VZNO. M, ~ ~r 192

~j

1 t

1 l

4S'*.

~4 j

~Q",-

~ ~V'

DM CGNZROT.S 6.5.2e4 Consultants shall be utilized as determined by che NSDRC Chairman to~

provi8'xpert advice to the NSDRC.

c' EUNCY 6.5.2.5 The NSDRC shall meet at least once per six months.

,F QUORUM e

sr

~

~

6.5.2.6 A quorum, the minianum number of regular members and.alternates required to hold a NSDKC meetin~sha1.1 be eight members, of whom no more chan two shall be designated or temporary 'alternates.

The Chairman or acting Chai~an shall be present for all NSDRC meetings.

If the number of members present is greater than a quorum, then the maj rity participating and voting at the meeting shall not have line responsibility or operations of the facility.

For the purpose of a quorum, only the Plant Mana r is considered to have line responsibility.

i'gV~EV s

6.5.2.7.

The NSDRC is responsible or assuring that independent reviews of the following are performed:

a.

The safety evaluations for 1)'anges to procedures, equipment or systems and 2) tests or experim nts completed under the provision of 10 CFR 50.59 to verify that such ac ons did not constitute an unreviewed safety question.

vr b.

Proposed changes to procedures, equippent or systems which involve an unreviewed safety question as defined 10 CFR 50.59.

c.

Proposed tests or experiments which invol an unreviewed safety question as defined in 10 CFR 50.59.

d.

Proposed changes in Technical Specifications o

this operating license.

a e.

Violations of codes, regulations,

orders, Technicaj Specifications, license'equirements, or of internal procedures or %nstructions having nuclear safety significance.

f

• Regnlac NSDRC aeabers are erpeoted to attend the nearing chanc er possible, and alternates may attend as voting members only on an irregular basi If boch a regular member and his alternate attend a meeting, only the regular m mber may particf'pate as a voting member, and the alternate is considered a guest.

Independent reviews may be performed by groups which report directly o

the NSDRC and which must have NSDRC membership participation.

vv ec a COOK NUCLEAR PLANT - UNIT,I~ '6=8 AHENDHEHT. NO., AC, 154 (

~'IAAVIVe<<sef

~ <<e<<ere e o

<<<<'ve'.~~<<j

~j

J

~

le MINISTR'ITIVE COHYROLS-All REPORTABLE PtENTS.

C e.

Significant operating abnormalities or deviacions from normal an@'xpected performance of plant equipment that affect nuclear'afety.

h.

Allrecognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related'tructures,

stems, or components.

Repm;cs and meeting minutes of the PHSRC.

tIUD2TS f

6.5.2.8 Audits of faciliq activities shall be performed under the cognizance of the NSDRC.

These audi shall encompass:

a ~

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions ac leasg once per,'12 months.

~

~

e b.

The performance,

training, and qualifications of the..entire facility staff at leasi'oence per 12 months.

J I

The results of actions ta en to correct deficiencies occurring in facilityequipaent, structures, systems or. method of operation that affect nucleir safety at~least once per 6 months.

d.

The performance of activities required by the ~J.ty Assurance Program to meet the criteria of Appendix "B", 10 CE 50, at least once per 24'months.

Deleted ~

f.

Deleted.

~

g-The fire protection programmatic controls including the implementinf procedures at lease once per 24 months by qualified licensee QA personnel.

h.

~'he fire protection equipment and protean implementation at least once per 12 months using either a qualified offsite licensee fire protection engineer or an outside independenc fire protection y'onsxQ.taat.

An outs@de independent fire protection consultant shall be used at least every third year.

\\

/

I

/

The Radiological Environmental Monitoring Program and the resulcs'e thereof at least once per 12 months.

~

I I

I I

CdOK"NUCLEAR PMT - UNIX 3=.:-,. 6-9 AMENDMENT NO. 8"

'92- -....,.

~ s

Jl I

k.

The OPSY:=

DOSE CALCULATION MANUAL and ~glementing procedures t j, 1east once per 24 months.

s The PROCESS CONTROL PROGRAM and implementing procedu"es for'olid'~ication of radioactive wasps at Least once per,.24 months.

The performance of activities required by the Quality Assurance Prog=am to meet the criteria of Regulatory Guide le21, Rev.

1, June 1974 and Regulatory Guide 4.1, Rev. 1, April 975 at least once pez 12 months.

Any other area of facility opera%on considered appropriate by the SDRC.

+VP(ORT~

6.5.2.9 The NSDR~shall zepoz-to and advise th Vice President.

- Nuclear Operat oILs s

AEPSC, b

those areas of responsibility speci ied in'ections 6.5.2.7 and 6.5.2.8.

~oCOROS 6.5.2.10 Records of NSDRC activities shall be prepared, approved and disa"ibnred as mdioared bolo a.

Minutes of each NSDR meeting shall be prepared, approved -znd-

~

issued within 14 days/following each meeting.

b.

Report of reviews encompassed by Section 6.5.2.7 above, shall be praparedepp,roved and isaac wirhfn 14 days following eonpierion of the review..i'.

Audit reports encompassed by Sec" on 6.5.2.8 above, shall be

~

fores=dad.'ro the Visa Presidann

- Noclear Operarions, A~SO, and to the management positions responsibl for the a eas audited wi~~

30 days after completion of the a dit.

6 5

3 CHNTCAL R Bl CO 0

6.5.3.1 Activit'es which affect nuclear safety shalL be c ducted as follows:

s a..

Procedures required by Specification 6.8 and othe~procedures which affect plant nuclear safety, and changes thereto, shall be

prepared, reviewed and approved.

Each such procedur~or procedure change shall be zevf.ewed by a q~Lified individual/group:

r other than the individual/group Wch prepared the procedure or procedure

change, but vho may be

~rom the same organi=attn as ehe indivi.dual/group which prepared the pzocedure or pzocedu e

change, P ocedures other than Plant Manager Procedures COOK HUC~ Pv~-'i NO. ~,~ jjl

II I

MTNISi b.

C d

/

/

CONTROLS i

'"f shall.

be approved by the eppropriaee department head as' reviously designated in vriting by the Site Vice President/Plane Manager, or designee.

The Site Vice President/Plane Manager;- or

designee, sha11 approve Plant Manager Procedures.

Temporary changes to procedures vhich do not change the intent.'of ehe approved procedures shall be approved for implementati/on by evo members of the plant staff, ae least one of whom holds a Senior Operator license, and documeneed.

The temporary.changes shall Be approved by the ox'iginal approval authority vi,thin 14 days of implementation.

For changes to procedures vhich may involve a chinge in intent of the approved procedures, the person authorized above to approve ehe procedure'hall appx'ove ehe changeiprior to implementation.

,/

Proposed changes or modifications to plant nuclear safety-related structures,';

systems and components'hall be revieved as designated by the Site Vice President/Plant Managere or designee.

Each such modificaeion shall be reviewed (re ference T/S 6.5.3.1.e) b a

qualified 'reference T/S 6.5.3.1.d) individual/group other than the; individual/group which designed the modification, but vho may-'be from the same organization as the individual/group vhich designed ehe modifications.

Proposed modifications to plane nuclear safety-related structures, systems and components shall he approved prior to implementation-by We Site Vice President/Plant Manager, or designee.

//

Proposed tests and expex'ts vhich affect plant nuclear safeey and are not addressed in e Final Safety Analysis Report or Technical Specifications shall be

prepared, reviewed, and approved.

Each such test or experiment shall be zevieved by qualified indivi'duals/groups 'other than ehe individual/group vhich prepared.the proposed test or experiment eo assure cznss-disciplinary,xeviev as appropriate for the proposed test or experiment. / Proposed tests and experiments shall be approved before implementation by the Site Vice President/Plant Manager',"'r designee./

Individuals vho conduceed the revievs per'formed in the accordance vith S)ecificaeion 6.5.3.1a, 6.5.3.1b, and 6.5.3.1c, shall be members of the plane management staff prevfously designaeed by the/Site Vice Presidene/Plane Manager and shall meet or exceed the minimum qualificaeions of ANSI N18.1-1971Section 4e4 for

/

/

comparable positions.

Each such reviev shell include a

determination of vhether or not additional, cross~disciplinary reviev is necessary.

If deemed necessazy, such review shall be petfoteed by tnaliffed petaonnal of the apptoptiata Qaoipline.

Each x'eviev shall include a determination of vhether o

not an unrevieved safe ty ques tion is involved.

Pursuant eo 10 CFR 50.59, NRC approval of items involving unzevieved safety questions shall be obeained prior to the approval of the Site Vice President/Plant

Manager, or designee, for implementaeiok, Deleted.

~ (

FC&T - bAIT'I

'" '""::6-11='

--=-".". -

AMENDMW

'0-

"W'0 p

~l

~r I

III I

0

6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written pmcedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended ia Appendix A of Regulatory Guide 1.33, Rev. 2, February 1978.

b.

Deleted.

c.

Deleted.

d.

PROCESS CONTROL PROGRAM implementation.

c.

OFFS1TE DOSE CALCULATIONMANUALimplementation.

f.

'uality Assurance Program for effluen and cavironmeatal monitoring using the guidance in Regulatory Guide 1.21, Rev. 1,.Junc 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

g.

Compoaent Cyclic or Transient Limits program, which provides conuols to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that compoaents arc maintained within the limits.

6.8.2 Each pmcedure aad fication 6.8.1 above, aad changes thereto, including ges, shall bc reviewed prior to implementation as s

'ecifl~lon 6.5 above.

6.8.3 A plant pmgram for post-accideat sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze tcactor coolaat samples, containmeat atmosphere noble gas samples, and uait vcat gaseous cffluent samples for iodines aad particulates under accident conditions. Thc program willinclude thc following:

a.

b.

C.

Training of personnel, Pmcedures for sampling and analysis, Pmvisions for maintenaace of sampling aad analysis equipment.

COOK itUCLEAR PLAi~T-UiiT1 Page 6-

~

AAIEiboilfE>T=".~. 4R. ~. 20t

p,l lg f

6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 6.8.4 The following programs shall bc established, implemented, and maintained:

Radioactive Effluent Controls Pro A program shall bc provided conforming with 10 CFR 50.36a for the control of radioactive efQuents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

Thc program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shaMnclude remedial actions to be taken whenever the program limits arc exceeded.

The program shall include the following elements:

1)

Limitations on thc operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED ARI~ conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR20.106 and with thc methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose commiunent to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)

Determination ofcumulative and projected dose contributions from radioactive cffIuents for the cuncnt calendar quarter and curat calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use ofthe liquidand gaseous effluent treaunent systems to ensure that the appropriate portions of thcsc systems are used to reduce releases of radioactivity when the projected doses in a 31'eriod would excccd 2 pcrccnt ofthe guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, COOK NUCLEAR PLANT-UNIT 1 Page 6-AMENDMENT189

II

DM N S

TVE CONTROLS 6

8 PROCEDURES AND PROGRAMS (continued) 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, 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 I to 10CFR Part 50, and 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.

adio o

ca E v pnme ta Mo tor o

a A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative 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 pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond 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 measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

COOK NUCLEAR PLANT - UNIT 1 6~v 8

AMENDMENT NO.

189

~ 4

M N STRA CO OLS 6

9 REPORTING RE UIREHEHTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear,

thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the ope ating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT - UNIT 1 6-18c ANE?G)MENT NO.

W4, 454, 189

DM NISTRATIVE CONTROLS STARTUP REPORT (continued) 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

6.9.1.4 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 shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functionsz, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),

waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20X of the individual total dose need not be accounted for.

In the aggregate, at least 80X of the total whole body dose received from external sources shall be assigned to specific ma)or work functions.

b.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4,4.5.5.b) c ~

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the I-131 specific activity limit was exceeded.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

COOK NUC~~

PLANT - UNIT 1 6-A~~MEÃi NO. M, 43', 4',

189

/g

CO OLS RADIOLOGICAL RONMENT 0

TING REPOR 3

6.9.1.6 The Annual Radiological Environmental Operating Report 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 the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

AL RADIOACT E

S 0

6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

Jl A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste

systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT - UNIT 1 6-AMENDMENT NO. M, 444, 454, 474 189 il

f ~

I

~ 'I

I ~

6.0 ADMIMSTIV.TIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating stMistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.

Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month followiag the calendar month covered by thc report.

CORE OPERATING LIMITSREPORT 6.9.1.9.1 Core operating limits shall be established and documeated in the CORE OPERATING LMITS REPORT before each reload cycle or aay remaining part of a reload cycle for the following:

Moderator Temperature Cocfficieat Limits for Specification 3/4.1.1.4, b.

Rod Drop Time Limits for Specification 3/4.1.3.3, c.

Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.

Control Rod Insertion Limits for Specification 3/4.1.3.5, Axial Flux Difference for Specification 3/4.2.1, f.

Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.

Allowable Power Level for Specificatioa 3/4.2.6.

6.9.1.9.2 The analyucal methods used to determine the core operating limits shall be those previously reviewed and approved by thc NRC in:

WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westiaghouse Proprietary),

WCAP-8385, Power Distribution Control and Load Following Procedures

- Topical Report," September 1974 (Westinghouse Proprietary),

C.

WCAP-10216-P-A, Revision IA, Relaxation of Constant Axial Offset Control/F~

Surveillance Technical Specificatioa, February 1994 (Westinghouse Proprietary),

WCAP-10266-P-A Rcv. 2, The 1981 Version of Westiaghouse Evaluation Mode Using BASH Code, March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNITI Page 6-IZ AMENDKKNT69, 484, 474, 489, 206

DMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 6.9.1.9.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.9.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC document contxol desk with copies to the Regional Administrator and Resident Inspector.

SPECIA REPORTS 6.9.2 Special reports shall be submitted to the attention of the document control desk

- U.S. Nuclear Regulatory Commission (Washington, D.C. 20555),

with copies to the Region III Administrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.

co Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

High Specific Activity.in RCS Coolant, Specification 3.4.8.

e.

RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification, 3.4.9.3.

Moderator Temperature Coefficient, Specification 3.1.1.4.

Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.

h.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

i.

Violation of Safety Limit, Specification 6.7.1.

COOK NUCLEAR PLANT - UNIT 1 6p j 2 AMENDS~ NO. M, 454, 189

4 ~

CONTROLS 6

1O EM g ~7

.1 ~The following records shall be retained for at least five years:r a.

Records and logs of unit operation covering time interval at each power 1'evel.

b.

Records and logs of principal maintenance~ tivities, inspections, repair and replacement of incipal items of equipment related'to nuclear safety c.

All REPORTABLE EVENTS submitt to the Commission.

l d.

e.

Records of surveillance ctiv ties, inspections and calibrations required by these Te ical SpecMications.

Records of chan s made to the procedures required by Specificatio 6.8.1.

f.

Recor of sealed source and fission detec n leak tests and res s.

g.

Records of annual physical inventory of all sealed s urce material on record.

COOK NUCLEAR PLANT = UNIT"1

',~9-AK2$HENT NO. A, 430, 446, 444 189

E ~

6.0:

ADMINISTRATIVECONTROLS

~6.10 RECORD RETENTION Continued 6.10;2.

C.

c.

The following records shall be retaiacd for the duration of the Facility Operating Uccnsc:

a Records and drawing changes refiecting unit design modifiicatious made to systems aad equipment described in the Final Safety Analysis Report.

J b.

Qecords of new and irradiated fuel inventory, fuel transfers and.assembly burnup hi ries.

Recoah fradiation exposure for all individuals entering radiation control areas.

d.

Rcconh of gaseous aad liquid radioactive materia.released to thc environment.

Records of transient or operatioaal cycles for'those facility components identifie ia the Updated Final Safety Analysis Report. x r

J'.

Records of reactor tests and experiments.

Records of training and qualificatioa'for current members of thc Plant StaK jr h.

Records of in-service inspecrions performed, ursuaat to these Tcchnical Specifications.

i.

Records of Quality Assurance activities rcquirctf'b the QA Maaual.

j.

Recoids of reviews performed for changes made to procedures or equipment or review

.of tests and expcrimeats pursuant to 10 CFR 5059.

/'ecords of meetings of the PNSRC aad the NSDRC.

L Records of radioactive shipmeats.

Records ofthc service lives ofhydraulic snubbers including the date at which scrvicc life commences and associated installation and maintenance records.

Records of rcvicws performed for changes made to the OFFSITE DGSE CALCULATIONMANUALaad the PROCESS

~gggRAM.

6.11 RADIATIONPROTECTION PROGRAM Procedures for personnel radiatioa protection shall be prepared consisteat with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations iavolving personnel radiation exposure.

COOK NUCLEAR PLANT-UNITI Paoe 6-A~(ENDLLENT89, 444, ~, 480, 20!

6.0 ADMINISTRATIVECONTROLS 6.12 HIGH RADIATIONAREA 6.12.1 In lieu of the contml device or alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrcm/hr or less sha11 be barricaded and conspicuously posted as a high radiatioa area aad entrance thereto shall bc contmlled by requiring issuance of a Radiation Work Pcnait.

Aay individual or gmup of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

~ -

a.

A radiation monitoring device which continuously indicates thc radiation dose rate ia the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is receivaL Entry into such areas with this monitoring device may be made after thc dose rate level in the area has been established and personnel have been made aware of it.

C.

An individual qualified in radiatioa pmtection procedures who is equipped with a radiation dose rate monitoring device. This individual shall bc responsible forpmviding positive control over the activities within the area and shall perform periodi radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which thc inteasity of radiation is greater than 1000 mrem/hr. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative contml of the Shif't Supervisor on duty and/or the Plaat Health Physicist (Plant Radiation Pmtecuoa Supervisor).

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels ia thc immediate work areas.

In thc event that it is not possible or practicable to pmvide locked doors due to area size or configuratio, the area shall be mpcd off, conspicuously posted and a Gashing light shall bc activated as a warning device.

Health Physics (Radiation Protection) persoaael shall be exempt from the RWP issuance requirement during the perfonnance of their assigned radiation protection duties, pmvided they comply with approved radiation protection pmcedurcs for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT1 Page 6-AMENDMENT94, 4$0, 484, 189

CO OS 6.

3

. OCESS CO OL PROGRAM PCP 6.13.1 Changes to ehe PCP:

a.

Shall be documented and records of reviews performed shall be retained This documeneaeion shall contain'.

1.

Sufficient information to support ehe change together with the appropriate analyses or evaluations justifying the change(s) aad 2.

A determination chac che change'will maintain the overall conformance of ehe solidified waste product to existing requirements of Federal,

State, or ocher applicable regulations.

b.

Shall become effective after

~he approval of ehe Plane Manager.

6 14 0 SETE DOSE CALCULATION MANUAL ODCM 6.14.1 Changes to the ODCM:

a ~

Shall be documented and records of reviews performed shall be retained This documeneaeion shall contain:

l.

Sufficient information to support the chaage together with the appropriate analyses or evaluacions justifying the chaage(s) and 2.

A determination thae the change will maintain the level of radioactive effluent contxol required by 10 CFR 20.M6; "40 CFR Pare

190, 10 CFR 50.36a, aad Appendix I to 10 CPR Pare 50 and not adversely impact the accuracy or reliability of

effluenc, dose, or seepoint calculations.

b.

Shall become effective after

~ad-the approval of the Plant Manager.

c Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluene Release Report for the period of the report in which any change to the ODW was made.

Each change shall be ideneified by markings in the margin of che affected

pages, clearly indicating the area of the page that was changed, and shall indicate the dace (e.g., month/year) the change was implemented.

COOK NUCLEAR PLANT - UNIT 1

~/ C AMENDMENT NO. $7-, 4Q+,

189

~ ~

INDEX ADMINISTRATIVECONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsitc and Offsite Organization... ~...............

Facility Staff.

~

~

~

~

~

0 1

~

~

~

~

~

~

~

6-1

\\

~

~

~

~

~

~

6-1 6.3 FACILITYSTAFF UALIFICATIONS 6.4 TRAINING o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

65 RE~~

~

DIT DCW

&4 6..

PLANT NUCLEAR SAFETY REVIEW COMMTTTEE T

Functio Composition..

Alternates

~

~

~

~

~

~

~

~

~

Mccting Frequency Quorum Responsibilities.......

Authortty...........

Records

. ~...

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

&4 64

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ 0 0

~

~

~

~

~

~

~

~

~

~

~

~

~

6-5 6-5

~

~

~

~

~

~

~

~

~

~

~

~

~

~

64

~

~

~

6.5.2 NUCLEAR SAFEI'Y AND IGN REVIEW COMMI'ICE Funcnon Composition Alta6atc Members.....

~

~

~

~

~ bo

~

~

~

6-6

~

~

~

~

~

~

~

~.. "<<.6-7 COOK NUCLEAR PLANT-UNIT2 AMENDMENTV4, 4P, 438, 175

M IS IVE CONTROLS 6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE (continued)

OQSultentS

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

ohio

~ ~ ~

~

~

~

6-8 Meeting Erequency...............

Quorusl

~ ~

~ ~

~

~ ~ ~

~ ~

~

~

~

~

~ ~ ~ ~

~ ~ ~ ~ ~ ~

6-8 6-8 Reve.ev............

~

~

~ ~

~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ oooo

~

6-8 Qdi'ts

~ ~ ~

~

~

~ ~ ~

~

~

~

~

~

~ ~ ~ ~

~

~ ~

A 6-9 o

Author

~

~

~ ~ ~

~

~

~

~

~

~

~

~

~

~ ~

~ ~

~

~

~

~

~

6-10 eCOrdS

~

~

~

~

~ ~

~

~ ~ ~ ~ ~ ~

~

~

~

~

~ ~ ~ ~

~ ~ ~ ~

~ ~ ~ ~ ~ o ~

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ o ~

~ o ~

~

.5.3 TECHNICAL REVIEW AND CONTROL...........

6-10

~6-10 6 7 SA L MI OLA ON 6

8 PROCEDURES R0

~

~

~

~ ~ ~ ~

~ ~ ~ ~

~ ~

~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ o o ~ ~

6 6

REPOR ABLE EVENT CTION......

~ ~.

~

~ - ~ ~ ~ ~

~ ~

~ ~ ~ -- ~

~ ~ --- ~ ~ ~ 6P" O 6+K 6-)E')'.

9 RET'ORTING RE UIRBfPiTS, 6.9.1 ROUTTNE REPORTS....................................

6+3c 6.9.2 SPECIAL REPORTS 9~c~~

6 0

I CORD" ET

~ ~

~

~ ~ ~ ~

~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~

~ o

/3 6'19

)

~

~

~ V C AVW'~aooooPva ~,Pod~

9 o ~ ~ o o ~ ~

1 RAD 0

POE ON RO

~

~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ o ~ ~ o \\ o o ~ ~ o \\ ~ ~ ~ ~ ~

~ ~

~

~

~

~

~

~

~ ~ ~ ~

~

~

~

~

~

~ ~ ~ o ~ ~ ~

~ ~ ~ ~ ~ ~

~

~ o

~

~

6.

3 PROC SS CONTRO PROGRAM CP 6

4 OFFSITE DOSE CALCULA ION AL ODCM COOK NUCLEAR PLANT - UNIT 2 XVII AMENDMENT NO. ~, ~,

175

3 TO

HRC:0659X INISTRAT VE COS~OLS 6

3 FACTL TY STAM UALIFICAT ONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI H18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager,

@ho shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering di.scip1ine vith specific training in plant design,

'and response and analysis of the plant for transients and accidents

and, (3) the Operations Superintendent, who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.

6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6 5

ZZP AÃVRfiD T 6

'LANT NUCLFAR SAFETY REVIEW CONG E

SRC 6.5.1.1 The

~C shall function to advise the Site Vice President/Plant Manager, or designee, on all matters related to nuclear safety.

COMPOSI ION 6.5.1.2 The PHSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Site Vice President/Plant Manager, Assistant Pl&tManagers or Department Superintendents;"

The membership shall represent the functional areas of the plant, including, but not limited to Operations, Technical.

Sup ort, Licensing, Maintenance and Radiation Protection.

The PNSRC membership shall consist of at least one individual froa each of the areas designated.

All members, including the Chairman and his alternates, the members and their alternates, shaU.

be designate'y the Site Vice President/Plant Manager.

PNSRC members and'alternates shall meet or exceed the minimum quelifi.cations of ANSI N18.1-1971 Section 4.4 for comparable positions..

The nuclear po~er plant operations.individual sha11 meet the qualifications of Section 4.2.&of ANSI H18.1-197I, except for the requirement to hold a current Senior Operator License, The operations individual must hold or have held a Senior Operator License+at Cook Huclear Plant or a similar reactor.

The maintenance individual shall meet, the qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT - UNIT 2 6-4 AMENDMENT NO. V, 178

I ~

AL'iiNhTZS 6.5.1.3 Ho more thea tvo altezaates shall paz=icipata as voting members ia/

PNSRC ac ivities ac any one time.

& TZNC PRE GENT

/

6.5.I..4 The PNSRC shall meet ac least once pet calendar month and as convened by cheiPHSRC Chairman or his designated alternates QUORUM

//

6.5.1.5 h cpzorum of 'the PNSRC shall consist of the Chaizman or his designated alteraate aad at least th ee members including alternates RZS PONST3 EIZTX=S 6.5.1.6 The PNSRC shall be z sponsible for:

a.

Raviev of all Plant verger Xastructions (PQs) aad revisions thereto.

,/

b-Eeofao of safaris aoaloasfonn fon (l) plans sfsa psoosfonsa a-revisions thereco vhich affec the auc].ea>> saf ecy of the plaac:

(2) changes or modificacionsf t nuclear safety-related sees, systems ox componeacs; and/(3) t cs oz experiments vhich affect plant auclea safecy to ver~ y that such actions did not constitute an unrevieved safety question as deemed fn 10 Cci. 50.59.

l c.

Reviev of (1) proaosed procedures and revisions to procedu=as, (2)

I' c"sages to ecpxipmenc,'yst~,

or facQ.ities, and (3) proposed tests ot'rperfmcnts vhich may involve an vieved sazety

~estioa as defined in 10 ~f 50.59.

/

d.

Reviev of. proposed changes to hppendix "4" Techni Spec&icacians or the Operating LLcease aad zeadering decezminacioas ia vriting vith regard to vhecher or ace the proposed'change coascituces a Significant Ha=azds Consideracioas.

~ -

~~escigaciou of all violatioas of the Tachaical Spec~~iecioas including che prepazac'on and fozvarding of reports cover~kg evaluation aad recommeadacioas to prevent recur=ence to the

.,'hairman of the HSDRC.

/

Reviev of all RE~ORTh3LE ITS.

I r.'.. Re~ev of flc~f jV operaci~ t detect pocencgW ~lear safe~

hazards.

s~

A

~ s u

r j

COOX NUC~2Mi-"-Pili. 2 6

5 QSBK~'-HQ...D E Jg B E

h.

Performance of special

reviews, investigations of"analyses and reports thereon as requested by the Chairman of the NSDRC.

Deleted.

j.

Deleted.

k.

Renew of any accidental, unplanned, or uncontrolled~radioactive releihe including the preparation of reports covering evaluations, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Senior Vice President Rxclear Generation and to the NSDRC,~

1.

Revie~ of ch ges to the PROCESS CONTRO

PROGRAM, OFPSITE DOSE CALCULATION MANUAL, and radwaste treatment'ystem.

AUTHORITY 6.5.1.7 The PNSRC shall:

a.

ECORDS 6.5.1.8 shal1 be Recommend to the Site Vi e President/Plant

Manager, or desginee, written approval or disapprbyal/of items considered under 6.5.1.6 (a) through (d) above.

Render determinations in writin with regard to whether or not each item considered under 8.5.1. 6 (a) through (c) and (e) above constitutes an unrevieved safety question.

Provide written notif5.cati.on within/24 hours to the Senior Vice President

-Nuclear Generation and the NSDRC of disagreement between the PNSRC and the/Site Vice Pres'ident/Plant Manager;

hovever, the Site Vice President/Plant Manager, 'i

designee, shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

The PNSRC shall maintain vritten minutes of each meeting and copies provided to the Chairman of the NSDRC.

ES GN EV E

NSDRC CTION 6 5.2 The NSDRC shall function to provide des ated activities in the areas of:

independent reviev and aud'it of a.

nuclear power plant operations b.

nuclear engineering

~ ~

c.

chemistry end radiochemistry d.

metallurgy instrumentation and control 3.

4.

5.

'6.

7.

8.

9.

10.

11.

12.

13.

radiological safety g.

mechanical and electrical engineering quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the following regular members:

1.

Senior Vi'ce President

- Nuclear Generation (NSDRC Chairman) 2 ~

Manager - Nuclear Safety,

Ucensing,

& Fuel Division -

(NSDRC Secretary)

Site Vice President/Plant Manager - Donald C. Cook Nuclear Plant Vice President

-'iIndiana Michigan Pover Company Executive Vice President

- Engineering

& Construction

'Vice President

- Transmission and Distribution Services Senior Vice President-;

Fossil and Hydro Generation Manager - Nuclear Engineering Department Vice President

- Civil Engineering Manager - Nuclear Plane Engineering Support Division Manager

-, Nuclear Support Services Department Manager.'- Quality Assurance Department Manager - Production Support and Administrative Services Section Additional members and Vice Chairman may be appointed by the President and Chief Operating Officer.

LTERN TE ~ERS 6.5.2.3,Designated alternate members shall be appointed by'he President and Chief Operating Officer or such other person as he shall designate.

In addition, temporary alternate members may be appointed by the NSDRC Chairman to serve on an incerim basis, as requided.

Temporary alternate members are empovered co act on che behalf of the regular or designated alternate members for vhom they substitute.

AM&DNZk+a-N 178

6.5.2.4 Consultants shall be utili"ed as determined by the NSDRC Chairmango provide expert advice to the NSDRC.

ETTNG FRE UENCY 6.'5.2.5 The NSDRC shall meet at lease once per six months.

QUOTER 6.5.2.6 A quorum, the inimum number of regular members ayd alternates recuired to hold a NSDRC meeting 'shall be eight members, of whom no more than two shall be designated or temporary alternates.

The Chairman or acging Cha'~an shall be present for all NSDRC meetings.

If the number of members present is greater than a quorum, then the majority par icipating and voting at the meeting shall not have line responsibil'ty fo', operat'ons of the.-facility.

For the purpose of a quorum, only the Plant Manager~is considered to have line responsibility.

R REVIEW 6.5.2.7.

The NSDRC is responsible for assuring that independent reviews of the following are performed:

a.

The safety evaluations foryl) chMges to procedures, equipment or systems and 2) tests or experm4ents&ompleted under the provision of 10 CFR 50.59 to veri.fy that'uch action did not const'tute an unreviewed safety questi.on.

r b.

Proposed changes to 'procedures, equipment.or systems which involve an unreviewed safety,:question as defined in 1 CFR 50.59.

c.

Proposed tests, or experiments which involve unreviewed safety quest'on as defined in 10 CFR 50.59-I d.

Proposed changes in Technical Speci.fications or s operating license.

e.

Violations of codes, regulations,

orders, Technical Specifications, license requi"ements, or of internal procedures or 'uctions having nuclear safety significance.

Regular NSDRC members are expected to attend the meeting whenever possible and alternates may attend as voting members only on an ir egular basisX If both a regular member and his alternate attend a meeting, only the regular member may participate as a voting member, and the alternate is considered a guest.

r Independent reviews may be performed by groups which report dXrectly<to the NSDRC and which must have NSDRC membership participation.

I

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

/

All REPORTABLE EVENTS.

h.

All recognized indications of an unanticipated deficiency in some asRece of design or operation of safety-related structures,

systems, or components.

i.

Reports and meeting minutes of ehe PNSRC.

r

~T~S 6.5.2.8 Audits of facility activities shall be, performed under the cognizance of the NSDRC.

These audits shall encompass:

~~

a.

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions ae, least once per 12 months.

b.

ci d.

e.

The performance, trainin

, and ualifications of the entire facility staff at least once pe 12 mon The results of actions taken to correct deficiencies occurr'ingin facility equipment~ structures, systems or method of operation thae affect nuclear suety at least once per months.

The performaace of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at lease, once per 24 months.

Deleted.~

Deleted.

The fire protection programmatic controls including the implementing procedu es at least once pe 24 months by qualified licensee QA

'personnel.

The fire protection equipment and program implemeneaeion at lease once pe 12 months using either a qualified offsiee licensee fire protection engineer or an outside independent fire protection consultant.

An oueside independent fire proeection consultant shaU.

be used at least every third year.

The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.

~~CtEAR FCAKZ - ONIT 2 6.-'9-

---

"AMENDMENT--NO.-M-,'434-

<<178

~ g

~

6 k.

R:-CORDS EV AND CO 0

s '"

The 0:"=SITE DOSE CALCULATION MANUAL and '~3.ementing procedu=es,at

'east once per 24 months.

Th PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioact've ~astes at least once per 24'cinths.

1.

The performance of act'vities required by the /cali~ Assu-ance

~ogram to meet the cx'iteria of Regulatory Guide~X.21, Rev.

1, e 1974 and Regulatory Guide 4.1, Rev. 1, AprQ 1975 at least once pe 12 months.

m.

Any o er area of facility operation considered appropriate by the NSDRC.

/

s s

~AOTHORI

~

6.5.2.9 The NSDRC shall eport to and advise the Vice Pres dent - Nuclea Operations, A~SC, on those &eas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

6.5.2.10 Records of NSDRC activities shall be prepax'ed, approved and 2

distx'ibuted as indicated belo~: l

.I a.

Minutes of each NSDRC meeting shall be'prepared, approved and sued v5.thin 14 days folloving each meeting.

~

b.

Reports of revievs encompassed by Section 6.5.2.7 above, shall be

prepared, approved and issued vithin f4 days folleving completion of the eviev.

c.

Audit,reports encompassed by Section 6.5.2.8 above, shall be forwarded'co che Vine Presidenc

- Nuclear Operacions,

ARoSC, and to;the management positions responsible for thee, areas

audited,

&thin 30 days after completion of the audit.

6 3

CW 6.3.3.1/Aecieicies uhich efface nuclear safecR shall 'be eonduece~d.ss foliose:

//

6

, a.

Procedures required by Specification 6.8 and other procecb-es vhich affect plant nuclear safety, and changes thereto, shall be

prepared, revieved and approved.

Each such px'ocedure or procedu=e change shall be revieved by a qualified individual/g"oup other

~ the individual/group vhich prepax'ed the procedure or procedu=e

change, but vho may be from the same organizat'on~.. rhe dividual/group vhich prepared the procedure or procedu=e change.

Procedures other than Plant Manager Procedux'es

shall be approved by the appropriate department head as previously designated in writing by the Site Vice President/Plant Manager.; or designee.

The Site Vice President/Plant Manager, or designee.;shall approve Plant Manager Procedures.

Temporary changes to procedures which do not change the intent of the approved procedures shall be roved for implementation by two members of the plant staff, at le t one of whom holds a Senior Operator license, and documented.

The emporary changes shall be approved -by the original approval authority within 14 days of implementation. / For changes to procedures which may involve a

change in inst of the approved procedure~

the person authorized above to approve the procedure shall approve the change prior to implementation.

b.

Proposed changes or modifications to plant'nuclear safety-related I

structures, systems and components shall be reviewed as designated. by the Site Vice President/Plant

Manager, or designee.

Each such nodiffcacion ehallge cevfeoed (y'efecence T/S 6.5.3.1.e) by a

qualified (reference pS 6.5.3.1.df individual/group other than the individual/group which designed ge modification, but who may be from the same organization ea the ~individual/group whi.ch designed the modifications.

Proposed ~modifications to plant nuclear safety-related structures, systems and components shall be approved prior to X

~

implementation by the Site Vic President/Plant Manager, or designee.

c.

Proposed tests and exper ents wh h affect plant nuclear safety and are not addressed in the Pi.nal S

sty Analysis Report or Technical Specifications shall be prepared,

rebiewed, and approved.

Each such test or experiment sdall be reviewed by qualified individuals/groups other than the individual/group which prepared the proposed test or experiment to assure cross-disciplinary review as appropriate for the proposed test oi experiment.

Proposed test, and experiments shall be approved before implementation by the Site Vice President/Plant

Hanagez, or esignee.

d.

Zndividua)s who conducted the reviews pezforme in accordance"wi'th Specification 6.5.3.la, 6.5.3.lb, and 6.5.3.lc, +all be members of the plapt management staff pzeviously designated%by the Site Vice President/Plant Manager and shall mee t or.exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.

Each such review shall include a determinahion of whether or,.not additional, cross-disciplinary review is necessa~.

Ef deemed necessary, such review shall be performed by qualified personnel of e appropriate discipline.

l e.'ach review shall include a determination of whether or ot an unzevtewed safety question fs involved.

Pursuant to 10 CPR '50.59.

NRC approval of items involving unreviewed safety questions shall be obtained prior to the approval of the Site Vice President/Plane

/

Manager, or designee, for implementation.

Deleted.

~<<~

(continued) g.

Deleted.

6.5.3s2 Records af th'bove activities sha

-be provided to the Site Vice Preident lan~Manager, or designee, PNSRC and/or the HSDR necessary for qa red reviews.

6 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

/+LE~

b.

The Commission shall be notified and a report submitted pursuant, to the requirements of 10 CFR 50.73+

of this revise H.

e suheitted toe'h~SDRCso~-the Seuior Vite P

- Nuclear Generation.

s 6 7 SAFETY LIMITVIOLATION 6.7.1 The following actions shall be taken in the event a safety limit i. -.

violated:

0 >+Ifm fQ $

sdi4r V'ce P~6~ch+-

t4 <le ip~ G.em rett~

b.

C The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />..

Pirhiu 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s~~

A Safety LimitViolation Report shall be prepared.

This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility componencs, systems or structures; and (9).~orrecMve action taken to prevent recurrence.

6e Safetyp Limit Violation Report shall be submitted to the Commissio~

Rt: and e Senior Vice President-s f4 d.

Operation of the unit shall not be resumed until authorS.zed by the Commission.

COOK hiJCL".G PLANT - UNIT 2 A~~%)M~'iT NO.

178

1 ~

6.0 ADlVQKISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall bc established, implemented and maintained coveriag the activities referenced below:

a.

The applicable procedures recommended in Appendix "A of Regulatory Guide 1.33, Rev. 2, February 1978.

b.

Deleted.

c.

Deleted.

d.

PROCESS CONTROL PROGRAM implementation.

e.

OFFSITE DOSE CAI.CULATIONMANUALimplementation.

f.

Quality Assurance Program for effluent aad environmeatal monitoring using thc guidance in

'egulatory Guide 1.21, Rcv. I, Junc 1974, and Regulatory Guide 4.1, Rev. I, April 1975.

catioa 6.8.1 above, and changes thereto," including ges, shaH be reviewed prior to imp emen

'Ficati ve.

g.

Component Cyclic or Transieat Limits program, which provides controls to track the UFSAR,

, Section 4.1, cyclic aad transient occurrences to ensure that compoaents are maintained within the limits.

6.8.2 Each p 6.8.3 Aplant program for post-accident sampling shall bc established, implemented, and maintained which will ensure thc capability to obtain aad analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples foriodines and particuhtcs under accident conditions. The program will include the following:

b.

C.

Training of personnel, Procedures for sampling and aaalysis, Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PLANT-UNIT2 Page 6@5l A116ENDggENT 66, ggg, ~, ~, 166

6.0 AOMIMSTRATlVECONTROLS PROCEDURES AND PROGRAMS Continued

~

~

6.8A The following programs shall be established, implemented, and maintained:

Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50.36a for thc control of radioactive efflucnts and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shaH be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever thc program limits are exceeded.

The program shall include thc following elements:

I)

Limitations on the operability of radioactive liquid and gaseous monitoring insuumentation including surveillance tests and sctpoint determination in accordance with the methodology in the ODCM, 2)

Limitations on thc concentrations of radioactive material released in liquid cffluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20. 106 and with thc methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive. materials in liquid cffluents released from each unit to UNRESHUCTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)

Determination ofcumulative and projected dose contributions from radioactive effiuents for thc current calendar quarter and current calendar year in accordance with thc methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on thc operability and use ofthe liquid and gaseous effluen treaunent systems to ensure that the appropriate portions of these systems are used to reduce rcleascs of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitmcnt conforming to Appendix I to 10 CFR Patt 50, COOK iIUCLEARPLANT-UNIT2 Page 6-AMENDMENT175

W

ADMINISTRA IVE CONTROLS PROCEDURES AND PROGRAMS (continued) 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, 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 I to 10CFR Part 50, and 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.

Radiolo ica Environmenta Monito n

o am A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative 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 pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling,

analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure tha" changes in the use of areas at and beyond 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 measurements of radioactive materials in environmental sample matrices are performed as par" of the quality assurance program for environmental monitoring.

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO.

175

T CO 0

PORTING RE EMENTS RO N

RE ORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be.submitted to the Regional Administrator unless otherwise noted.

STARTUP R

PO 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in'this report.

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. 44, ~,

175

EI j

DM N S

T CONTROLS 6.9.1.3 Startup reports shall b'e submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

6.9.1.4 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 shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a ~

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr(and their associated man rem exposure according to work and job)functionsz, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),

waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20X of the individual total dose need not be accounted for.

In the

,aggregate, at least 80X of the total whole body dose received from external sources shall be assigned to specific major work functions

~

b.

The complete results of steam generator tube in-service inspections performed. during the report period (reference Specification 4.4.5.5.b).

C.

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the I-131 specific activity limit was exceeded.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. W, 449, 175

~ I

M S

TVE CO 0

L RAD 0 GIC L ENV RO ENTA OPERA G REPO 6.9.1.6 The Annual Radiological Environmental Operating Report 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 the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUAL RADIOACTIVE E RELEASE REPORT~

6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

The report shall include a summary of the quantities of radioactiv'e liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CPR Part 50.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste

systems, the submittal shall specify the releases of radioactive material for each unit ~

COOK NUCLEAR PLANT - UNIT 2 6-AMENDMENT NO. 48, ~, 438, iy 175

i ~

4 l

l

i~

6.0 ADMIMSTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operatiag statisucs aad shutdown experience, Including documentauon of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commissioa (Attn: Document Control Desk), Washingtoa, D.C. 20555, with a copy to the Regional Office no later thaa the 15th of each month followiag thc calendar month covered by the report.

CORE OPERATING LIMITSREPORT 6.9.1.9.1 Core operating limits shall bc established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining pan of a reload cycle for the following:

a.

Moderator Temperature Cocfficieat Limits for Specification 3/4.1.1A, b.

Rod Drop Time Limits for Specification 3/4.1.3.4, c.

Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, d.

Control Rod Insertion Limits for Specification 3/4.1.3.6, e.

Axial Flux Difference for Specification 3/4.2.1, f.

Heat Flux Hot Channel Factor for Specificatioa 3/4.2.2, g.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limits shaH be those previously reviewed aad approved by the NRC in:

a.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"

July 1985 (Westinghouse Proprietary),

b.

WCAP-8385, Power Distribution Control and Load Following Procedures - Topical Report, September 1974 (Westinghouse Proprietary),

k c.

WCAP-10216-P-A, Revision IA, Relaxation of Constant Axial Offset Control/F~ Surveillance Technical Specification, February 1994 (Westiaghouse Proprietary),

d.

WCAP-10266-P-A Rev. 2, Thc 1981 Version of Wcstinghousc Evaluation Mode Using BASH

Code, March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UiiIT2 Page 6-H

/'MENDMENTF4, QS, ~, ~, 190

ADMINISTRATIVE CONTROLS CORE OPERATI G LIMITS RE OR (Continued) 6.9.1.9.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.9.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC document control desk with copies to the Regional Administrator and Resident Inspector.

C A 0

S 6.9.2 Special reports shall be submitted to the attention of the document control desk

- U.S. Nuclear Regulatory Commission (Washington, D.C. 20555),

with copies to the Region IIIAdministrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a ~

inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.

c ~

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

High Specific Activity.in RCS Coolant,.Specification 3.4.8.

e.

RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification 3.4.9.3.

g-Moderator Temperature Coefficient, Specification 3.1.1.4.

Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.

h.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

i.

Violation of Safety Limit, Specification 6.7.1.

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. W, 43$,

175

~y l

if

0 RCO 6.10.1 ~Zhe following records shall be retained for at least five.y~:

a.

Recor and logs of unit operation covering time interval at each

~

~

~

~

power lev b.

Records and logs principal maintenance a

vities, inspections, repair and replacement of pr ncipal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted ed the Commission.

d.

Records of surveillance acWvities, inspections and calibrations required by these Technical Specificatxons.

e.

Records of chang made to the proceduxes required by

~

Specification

.8.1.

l f.

Records~

sealed source and fission detection leak eests and results.

'g. ~ ecords of annual physical inventory of all sealed source

'material on record.

4 ~

6.0

=

ADMPKFIRATIVECONTROLS 6.10.2 c following records shall be retained for the duration of the Facility Operating License:

b.

C.

d.

c.

g h.

J ~

d bed in the Final Safety Analysis Report.

ecords and drawing changes refiecting unit design modifications made to systems and equfpment Records o ew and irradiated fuel inventory, fuel transfers and assembly butnup histories.

Records of radi

'on exposure for all individuals entering radiation coriuol areas.

Records of gaseous and liquid radioactive material released to t6e environment.

Records of transient or ope onai cycles for those facility components identified in the Updated Final Safety Analysis Report.

I

. Records of reactor tests and experimcn Records of training and qualification for t members of the Plant Staff.

Records of in-service inspections performed p to these Technical Specifications.

~

.r'ecords of Quality Assurance activities required by the Manual.

Records of reviews performed for changes made to pmccd r equipment or review of tests and experiments pursuant to 10 CFR 50.59.

Records of meetings of the PNSRC and the NSDRC.

l.

Records of radioactive shipments.

m. +'ecords of the service lives of hydraulic snubbers including the date at which service life commences and associated installation and maintenance records.

,i'a.

Records of reviews performed for changes to the OFFSITE DOSE CALCULATIONMANU and the PROCESS CONTROL PROGRAM.

6.11 RADIATIONPROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

COOK NUCLEAR PLANT-UNIT2 Page 6-+~

J +

AMENDiiKliTW, 438, 486, ~, 1S6

~ ~

'I l

6.0 ADMNISTRATIVECOYIROLS 6.12 HIGH RADIATIONAREA 6.12.1 In lieu of the control device" or,"alarm signal required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiatioa is 1000 mrcm/Itr or less shall be barricaded and conspicuously posted as a high radiatioa area and entrance thereto shaH be controHcd by requiring issuance ofa Radiation Work Permit

. Any individual or group ofindividuals permitted to enter such areas shall be provided with or accompanied by onc or more of the foHowiag:

a.

A radiatioa monitoring device which continuously indicates thc radiatioa dose rate in thc area.

b.

A radiation monitoring device which continuously integrates thc radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after thc dose rate level in the area has been established and personnel have been made aware of it.

C.

Aa individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the acuvitics wiihia the area aad shaH perform periodic radiatioa surveillance at thc frequency specified by thc facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6. 12.1 shaH also apply to each high radiation area in which thc intensity ofradiation is greater than 1000 mrem/hr.

When possible, locked doors shaG be provided to prcveat unauthorized entry into such areas, and the keys shaH be maintained under the administrative control of thc Shift Supervisor oa duty and/or the Plant Health Physicist (Plant Radiatioa Protccuon Supervisor).

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels ia the immediate work areas.

In the event that it is aot possible or practicahle,to provide locked doors duc to area size or configuration, the area shaH bc roped off, conspicuously posted and a Gashing light shall be activated as a warning device.

Health Phvsics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance. of their assigned radiation protectioa duties, provided they comply with approved radiatioa protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT2 Page 6+6 I

AMENDMENT80, 434, 4%, 175

I S

E CO OLS 6

3 OCSSCO 0

0 6.13.1 Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations Justifying the change(s) and 2.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal,

State, or other applicable regulations.

b.

Shall become effective after d-the approval of the Plant Manager.

6 4 OFFS TE DOSE CALCULATION MANU L ODCM 6.14.1 Changes to the ODCM:

Shall be documented and records of reviews performed shall be retained This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations )ustifying the change(s) and 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 I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Shall become effective after~

~ the approval of the Plant Manager.

c ~

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be ident'ified by markings in the margin of the affected

pages, cLearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

COOK NUCLEAR PLANT - UNIT 2 6' +

AMENDNENT NO. W, 48$,

175

lg

ATTACHMENT 3 TO AEP'NRC'80027 REVISED TECHNICAL SPECIFICATION PAGES

~ I l

~ ~

INDEX ADMINISTRATIVECONTROLS SECTION 6.1 RESPONSIBILITY 6.2 ORGANIZATION

'A'GE Onsite and Offsite Organization Facility Staff 6.3 FACILITYSTAFF UALIFICATIONS 6.4 TRAINING..

6-1 6-1

... 64 6.5 DELETED 6.6 REPORTABLE EVENT ACTION...

6.7 SAFETY LIMITVIOLATION...

6-5 6-5 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING RE UIREMENTS 6-6 6.9.1 ROUTINE REPORTS...

6.9.2 SPECIAL REPORTS...

6-9 6-13 6.10 DELETED 6.11 RADIATIONPROTECTION PROGRAM 6-14 6.12 HIGH RADIATIONAREA 6-14 6.13 PROCESS CONTROL PROGRAM PCP

~

~

~

~

~

~

~

~

~ 6 15 6.14 OFFSITE DOSE CALCULATIONMANUAL ODCM

.. 6-15 COOK NUCLEAR PLANT-UNITI XVI AMENDMENT69, 4%, 454,

4SQ,

~ y J

6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall'have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant

design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facilitystaff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 DELETED COOK NUCLEAR PLANT-UNIT1 Page 64 AMENDMENT49, 63, 488, 4$4, 486, 4$Q

~ g I

6.0 ADMINISTRATIVECONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73.

b.

Deleted.

6.7 SAFETY LIMITVIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the Senior Vice President - Nuclear Generation.

A Safety Limit Violation Report shall be prepared.

This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.

Within 14 days of the violation, the Safety Limit Violation Report shall be submitted to the Commission and to the Senior Vice President - Nuclear Generation.

Operation of the unit shall not be resumed until authorized by the Commission.

COOK NUCLEAR PLANT-UNIT1 Page 6-5 AMENDMENTSV, 454, 489, 4$Q,

I) r

6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.

e.

Deleted.

Deleted.

PROCESS CONTROL PROGRAM implementation.

OFFSITE DOSE CALCULATIONMANUALimplementation.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev.

1, April 1975.

Component Cyclic or Transient Limits program, which provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained within the limits.

6.8.2 Deleted.

6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions. The program will include the following:

Training of personnel, Procedures for sampling and analysis, Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PLANT-UNIT1 Page 6-6 AMENDMENTVS, 484, 489, 403,

Ã4,

~ ~

0 0,

6 0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 6.8.4 The following programs shall be established, implemented, and maintained:

a.

Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 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 gaseous effluents in accordance with 10 CFR 20. 106 and with the methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,

6) 'imitations on the operability and use ofthe liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 314ay period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I.to 10 CFR Part 50, COOK NUCLEAR PLANT-UNIT1 Page 6-7 AMENDMENT489,

l

6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARYconforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, 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 BOUNDARYconforming to Appendix I to 10CFR Part 50, and 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.

Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative 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 pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling,

analysis, and reporting of radiation 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 beyond the SITE BOUNDARYare identified and that modifications to the monitoring program are made ifrequired 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 measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

COOK NUCLEAR PLANT-UNIT1 Page 6-8 AMENDMENTQS,

~ ~

6.0 ADMINISTRATIVECONTROLS 6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements ofTitle 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison ofthese values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT-UNITI Page 6-9 AMENDMENT&, 454, 489)

6.0 ADMINISTRATIVECONTROLS O

6.9 STARTUP REPORT Continued 6.9.1.3 Startu re orts shal ANNUALREPORTS1 p

p 1 be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months followinginitialcriticality, whichever is earliest. Ifthe Startup Report does not cover all three events (i.e., initialcriticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

6.9.1.4 Annual reports covering the activities ofthe unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required 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 mrem/yr and their associated man rem exposure according to work and job functions2, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),

waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

Documentation ofall challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

Information regarding any instances when the I-131 specific activity limitwas exceeded.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

2 COOK NUCLEAR PLANT-UNITI Page 6-10 AMENDMENTSV, 434, 4$4,

489,

6.0 ADMINISTRATIVECONTROLS ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT3 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 ofeach year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during'the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste

systems, the subminal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT-UNIT1 Page 6-11 AMENDMENTVV, 44k, 454, 474, 489,

~ g

6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U:S.

Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITSREPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a.

Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.

Rod Drop Time Limits for Specification 3/4.1.3.3, c.

Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.

Control Rod Insertion Limits for Specification 3/4.1.3.5, e.

Axial Flux Difference for Specification 3/4.2.1, f.

Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation'Methodology," July 1985 (Westinghouse Proprietary),

WCAP-8385, "Power Distribution Control and Load Following Procedures

- Topical Report," September 1974 (Westinghouse Proprietary),

WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control/F~

Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),

WCAP-10266-P-A Rev. 2, "The 1981 Version ofWestinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT1 Page 6-12 AMENDMENT69, 454, 474, 48Q, A6,

Ig I

6.0 ADMINISTRATIVECONTROLS CORE OPERATING LIMITSREPORT Continued 6.9.1.9.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.9.4 The CORE OPERATING LIMITSREPORT, including any mid~ycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC document control desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the attention of the document control desk - U.S. Nuclear Regulatory Commission (Washington, D.C. 20555), with copies to the Region IIIAdministrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.

c.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

High Specific Activityin RCS Coolant, Specification 3.4.8.

e.

RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification 3.4.9.3.

f.

Moderator Temperature Coefficient, Specification 3.1.1.4.

g.

Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.

h.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

Violation of Safety Limit, Specification 6.7.1.

6.10 DELETED COOK NUCLEAR PLANT-UNIT1 Page 6-13 AMENDMENTSV, 4$4, 48Q,

Iy II l

I N

6.0 ADMINISTRATIVECONTROLS 6.11 RADIATIONPROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATIONAREA In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit~.

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 radiation monitoring device which continuously indicates the radiation dose rate in the area.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist tn the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas.

In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT1 Page 6-14 AMENDMENT94, 480, 4$4,

480,

< ~

6.0 ADMINISTRATIVECONTROLS 6.13 PROCESS CONTROL PROGRAM PCP 6.13.1 Changes to the PCP:

Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after the approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATIONMANUAL ODCM 6.14.1 Changes to the ODCM:

Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 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 I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Shall become effective after the approval of the Plant Manager.

C.

Shall be submitted to the Commission in the form of a complete, legible copy ofthe entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was

changed, and shall indicate the date (e.g., month/year) the change was implemented.

COOK NUCLEAR PLANT-UNIT1 Page 6-15 AMENDMENTA, 484, 489,

l~

r

,i,l

INDEX ADMINISTRATIVECONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organization Facility Staff 6.3 FACILITYSTAFF UALIFICATIONS 6-1 6-1 6.4 TRAINING 6.5 DELETED 6.6 REPORTABLE EVENT ACTION 6-5 6.7 SAFETY LIMITVIOLATION 6-5 6.8 PROCEDURES AND PROGRAMS 6-6 6.9 REPORTING RE UIREMENTS 6.9.1 ROUTINE REPORTS 6-9 6.9.2 SPECIAL REPORTS 6-13 6.10 DELETED 6.11 RADIATIONPROTECTION PROGRAM 6-14 6.12 HIGH RADIATIONAREA 6-14 6.13 PROCESS CONTROL PROGRAM PCP 6-15 6.14 OFFSITE DOSE CALCULATIONMANUAL ODCM

~.

~

~ ~...........

~

6-15 COOK NUCLEAR PLANT-UNIT2 XVI AMENDMENTV4) 407) 488) 47$ )

6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant

design, and response and analysis of the plant for transients and accidents

and, (3) the Operations Superintendent, who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facilitystaff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 DELETED COOK NUCLEAR PLANT-UNIT2 Page 64 AMENDMENT84, 4%, 438,

~, 478,

ls I

l

6.0 ADMMSTRATIVECONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73.

b.

Deleted.

6.7 SAFETY LIMITVIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the Senior Vice President - Nuclear Generation.

A Safety Limit Violation Report shall be prepared.

This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.

Within 14 days of the violation, the Safety Limit Violation Report shall be submitted to the Commission and to the Senior Vice President - Nuclear Generation.

Operation of the unit shall not be resumed until authorized by the Commission.

COOK NUCLEAR PLANT-UNIT2 Page 6-5 AMENDMENTV3, 43S, %VS,

478,

Ig e

6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.

b.

Deleted.

c.

Deleted.

d.

PROCESS CONTROL PROGRAM implementation.

e.

OFFSITE DOSE CALCULATIONMANUALimplementation.

f.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

g.

Component Cyclic or Transient Limits program, which provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained within the limits.

6.8.2 Deleted.

6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions. The program will include the following:

a.

Training of personnel, b.

Procedures for sampling and analysis, c.

Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PLANT-UNIT2 Page 64 AMENDMENTSk, 438, IVAN, kV8,

48G,

P

6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 6.8.4 The following programs shall be established, implemented, and maintained:

Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 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 gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part'50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use ofthe liquid and gaseous effluent treatment systems

~

to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 314ay period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, COOK NUCLEAR PLANT-UNIT2 Page 6-7

6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARYconforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, 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 BOUNDARYconforming to Appendix I to 10CFR Part 50, and 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.

Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative 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 pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3)1iiclude the following:

1)

Monitoring, sampling,

analysis, and reporting of radiation 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 beyond the SITE BOUNDARYare identified and that modifications to the monitoring program are made ifrequired 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 measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

COOK NUCLEAR PLANT-UNIT2 Page 6-8 AMENDMENT478,

I II l1

,l

'I, 1,'J I

4 ~

I I

6.0 ADMINISTRATIVECONTROLS 6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements ofTitle 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

STARTUP REPORT A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison ofthese values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT-UNIT2 Page 6-9 AMENDMENTR, 438, ~,

A li

6.0 ADMINISTRATIVECONTROLS STARTUP REPORT Continued 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. Ifthe Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUALREPORTS1 6.9.1.4 Annual reports covering the activities ofthe unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required 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 mrem/yr and their associated man rem exposure according to work and job functions2, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),

waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

Information regarding any instances when the I-131 specific activity limitwas exceeded.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

COOK NUCLEAR PLANT-UNIT2 Page 6-10 AMENDMENT&, 440, 47$,

C~

6.0 ADMINISTRATIVECONTROLS ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT3 6.9.1.6 The Annual Radiological Environmental Operating Report 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 the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT3 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (I) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste

systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT-UNIT2 Page 6-11 AMENDMENT58, 429, 488, 487, XV',

6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITSREPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a.

Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.

Rod Drop Time Limits for Specification 3/4.1.3.4, c.

Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, d.

Control Rod Insertion Limits for Specification 3/4.1.3.6, e.

Axial Flux Difference for Specification 3/4.2.1, f.

Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"

July 1985 (Westinghouse Proprietary),

b.

WCAP-8385, "Power Distribution Control and Load Following Procedures

- Topical Report,"

September 1974 (Westinghouse Proprietary),

c.

WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control/Fq Surveillance Technical Specification," Februaiy 1994 (Westinghouse Proprietary),

d.

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT2 Page 6-12 AMENDMENTA, 438, 4&V, kVS,

490,

I I

IJ

6.0 ADMINISTRATIVECONTROLS CORE OPERATING LIMITSREPORT Continued 6.9.1.9.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.9.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC document control desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the attention of the document control desk - U.S. Nuclear Regulatory Commission (Washington, D.C. 20555), with copies to the Region III Administrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.

c.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

High Specific Activityin RCS Coolant, Specification 3.4.8.

e.

RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specifications.4.9.3.

f.

Moderator Temperature Coefficient, Specification 3.1.1.4.

g.

Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.

h.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

i.

Violation of Safety Limit, Specification 6.7.1.

'.10 DELETED COOK NUCLEAR PLANT-UNIT2 Page 6-13 AMENDMENTV8, 438, ~,

4 i)

I

6.0 ADMINISTRATIVECONTROLS 6.11 RADIATIONPROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATIONAREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Perinit*. 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 device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.

C.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in th'e Radiation Work Permit.

6.12.2 The requirements of 6. 12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr.

When possible, locked doors shall be provided to preventunauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas.

In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT2 Page 6-14 AMENDMENT80, 436, 43S,

'.0 ADMINISTRATIVECONTROLS 6.13 PROCESS CONTROL PROGRAM PCP 6.13.1 Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after the approval of the Plant Manager.

6.14 OFFSITE DOSE CALCULATIONMANUAL ODCM 6.14.1 Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 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 I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Shall become effective after the approval of the Plant Manager.

Shall be submitted to the Commission in the form of a complete, legible copy ofthe entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was

changed, and shall indicate the date (e.g., month/year) the change was implemented.

COOK NUCLEAR PLANT-UNIT2 Page 6-15 A5KNDMENT74, 438, IVAN,