Text

Proposed Tech Specs,Revising Administrative Controls Section 6.0 to Include Removal of Organizational Figures
	ML20235J295
Person / Time
Site:	LaSalle
Issue date:	02/17/1989
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20235J287	List: ML20235J283; ML20235J295;
References
	NUDOCS 8902240235
	Download: ML20235J295 (53)
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, .; . ATTACHMENT A PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF ~ FACIL1'D[

QPERATING LICENSES,l1PL_11_AND NPF LASALLE COUNTY STATION

'URII_1 UNIT 2 Revised Pages: XIXa XIX 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6 6-6 6 6-8 6-8 6-9 6-9 6-10. 6-10 6-11 6-11 6-12 6-12 6-15 6-15 6-17 6-17 6-18 6-18 6-19 6-19 6-24 6-24 0043V:12 rw 8902240235 890217 PDR ADOCK0500){3 P

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= 9' s '

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. , INDEX I

LIST OF FIGURES (Continued)

FIGURE 1 PAGE

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6.1-1 6-11 ,

6.1-2 ardi viiCa-U AT 0; ..Q g ( 6 4 ...................

l' 6-12 6.1-3 MINIMUM SHIFT CREW COMPOSITION .................. 6-13 i

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LA SALLE - UNIT 1 XIXa Amendment No. 1 1

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_ _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ . __ -. i

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O. 6.0 ADMINISTRATIVE CONTROLS t !

u 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A. tation-Manager sham-have-overa-H-fuH-time-responsibihty-for-s '- '

f peration o . During periods when t tie , ger is /

unavailable, he shall designa it to an established 41ternatew e NSI N18.1 of March 8, e44eo reouire, y p,,s-4oe-plant-manager.

I b. The Shift Supervisor shall be responsible for directing and commanding t/,ce Penn.xt the overall operation of the facility on his shift. The primary manage- g g ,g ment responsibility of the Shift Supervisor shall be for safe operation '

of the nuclear facility on his shift under all conditions. A management [

directive signed by S:ictant Viec Prc;ident-end Ceneral " onager Miea. f 6tations emphasizing this primary management responsibility and that g clearly establishes the command duties of the Shift Supervisor shall be reissued to all station personnel on an annual basis. '

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% The-corporetya nagement-which-rela t es-to-t he-ope r a tion-of-thi s-station. ,

is suvwn in riguiu v.2 4.

C. The-normabfunct4onal-organization 4or-operation-of-the-stat 4on-shall be '

es-shown-4n449 ere 5.1-2. The shift manning for the station shall be as shown in Figure 6.1-3. The individual filling the position of Ass 4 stent

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Super ntendent-Technic:1 Servic+e shall meet the minimum acceptable level i j for " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971.

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() -6ck,ocal >The individuals Ser"4cer filling the positions Superintendent,shall of Production meet the Superintendent minimum acceptable

" Plant Manager" as described in Section 4.2.1 of ANSI N18.1-1971.

level forand j

1. At least one licensed Reactor Operator shall be in the cor'*ol room when fuel is in the reactor. In addition, while the reacty is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator who has been designated by the Shift Supervisor to assume the control room direction responsibility shall be in the Control Room.

2. A alth-phys 4cs. technician

shall be on site when fuel is in the eactor. .

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3. All CORE ALTERATIONS shall be observed and directly supervised by 1 either a licensed Senior Reactor Operator or Senior Reactor Operator

, Limited to Fuel Handling who has no other concurrent responsibilities rod h$ prehdA during this operation.

4. A site Fire Brigade of at least 5 members shall be maintained onsite at all times *. The Fire Brigade shall not include the Shift Supervisor, the Station Control Room Engineer and the 2 other members of the mini-mum shift crew necessary for safe shutdown of the unit and any personnel equired for other essential functions during a fire emergency.

The heekh phyifet technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accomodate unexpected absence provided immediate action is taken to fill the required positions. {

LA SALLE UNIT 1 6-1 Amendment No.

3 l

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.s.

t A,.

~ INSERT 1_

A. Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the. positions for activities affecting the safety of the nuclear power plant.

1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These. relationships shall be documented and updated, . as ,

appropriate, in the form of organization' charts, functional descriptions of departmental responsibilities and relationships, and-job descriptions for key personnel positions, or in equivalent forms of documentation. .These requirements shall be documented in the Quality' Assurance Manual or the Management Plan for. Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Relationships.

2. The Station Manager chall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

3. The Senior Vice President-Nuclear' Operations shall have corporate I responsibility for overall plant nuclear safety and shall take any ,

measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

4. The individuals who train the operating staff and those who carry out health physics and qualihr assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating

-pressures.

r s .. . _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ a_

4 ADMINISTRATIVE CONTROLS y.

5. The Onsite Nuclear' Safety Group (ONSG) shall function to, examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operat-ing experience information,. including plants of similar design, which may ; indicate areas for improving unit safety. The ONSG'shall be composed of at least three, dedicated, full-time engineers of ' M-multi-disciplines located on site and shall be augmented on a part-time basis by personnel from other parts of the Commonwealth Edison Company organization to. provide expertise not represented in the-group. The ONSG shall be responsible for maintaining surveillance of unit activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as_ practical. The ONSG shall make detailed recommendations-for revised procedures, equipment modifications, maintenance activi-ties, operations activities or other means of improving unit safety to the :: . .._ , i:'::- T:'C $44sb 4525SM Aleayee 4,id t%r

- 64shn6n Mregt ,

6. The Station Control Room Engineer (SCRE) serves.as the lead control room SRO during normal operations.and as the Shift Technical Advisor

! (STA) during abnormal operating and accident conditions. In the-event of abnormal operating or accident conditions, the SCRE will

~

relinquish his job as control room SRO to the Shift Foreman and will assume the role of.STA, when he shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

7. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g, senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained-without routine heavy use of overtime. However, in the event that unforeseen problems ,

require substantial amounts of overtime to be used, the following ~l guidelines shall be followed:

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

b. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between work periods, including shift turnover time.

d. The use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Not responsible for sign-off feature.

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I LA SALLE - UNIT 1 6-2 Amendment No. 6

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A0MINISTRATIVE CONTROLS A fredad4 Agdeviationfromtheaboveguidelinesshallbeauthorizedbythe"r:d= tier, A7 crvice kperintendent: for their individual departments, or higher levels i [ f management, o in accordance with established procedures and with docum

'*f of the basis for granting the deviation. Controls shall be included in the MM 3rocedures sucLt_ hat individual overtime shall be reviewed monthly by the P roduc ti o n " "--~ -" ha-4 a + a ada-"- -

lr been assigned. Routine deviation from to assure that excessive hours have not. /

the above guidelines is not authorized.

l- 39%Er

, 2. D. Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and l

- Training of Nuclear Power Plant Personnel," dated March 8, 1971. The

. $m/6 Apes b - M / Chem Scar"4eer shall meet the requirements of radiation protection

'( Evour*.se i manager of Regulatory Guide 1.8, September, 1975. The ANSI N18.1-1971 qualification requirements for S d/CF-- Technician may also be met by ,

either of the following alternatives:M WaMan' Pr&cG&.

1. Individuals who have completed the';" d/Chr Technician training program and have accrued 1 year of working experience in the specialty, or ~

2. Individuals who have completed the Od/Ch= Technician training C%&Ln'h(ade' 1 program, but have not yet accrued 1 year of working experience in the specialty, who are supervised by on-shift health physics -

supervision who meet the requirements of ANSI N18.1-1971 Section 4'3.2, " Supervisor Not Requiring AEC Licenses," or Section 4.4.4, " Radiation Protection.

E. Retraining and replacement, training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971 and Appendix "A" of 10 CFR Part 55, and shall include familiarization with relevant industry operational .

experience identified by the ONSG. p i F. Retraining shall be conducted at intervals not exceeding 2 years. M7 May !

Abcka r $a

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G. The Review and Investigative Function and the Audit Function of acEivities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below: .

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1. The Superintendent of the Offsite Review and Investigat e Function shall be appointed by the Manag-- ' "" '--- e-' ' ' e Aud4 h G eora6e A 4b Function shall be the responsibility of the Manager of belity $/45 Assurance and shall be independent of operations, Offsite Review and Investigative Function h"[f a. The Superintendent of the Offsite Review and Investigative Func- f tion shall: (1) provide directions for the review and investi-gative function and appoint a senior participant to provide appropriate direction, (2) select each participant for this func-tion, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary LA SALLE UNIT 1 6-3 AmendmentNo./

s N- s JNSERT 2

8. The Assistant Superintendent Operating shall hold a Senior Reactor Operator License.

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. . DISEE L 1 l

The Manager of QA/NS reports directly to the Chief Executive Officer !

and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety. Policy is promulgated through a central policy committee directed by the Manager of QA/NS. The Manager of QA/NS has 1 the responsibility for the performance of periodic audits of each nuclear !

station and corporate departments to determine that QA/NS policy is being carried out. I i

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,,v ADMIi1ISTRdTIVECONTROLS review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing.the review and investigative function,.

. idee Pre 3Ses 8df (5) approve and report in a timely manner all findings of non-de'/* % Man Vd compliance with NRC requirements to the '!uclear Station Manager, Staticm. Awb5emed (p,q/us, #.u/3 W' nt Vicc Prc;ident and Cencrci Manager _

a t acg:r of Quc'ity ^.;;urc = c, and thefVice President - Nuclea Operations. During periods when the Superintendent of Offsite M, *d NO 6dd] t Precams and Assessoo ; Review and Investigative Funct i on is unavailable,'he shall

designate this responsibility to an established alternate, who satisfies the formal training and experience for the Super-intendent of the Offsite Review and Investigate Function. The 4 responsibilities of the personnel performing this function are stated below. The Offsite Review and Investigative Function shall review: ,

i:

1) The safety evaluations for (1) changes to procedures, l equipment, or systems as described in the safety analysis i.

report and (2) tests or experiments completed under the provision of 10 CFR 50.59 ',o verify that such actions did l j

not constitute an unreviewed safety' question. Proposed 4

changes to the Quality Assurance Program description shall /

be reviewed and approved by the Manager of Q =lity ^.;; uran =. d /M

2) Proposed changes to procedures, equipment or systems which

) involve an unreviewed safety question as defined in 10 CFR 50.59.

3) Proposed tests or experiments which involve an unreviewed '

safety question as defined in 10 CFR 50.59.

4) Proposed changes in Technical Specifications or NRC operating licenses. il Noncompliance with NRC requirements, et of internal procedures, !

5) or instructions having nuclear safety significance. ,

6) Significant operating abnormalities or deviation from ,

normal and expected performance of plant equipment that '

affect nuclear safety as referred to it by the.0nsite Review and Investigative Function.

7) All REPORTABLE EVENTS. V

8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency P'.an prior to implementation of such change.

10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Sta-tion Manager, M;i; tant Vice PMshent-end-Genen4-Meneger -

hcicar Station;, and-Manager of Quality ^.;;urcn:c'.

Vhe Pre &d Bale opembonspnd AVP %dt y Peyrms ad Assessment .

LA SALLE - UNIT 1 6-4 AmendmentNo.Je

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i

, ADMINISTRATIVE CONTROLS b.Sfjm Audit Function 3

s<c. ten The4 Audit Function shall be the responsibility of the Manager Of 'u lity ^.ssure ne. independent of the Productier Depart Ont.E d D k.

Such responsibility is delegated to the Oi,ector-of Quality f MP ewlay Bayams [*Nintenance) esetencedspers t4 enn-a nd-t he-9+ rector-e fAuauty-Awwam e Nuc/ ear- Gue6ty Roy rams Nanayo, ,

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N Alueb'ar* Gionl,"i fr foms Ns nq

] {itherofIepheve.,ordesightedCorpodaTeStafforSupervisor n L approved by the#eneger-of= Quality f: upaMdh shall approve the W audit agenda an'd checklists, the findings and the report of each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits shall be per-formed to assure that safety-related functions are covered within a period of 2 years or less as designated below.

1) Audit of the conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.

2) Audit of the adherence to procedures, training and qualifi-cation of the station staff at least once per year.

3) Audit of the results of actions taken to correct defi-ciencies occurring in fa'ctlity equipment, structures, sys-O tems, or. methods of operation that affect nuclear safety at least once per 6 months.

4) Audit of the peformance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50.

5) Audit of the Facility Emergency Plan and implementing procedures at least once per 12 months. ,

6) Audit of the Facility Security Plan and implementing procedures.

7) Audit onsite and offsite reviews.

8) Audit the Facility Fire Protection Program and implementing procedures.

9) The radiological environmental monitoring program and the results thereof at least once per 12 months.

10) The OFFSITE DOSE CALCULATION MANUAL and implementing

-- ptocedures.

O LA SALLE UNIT 1 6-5 Amendment No, f

^ .

ADMINISTRATIVE CONTROLS

' Audit

Function (Continued)

11) The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes.

12) The performance of activities required by the Company

, Quality Assurance Program and Procedures to meet the e .

criteria of Regulatory Guide 4.15, December 1977, at least g g ,[QA//$j Yice once per 12 months.

f).cs,*d e ( Ew/2 ogradf ods, Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Manager, //

We auoM.y % rams ad ager-of-Nuclean4afetyr-the-Assistent Vice ." resident end- A gnessmentj /de Sen$r enerd Manager -4uc4 ear 4tationsdanager-of-Qulity Assunnte, ee-V4ce-Chafrman r -and-the-Vice-President -Juclear- Operatione -

thef fbes Ye h NUC W

@ h.5 CP**G3 #g g 4fp/

The Manager of Quality A::urent: reports to the Chairman (4 M.<fodf of .h offee'r ' '

ofed43 c/,4cer , 30:rd :nd the Super #ntendent of th Of4 cite hvi= nd Irv::tig:-

tiv Functi:n , y ...., ......m.~r. ......._..~,n,e

die:Manacer of&lity Assurenc; er the Superintendent Of th:

m....m-f c-Offsite ."evieV &nd Invest 49ation Functica has the authority to r - order unit shutdown or request any other action which he deems

, N.S J necessary to avoid unsafe plant conditions.

. eCords a

/N3i9e7~4 1) Reviews, audits, and recommendations shall be documented j and distributed as co ired in 6.1.G.1.a and 6.1.G.1.b i

2) Copies of documentation, reports, and correspondence shall O-be kept on file at the station.

e. Procedures Written administrative procedures shall be prepared and maintained for the offsite reviews and investigative functions described in Specification 6.1.G.1.a. and for the audit functions described in Specification 6.1.G.1.b. Those procedures shall cover the following:

1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative l Function.

2) Use of committees and consultants.

3) Review and approval.

4) Detailed listing of items to be reviewed.

5) Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations of reviews and investigations, (4) approving reports, and (5) distributing reports.

6) Determining satisfactory completion of action required

" based on approved findings and recommendations reported by personnel performing the review and investigative function.

O LA SALLE UNIT 1 6-6 Amendment No.

L_

r INSERLs

'The'AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations. The AVP Quality Programs and Assessment-has the authority.

to recommend unit shutdown or request any other. action which he deems necessary to avoid unsafe plant conditions. All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.

0043V l

'ADIMINSTRATIVE CONTROLS

.a .

L.)

Offsite Review and Investigative Function (Continued) f) Radiological Safety Engineering graduate or equivalent with at least i 5 years of experience in radiation control and safety. j.

g) Reactor Safety Analysis Engineering graduate or equivalent with at least 5 years of experience in nuclear engineering.

h) Instrumentation and Control Engineering graduate or equivalent with at least i 5 years of experience in instrumentation and control ;

design and/or operation.

1) Metallurgy

{j Engineering graduate or equivalent with at least j!

5 years of experience in the metallurgical field. ll

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3) The Superintendent of the Offsite Review and Investigative ll Function shall have experience and training which satisfy !l ANSI N18.1-1971 requirements for plant managers. I

2. The Onsite Review and Investigative Function shall be supervised by the Station Manager.

A a. Onsite Review and Investigate've Function U The Station Manager shall: (1) provide direction for the Review and Investiga'tive Function and appoint the Technical Staff Super- - '

'l visor, or other comparably qualified individual as a senior par- i; ticipant to provide appropriate directions; (2) approve partici-pants for this function; (3) assure that a component bf more than one participant who collectively possess background and qualifica- 3; tions in the subject matter under review are selected to provide it comprehensive interdisciplinary review coverage under this func-tion; (4) independently review and approve the findings and recom- ;

mendations developed by personnel performing the Review and In- ,

vestigative Function; (5) report all findings of noncompliance l with NRC requirements, and provide recommendations;t: the A: sis-ent Vice -Pres 4 dent and General-Manager - Sc4 ear Stati:ns and g f'l 1 th: perStendent cf th: Off:it: Review and Investigative rune-44+m and (6) submit to the Offsite Review and Investigative Func- ,

tion for concurrence in a timely manner, those items described '

in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function.

The responsibilities of the personnel performing this function are stated below:

m) 1 Review of (1) procedures required by Specification 6.2 and changes thereto, (2) all programs required by Specification 6.2 and changes

4M~ theretc, and (3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.

(sp(<5 2)

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Review of all proposed test and experiments that affect nuclear safety.

LA SALLE UNIT 1 6-8 Amendment No.

u_.________---___. - _ _ m

ADMINISTRATIVE CONTROLS m

b Onsite Review and Investigative Function (Continued)

3) Review of all proposed changes to the Technical Speci-fications.

4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

5) Investigation of all noncompliance with NRC requirements ,i and shall prepare and forward a report covering evalua- 'l tion and recommendations to prevent recurrences,e-the- -!

t :i:t:nt "i : Prc;id:nt :nd Cencr-1 ".:n:g r - %:lecr j

-Stati:n: and t; the Superintendent ;f th: Off:it kei x /

and :r'; :tigat!': % n:tfan.,

6) Review of facility operations to detect potential safety hazards.

7) Performance of special reviews and investigations and >

j' reports thereon as requested by the Superintendent of the Offsite Review and Investigative Function. /

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f)ghbr' /drPyg/c *

) Review of the Station Security Plan and shall submit recommended changes to the ^zsistant ute o. m . 7.f , ,/. -

&curhJodS MP Gualb ~ . , u...... _ u ,... e+a... ,

n opms w,a apesms,a in " ' " " " ' ' ~ " ' " " " " ' ' - ' ~ ~ ' ' ' ~ " "

idul.Ac. h. 00A -

/jg(f./&64 A 9) Review of the Emergency P1 station implementing pro-ce p es a Q ggg{_{ g y commen p _ change g y.j,.},ggj(( j

\accordanca wlA SpodE*de _,

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. 10) Review of. reportable events and actions taken to prevent recurrence.

11) Review of every unplanned onsite release of radioactive !

i material to the environs including the preparation and forwarding of reports covering evaluation, recommendations ~

and disposition of the corrective action to prevent recur-renc j "u:Lje:rteStation:the Aasistent

nd to "the ice Supef4ntendent re:! dent :nd C of-th: ncr:1 "anag:r Off:ite -

-Review and Investigative Function, s u '

12) Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

b. Authority The Technical Staff Supervisor is responsible to the Station f Manager and shall make recommendations in a timely manner in all g areas of review, investigation, and quality control phases of plant maintenance, operation, and administrative procedures i

relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is >

necessary. TheStationManagershallfollowsuchrecommendations[ y or select a course of action that is more conservative regarding '

% cE- [/t s,ch d 8 d ' safe op'eration of the facility. All such disagreements shall be uf reported immediately to the ^::i: tant "ic Pr::ident and C ncrc.1

'Lumi ."w Iser-Staticiu and the Superintendent of the Offsite Review and Investigative Function. #

'. / ,

LA SALLE UNIT 1 6-9 Amendment No. 4 o

._ __=__a

ADMINISTRATIVE CONTROLS n

Onsite Review and Investigative Function (Continued) mpared andMW

c. Records

1) Reports, reviews, investigations, and recommendations shall r j be documented with copies to the 4::ictant "ic "resi ent N. b 58df^t umm - .v. . .m m u r , ,_,m, .. .icn , the Superintendent /

L FWR. operab51 of the Offsite Review and Investigative Function, the Sta-

~

tion Manager, and the Manaaer of Qualit" As:urance; )/

MP b.aaGtu rrwdms and Assessme$.

2) Copies of all records and documentation shall be kept on file at the station.

d. Procedures Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative Function.

These procedures shall include the following:

1) Content and method of submission and presentation to the i Station Manager, fa;i; tent Vice President end Genecel omoom .m.m. - -...m ,

Offsite Review and Investigative Function.

and the Superintendent of the )). -

2) Use of committees.

3) Review and approval.

4) Detailed listing of items to be reviewed.

/~~) 5) Procedures for administrate'idn of the quality control V activities.

6) Assignment'of responsibilities.

e. Personnel

1) The personnel performing the Onsite Review and Investiga-tive Function, in addition to the Station Manager, shall k consist of persons having expertise in: '

a) nuclear power plant technology, b) reactor operations, c) reactor engineering, d) radiological safety and chemist, e) Instrumentation and control, and f) mechanical and electric systems.

2) Personnel performing the Onsite Review and Investigative Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.

H. Fire Protection Program l

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either

[

qualified offsite licensee personnel or an outside fire protection firm.

An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

LA SALLE UNIT 1 6-10 Amendment No.

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-= gm = === .

== == g-a l- Ww M- .

m

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g

YEN =

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una = :: ==

n =e m A = 2 G , ,

LA SALLE - UNIT 1 6-11 Amendment No.

. _ _ _ _ _ _ - _ _ _ - _ _ _ _ . . _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ ____i

FIGURE 6.1-2 - DNA '

e

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w. = ,

65

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LA'SALLE - UNIT 1 6-12 Amendment No.

\

'l

_ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ __ ii

-.c j .,- ,

Fiaure 6.1-3 MINIMUM SHIFT CREW COMPOSITION

. WITH UNIT 2 IN CONDITION 1, 2, OR 3 l

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSIT 10" j CONDITIONS 1, 2 and 3 CONDITIONS.4 and 5 l

a a SE .l y a

SF l None D

R0 2 1 D

i ,A0 2 1 a

-SCRE l Hone. j or,'whenever a SCRE (SR0/STA).is not included in the shift crew composition, the minimum shift crew composition shall be as "

-follows:

WITH UNIT 2 IN CONDITION 1, 2, OR 3 p POSITION- NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITIONS 1, 2 and 3 CONDITIONS 4.and 5- -

8 SE 1" 1 8

SF 1 None '<

D RO 2 1 b !-

A0 2 y a

STA l None WITH UNIT 2 IN CONDITION 4 OR 5 OR DEFUELEO POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITIONS 1, 2 and 3 CONDITIONS 4 and 5 SE l a ya SF 1 None R0 2 1 b

A0 2 2 N STA 1 None

'LA SALLE - UNIT 1 6-13 Amendment No. 18

l * '

f' N Figure 6.1-3 (Continued)

N] '~'

MINIMUM SHIFT CREW COMPOSITION -

NOTES a/ Individual may fill the same position on Unit 2.

b/ One of the two required individuals may fill the same position on Unit 2.

SE - Shift Supervisor (Shift Enaineer) with a Senior Reactor Operators License on Unit 1.

SF - Shift Foreman with a Senior Reactor Operators License on Unit 1.

R0 - Individual with a Reactor Operators License on Unit 1.

A0 - Auxiliary Operator.

SCRE - Station Control Room Engineer with a Senior Reactor Operators License.

Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Figure 6.1-3 for a period of time not to i exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew >

composition to within the minimun requirements of Figure 6.1-3. This ,

provision does not permit any shift crew position to be unmanned upon shift -

change due to an oncoming shift crewman being late or absent.

While the unit is in OPERATIONAL CONDITION 1, 2, or 3, an individual with a valid SRO license shall be designated to assume the Control Room direction

~~. function. While the unit is in OPERATIONAL CONDITION 4 or 5, an individual

.' -- ) with a valid SRO or R0 license shall be designated to assume the Control Room direction function.

i I

7 ~N d ,

LA SALLE - UNIT I 6-14 Amendment No.18

ADMINISTRATIVE CONTROLS 6 1 1 HIGH RADIATION AREAS 6.1.1.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR 20, in lieu of the

" control device" or " alarm signal" required by paragraph 20.203(c)(2) of #

b 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr* but less than 1000 mrem /hr* 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 (RWP). Individuals ;

qualified in radiation protection procedures,- .:., e t d/CF r to:F .:: A or personnel continuously escorted by such individuals, may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas in which the intensity of radiation is greater than 100 mrem / ) .,l, I

hr* but less than 1000 mrem /hr*, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

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 in the area.

b. A radiation monitcring 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 knowledgeable of them.

c. A health physics qualified individual, i.e., qualified in radiation

@ protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physicist in the Radiation Work Permit (RWP).

6.1.1. 2 In addition to the requirements of 6.1.1.1, above, for areas accessible .

to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greatar than 1000 mrem *, the computer shall be programmed to permit entry through locked doors for any individual requiring [{'

access to any such High-High Radiation Area; for the time that access is required.

6.1.1.3 Keys to manually open computer controlled High Radiation Area doors '

and High-High Radiation Area doors shall be maintained under the Administra-tion control of the Shift Supervisor on duty and/or the Health Physicist.

6.1.1.4 High-High Radiation areas, as defined in 6.1.1.2 above, not equipped with the computerized card readers shall be maintained in accordance with 10 CFR 20.203 c.2 (iii), locked except during periods when access to the area

[

is required with positive control over each individual entry, or 10 CFR 20.203.c.4.

In the case of a High Radiation Area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted.

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 area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the ,

body could receive in one hour a dose in excess of 1000 mrem

that are located withi

Measurement made at 18" from source of radioactivity.

LA SALLE UNIT 1 6-15 Amendment No. $-

J

L. s.-

.yj

. ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued)

B. Radiation control procedures shall be maintained, made available to all; station personnel, and adhered to. These procedures shall show-permissible: radiation exposure'and shall be consistent with the requirements of:10 CFR'20. This radiation protection program shall.be.

organized to meet the requirements of 10 CFR 20.

C. 1. Procedures for items identified in Specification 6.2.A and'any changes to such procedures shall be reviewed and approved by.the Operating Engineer and the Technical Staff-Supervisor-in the areas of operation, fuel handling, or instrument maintenance, and by the

/t Mgoce Assistant Super;ntendent M:19t :: :: and Technical Staff. Supervisor in.the areas of plant maintenance and plant inspection. Procedures g for. items identified in Specification 6.2.B and any changes to such .j procedures shall be reviewed and approved by the Technical Staff "

supervisor and the7:df atf:n Chrf:try ;;r;f:;r. At least one ./

F .

personapprovingeachoftheaboveproceduresshallholdavalid r

T senior operator s license. In addition,'these procedures and changes .

+

( S8P' Mr thereto, must have authorization by the Station Manager before being implemented. f

2. Work and instruction type procedures which implement approved main'-

NobC#m tenance or modification procedures shall be approved.and authorized

.by the4 Assistant Superintendent "; int:r.;;;;-where the written authority j has been provided by the Station Manager. The" Maintenance / Modification Procedure" utilized for safety-related' work shall be so approved only if procedures refe'ren'ced in the " Maintenance / Modification Procedure" have been approved as required by 6.2.A. Procedures which do not fall within the requirements of 6.2,A or 6.2.8 may be spproved by tne Department Heads. -

D. Temporary changes to procedures 6.2.A and 6.2.B above may be made .

provided: 7 l

1. The intent of the ot winal procedure is not altered. i

2. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's Licese on the unit affected.

3. The change is documented, reviewed by the Onsite Review and Investi-gative Function and approved by the Station Manager within 14 days p of implementation.

E. Drills of the emergency procedures described in Specification 6.2.A.4 shall be conducted at frequencies as specified in the Generating Stations Emergency Plan (GSEP). These drills will be planned so that during the course of the year, communication links are tested and outside agencies are contacted. ' ~

O LA SALLE UNIT 1 6-17 AmendmentNo.4f

_ __-__=___-_ _ - _ - - - _ - - _ .

0

.4 c

a y q

ADM]NISTR.ATIVECONTROI.S L PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) j F. The following programs shall' be established, implemented, and m$intained:

1. Primary Coolant Sources Outside Primary Containment A program to reduce leakage from those' portions;of systems outside primary containment that could contain highly . radioactive fluids during a serious transient or accident to a's. low'as practical' levels.

The systems include LPCS, HPCS, RHR/LPCI, RCIC, hydrogen recombi.ner, process sampling, contairenent monitoring, and standby gas treatment systems. The program El include the following:

a. Preventive maintenance and periodic visual inspection require-ments, and ,

b. Integrated leak test requirements for.each system at. refueling cycle-intervals or-less.

2. In-Plant Radiation Monitoring +t A' program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

'a. Training of personnel,

b. Procedures for mpnitoring, and

c. Provisions for maintenance of sampling and analysis equipment. ;

3. Post-accident Sampling -

A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulate'in plant gaseous effluents, >

and containment atmosphere samples under accident conditions. The program. !:

shall. include the'following: [

a. Training of personnel,

b. Procedures for sampling and analysis,

c. Provisions for maintenance of sampling and analysis equipment.

6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT l OPERATION !

The following actions shall be taken for REPORTABLE EVENTS:

[

a. The Commission shall be notified and a Licensee Event Report

. submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed pursuant to Specifi-cation 6.1.G.2..e @ h c Oj, LA SALLE UNIT 1 6-18 Amendment No.

i 1

L L=

ADMINISTRATIVE CONTROLS !

.7

\va. e~sa. se w 1 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED i

If a safety limit is exceeded, the reactor shall be shut down immediately l pursuant to Specification 2.1.1,2.1.2and2.1.3,andcriticalreactoroperation/

shall not be resumed until authorized by the NRC. The conditions of shutdown /

shall be promptly reported to the S::i;t nt Vic: President and Ceneral t' nager Nuclear-Staticas or his designated alternate. The incident shall be reviewed l

pursuant to Specifications 6.1.G.1.a and=5.' O.2.c and a separate License Event j Report for each occurrence shall be prepa d in accordance with Section 50.73 i to 10 CFR Part 50. The NRC Operations soon as possible and in all cases withi oneChour. tershallbenotifiedbytelephoneas/,

The Assistent Vice Presidene-and Cenerel Menege.- Nuclear St:ti;n: nd the Manager ef3Nucler Safety shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . O Fsite fes,e M h 6 & fu d 44 3

6.5 PLANT OPERATING RECORDS [ /. (3.2..o) {

A. Records and/or logs relative to the following items shall be kept in a i-manner convenient for review and shall be retained for at least 5 years: [

i

1. Records of normal plant operaticn, including power levels and periods of operation at each power level; .,

2. Records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to Q nuclear safety;

3. Records and reports of reportable events;

4. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met. All equipment failing to meet surveil-lance requirements and the corrective action taken shall be recorded;

5. Records of changes to operating procedures;

6. Shift engineers' logs; and

7. Byproduct material inventory records and source leak test results.

O LA SALLE UNIT 1 6-19 Amendment No e

4

, IADMIN151kA' JIVE CONTROLS-

. Semiannual Radioactive Effluent Release Report (Continued)

The radioactive effluent release report shall include.the following

-information for each type of solid waste shipped offsite during the

. report period: -

a. Container volume,

b. ' Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by .

measurement or estimate), -

d. Type of waste -(e.g. , spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g. , LSA, Type A, Type B, Large Quantity), I and.

f. Solidification agent (e.g. , cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the. site to unrestricted areas of radioactive materials

'in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

5. Monthly Operating Report Routine reports of operating statistics and shutdown experience, including documentation of all challenges to safety / relief valves, A/ue/cor- /b6 shall-be submitted on a monthly basis to the Director, Office of

.gy, M a n Nai/ "";n;;;m:nt Inferntion and Program C;ntr:1, US Nuclear Regulatory ;

L gg pj,,37 fCommission, Washington,DC20555,withacopyoftheappropriate ,

Regional Office, to arrive no later than the 15th of each month j following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted I with the Monthly Operating Report within 90 days in which the change (s) was made effective. ~In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by Onsite Review and Investigative Function, i'

B. Deleted

/

LA SALLE UNIT 1 6-24 Amendment No.

l i

3 - .,1<

t*

,. LIST OF: FIGURES FIGURE 'PAGE

]

3.1.5-1 SODIUM PENTABORATE SOLUTION TEMPERATURE /

CONCENTRATION REQUIREMENTS ........................ 3/4 1-21 !

3.1.5-2 SODIUM PENTABORATE (Na 2 10B 016 10 H O) 2 VOLUME / CONCENTRATION REQUIREMENTS l................. 3/4 1-22 3.2.1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPES 8CRB176 8CRB219 and 8CRB071 ........................,.........,.......... 3/4 2-2 3.2.1-2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE FUEL TYPE.

BP8CRB299L. .............................,.......... 3/4 2-2(a) .

3.2.1-3 MAXIMUM AVERAGE ~ PLANAR LINEAR HEAT GENERATION RATE i (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, FUEL TYPES BC3000 AND BC320C............................ 3/4 2-2b ;

3.2.3-la MINIMUM CRITICAL POWER RATIO (MCPR) VERSUS I AT RATED FLOW .................................. 3/4 2-5 ' ('

3.2.3-lb MINIMUM-CRITICAL POWER RATIO (MCPR) VERSUS T AT RATED FLOW FOR END OF CYCLE RECIRCULATION PUMP TRIP AND MAIN TURBINE BYPASS SYSTEMS INOPERABLE ... 3/4 2-Sa 3.2.3-2 Kf FACTOR ......................................... 3/4 2-6 3.4.1.5-1 CORE THERMAL POWER (% OF RATED) VERSUS TOTAL CORE FLOW (% OF RATED) .................................. 3/4 4-5c 3.4.6.1-1 MINIMUM REACTOR VESSEL METAL TEMPERATURE VS. REACTOR VESSEL PRESSURE ....................... 3/4 4-19 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST ........ 3/4 7-33 B 3/4 3-1 REACTOR VESSEL WATER LEVEL ........................ B 3/4 3-7 B 3/4.4.6-1

CALCULATED FAST NEUTRON FLUENCE (E>1MeV) at 1/4 T AS A FUNCTION OF SERVICE LIFE ..................... B 3/4 4-7 8 3/4.6.2-1 SUPPRESSION P0OL LEVEL SETPOINTS .................. B 3/4 6-3a 5.1.1-1 EXCLUSION AREA AND SITE BOUNDARY FOR GASEOUS AND LIQUID EFFLUENTS .............................. 5-2 5.1.2-1 LOW POPULATION ZONE ............................... 5-3 6.1-1 EURPORATE:fW8ACDet#2. . 46.WA . . . . . . . . . . . . . . . . . . 6-11 6.1-2 ' UFilT ORCAltt2At202. . . . AGF/Kb. . . . . . . . . . . . . . . . . . . . . 6-12 l 6.1-3 MINIMUM SHIFT CREW COMPOSITION .................... 6-13 LA SALLE - UNIT 2 XIX Amendment No.

6.0 ADMINISTRATIVE CONTROLS

(

\

6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A. ?^ "'en eneger shall have-everall full-tim: respon:ibili ' ' - ;fo p operation o During periods when t t s /

unavailable, he shall designa e '

1 ity tu an established i

.lternate who w is?ie3 un SI N18.1 of Marc , ' nce 1 2 ;_ n:m:nt for plant manager flHMAT*1. B. The Shift Supervisor shall be responsible for directing and commanding . 3

%ee I the overall operation of the facility on his shift. The primary manage- FPes[ dent l ment responsibility of the Shift Supervisor shall be for safe operation y '

of the nuclear facility on his shift under all conditions.

directive signed by 4::fetent Vice Preefdent end Central M:n:ger - NuclemA manag itations emphasizing this primary management responsibility and that clearly establishes the command duties of the Shift Supervisor shall be

[

reissued to all station personnel on an annual basis.

/ The :crporate manag:::nt which-relates-to-the-operat4cn of-thi: :tatich is shown in figur; S.1-1. j C. The nereal functional cr-gaMiath-for-operath-of-the-stat"- "' "

~ 'as sh;wn in figur: 5.1-2. The shift manning for the station shall be as l; g shown in Figure 6.1-3. The individual filling the position of ^,::i:t nt gg[#'/' ' Sup;rint:ndent Technical-Serv 44es shall meet the minimum acceptable level f ' ',

for " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971.

[P"7~c4mM "crvic:: e The individuals filling the positions of Production Superintendent and Superintendent shall meet the gipimum acceptable level for " Plant f.,

Manager" as described in Section 4.2.1 of A'NSI N18.1-1971. '

1. At least one licensed Reactor Operator shall be'in the control room when fuel is in the reactor. In addition, while the reactor is in ,

OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator who has been designated by the Shift Supervisor to l assume the control room direction responsibility shall be in the .

Control Room. [,

2. A te-ith phy:f:: technician

shall be on site when fuel is in the h o r.

3. All CORE ALTERATIONS shall be observed and directly supervised by (Fa.d bon, either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities pro w 6,n during this operation.

4. A site Fire Brigade of at least 5 members shall be maintained onsite at all times". The Fire Brigade shall not include the Shift Supervisor, the Station Control Room Engineer and the 2 other members of the mini-mum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

The M th phy:fj: technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accomodate unexpected absence provided immediate action is taken to fill the ,<

p required positions.

V LA SALLE - UNIT 2 6-1 AmendmentNo.y 11

e ,

i i

1

. l INSERT 1 A. Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. .The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant. .

1. Lines of authority, responsibility, and communication shall be established and_ defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms j of documentation. These requirements shall be documented in the !

Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Relationships.

2. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. )

3. The Senior Vice President-Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall'take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

4. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate unsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

e

e e

b i

. 1 ADMI'NISTRA' TION CONTROLS j

! ADMINISTRATION CONTROLS

5. The Onsite Nuclear Safety Group (0NSG) shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operat-ing experience information, including plants of similar design, which may indicate areas for improving unit safety. The ONSG shall be composed of at least three, dedicated, full-time engineers of multi-disciplines located on site and shall be augmented on a part- #

[

time basis by personnel from other parts of the Commonwealth Edison Company organization to provide expertise not represented in the group. The ONSG shall be responsible for maintaining surveillance of unit activities to provide independent verification that these activities are performed correctly and that human errors are reduced as much as practical. The ONSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activi-ties, operations activities or other means of improving unit safety to the

%%,Gir::ter, 'bcle:r S:f:ty. Safeg Assessmeed Nomyer and44r Man spr.

6. The Station Control Room Engineer (SCRE) serves as the lead control room SR0 during normal operations and as the Shift Technical Advisor (STA) during abnormal operating and accident conditions. In the event of abnormal operating or accident conditions, the SCRE will relinquish his job as control room SR0 to the Shift Foreman and will assume the role of STA, when he shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

7. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g. senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time,

b. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in I any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between work periods, including sh'ift turnover time.

d. The use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Not responsible for sign-off feature. 1 LA SALLE - UNIT 2 6-2 Amendment No.

ADMINISTRATION CONTROLS

@ Any deviation from the above guidelines shall be authorized by the Production y_.

o cervice: Superintendents for their individual departments, or higher levels

o management, in accordance with established procedures and with documentation 7.Q g /(lcedures of the basis for granting the deviation. Controls shall be included in the pro-such that individual overtime shall be reviewed monthly by the Produc-1 tion oiN = fcca Superintendents to assure that excessive hours have not been assigned. Ra tine deviation from the above guidelines is not authorized.

' /A/sm-2 [ D. Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971. The NeeN4 % d/Ch e Supervisor shall meet the requirements of radiation protection A,7fo i manager of Regulatory Guide 1.8, September,1975. The ANSI N18.1-1971 ,

qualification requirements for-R:d/Che Technician may also be met by I either of the following alternatives: t%&b4 Fr ofec6&i /

1. Individuals who have completed the R:d/Chd Technician training program and have accrued 1 year of working experience in the specialty, or

2. Individuals who have completed the Rad / Chem Technician training program, but have not yet accrued 1 year of working experience in the specialty, who are supervised by on-shift health physics supervision who meet the requirements of ANSI N18.1-1971 Section '

4.3.2, " Supervisor Not Requiring AEC Licenses," or Section 4.4.4,

" Radiation Protection."

& E. Retraining and replacement training of Stat' ion personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated' March 8, 1971 and Appendix A of 10 CFR Part 55, and shall include familiarization with relevant industry operational experience identified by the 0NSG.

, Gusty Azurwe/

F. Retraining shall be conducted at intervals not exceeding 2 years. l Nodev 5/c(h G. The Review and Investigative Function and the Audit Function of activities /

WCM/A/C.h affecting quality duringand have the responsibilities facility operatiuns authorities shall outlined be constituted and j below: -

1. The Superintendent of the Offsite Review and Invest i Function y Ae44-t shall be appointed by the Manager of Nuclear Safet.[,. The

/

Nelity

[corpoede Subfunction -Aswr4nse and shall shall be the be independent responsibility of the Mana of operations, Offsite Review and Investigative Function a.

3 TheSuperintendentoftheOffsiteReviewandInvestigativeFunc-f tion shall: (1) provide directions for the review and investi-gative function and appoint a senicr participant to provide appropriate direction (2) select each participant for this s

function, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdis-ciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed g by personnel performing the review and investigative function, LA SALLE - UNIT 2 6-3 Amendment No.

l.. ..

. * : .s l

~1NSERT 2 L

8. The Assistant Superintendent Operating shall hold e Senior Reactor Operator License.

i,

e-

r. 1RSERT 3 The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety. Policy is promulgated through a central.

policy committee directed by the Manager of QA/NS. The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate departments to determine that QA/NS policy is being carried out.

l l

1

7 ADMINISTRATION CONTROLS

() Offsite Review and Investigative Function (Continued)

"g _ (5) approve and report in a timely manner all findings of non-compliance with NRC requirements to the Station Manager, ^ztic-g9 g* Q

. = tant " ice resident and Ccacral Manager - Mucicar Station;, g,,y '

B4Ae OPeradMs j Han29er Of Quality ^: erence, and thefVice President - Nuclear n

//o e o[6M//15, Operations. During periods when the Superintendent of Offsite g' dM Review and Investigative Function is unavailable, he shall

, designate this responsibility to an established alternate, who hv'5sdad (MP) bl satisfies the formal training and experience for the Superin-

/ pop,,,, ,n d i tendent of the Offsite Review and Investigate Function. The responsibilities of the personnel performing this function are

/haessmenf> m stated below. The Offsite Review and Investigative Function shall review:

1) The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis ,:

report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question. Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality M:urance.GA/AU,

2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.

V 3) Proposed tes'ts or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.

4) Proposed chanaes in Technical Specifications or NRC operating ,

licenses.

5) Noncompliance with NRC requirements, or of internal procedures, .

or instructions having nuclear safety significance. !

6) Significant operating abnormalities or deviation from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.

7) All REPORTABLE EVENTS. p

8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.

10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, ^, :i; tant " ice resident and Ccncr:1 Manageea -

-Nuclear Station:, 2nd u3n3ger gf gg33ity a,;;g7;n c,

, b c'l' OeSabltyk Z$WR Opus lths, and the AL/P C2uaOy OQ **S ij and Assessment .

LA SALLE - UNIT 2 6-4 Amendment No. [

L. 4.

, .j

]

, ADMINISTRATION CONTROLS j b.bI it Function \ W# #F"* ,-

Su,-

ThexAudit Function shall be the responsibility of the S n:; r ,

ef Qu:lity ^.::er:n:: independent of the Pr:ductier Dep:rtment.-

I f - gyp @4/4 '

Such responsibility is delegated to the-Director of Qu:lity l y f>::uren : :nd th: Dir::t:r of Quclity M:ur:n;;

g (Oper:ti:n:)

-(" inten:nceh "' 1 / g g gf 9 pu y gg {

~

\ Cither of , or designated Corporate Staff or Supervisor . p N approved by thed:n:g:r f Quality ^.::ur:n::, shall- approve the # 3 audit agenda and checklists, the findings and the report of each !

audit. Audits shall be performed in accordance with the Company I Quality Assurance Program and Procedures. ' Audits shall be per- l formed to assure that safety related functions are covered withia 1 a period of 2 years or less as designated below.

1) Audit of the conformance of facility operation to provisions contained within the Technical Specifications and applicable ;

license conditions at least once per year.

2) Audit of the adherence to orocedures, training and qualification of the station staff at least once per year.

3) Audit of the results of actions taken to correct deficiencies occurring in faci Mty equipment, structures, systems, or methods of operation that affect nuclear safety at least once per~6 months.

t

4) Audit of the peformance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50.

5) Audit of the Facility Emergency Plan and implementing I.

procedures at least once per 12 months.

6) Audit of the Facility Security Plan and implementing procedures.

7) Audit onsite and offsite reviews.

8) Audit the Facility Fire Protectior Program and implementing procedures.

9) The radiological environmental monitoring program and the results thereof at least once per 12 months.

10) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.

lit The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes.

f.A SALLE - UNIT 2 6-5 Amendment No.

- ----- _ --- - - - - - - - - - _ _ - - _ a

ADMINISTRATION CONTROLS Audit Function (Continued) ,

-, 12) The performance of activities required by the Company

_ Quality Assurance Program and Procedures to meet the g,f .-

,/ ggjy/ gy .

criteria of Regulatory Guide 4.15, December 1977, at least once per 12 months.

Hmt4otit BWe OpeedMS>

NP&a Report all findings of noncompliance with NRC requirements and Assemit Me racr%.

Seny b o*5ger urecommendations and results of each audit to the Station Manager, d Of Nu:4 ear Ofety, the ^::i: tent Vic: recident and j

He,& As[dorf- A/ue.k Mrd-Manager =--#uc4 ear Station:, Man:geraf Quality ^. :ur:nce, a

M oper bis,oad f4e CAsp the Vice Chatma+,--and-the-V4c0 Prc:ident - Nu:40:r Oper:ti:n:.

Operafo*M CHEr. c. Authority g& g g3 g . l The Manager of'Qu:lity A.._urance reports to the .h: rmen Of the

-hard and the SupeAtendent-of4he-M4s44e-Rev4ew :nd Inves44-W ye %nction reports to the u neger--of-4boleer 5:fety. Either [

'N Me Manaaer of Qu lity A::urance er the Superintendent f th:

c Of f:ite hviciand Inve:tigation unction has the authority to order unit shutdown or request any other action which he deems t - -

necessary to avoid unsafe plant conditions. -

S j/AlsEAT4[ d. Records

1) Reviews, audits, and recommendations shall be documented.

and distributed as covered in 6.1 G.1.a and 6.1.G.I.b

2) Copies of documentation, reports, and correspondence shall be kept on file at the station.

e. Procedures ...

Written administrative procedures shall be prepared and ma ntained for the offsite reviews and investigative functions described in Specification 6.1.G.1.a. and for the audit functions described in Specification 6.1.G.1.b. Those procedures shall cover the following:

1) Content and method of submission of presentations to the Superintendent of the Office Review and Investigative Function. M(/

2) Use of committees and consultants.

3) Review and approval.

4) Detailed listing of items to be reviewed.

5) Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations of reviews and investigations, (4) approving reports, and (5) distributing reports.

6) Determining satisfactory completion of action required based on approved findings and recommendations rep ~orted by

_ personnel performing the review and investigative function.

O LA SALLE - UNIT 2 6-6 Amendment No. ,

A e;

i

. . j 1

INSERT 4 1

I The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations. The AVP Quality Programs and Assessment has the authority to recommend unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions. All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.

ll 1

0043V

l

. 1

*. j ADMINISTRATION CONTROLS 3 i

?(~T V Offsite Review and Investigative Function (Continued)

{

1 f) Radiological Safety -

Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety. ~

g) Reactor St.fety Analysis Engineering graduate or equivalent with at least 5 years of experience in nuclear engineering.

h) Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.

i) Metallurgy Engineering graduate or equivalent with at.least 5 years of experience in the metallurgical field.

3) The Superintendent of the Offsite Review and Investigative Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.

2. The Onsite Review and Investigative Function shall be supervised by '

the Station Manager. ,

a. Onsite Review and Investigative Function eg f

\j The Station Manager shall: (1) provide direction for the Review I and Investigative Function and appoint the Technical Staff Super-visor, or other comparably qualified individual as a senior par-ticipant to provide appropriate directions; (2) approve partici-pants for this function; (3) assure that a component of more than one participant who collectively possess background and qualifica-tions in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; ,

(5) report all findings of noncompliance with NRC requirements, and provide recommendations t; the Assistant "ic: President and-Gen-- v er:1 M:n:g:r-Muclear Station:-:nd the Super 4ntendent Of th: Off:it:- )

bi= :nd Inve:tigative Func44FH and (6) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function.

The responsibilities of the personnel performing this function are stated below:

1) Review of (1) procedures required by Specification 6.2 and changes l thereto, (2) all programs required by Specification 6.2 and changes fa g thereto, and (3) any other proposed procedures or changes thereto as p s spaces determined by the Station Manager to affect nuclear safety. /

2) Review of all proposed test and experiments that affect nuclear safety.

k l

LA SALLE - UNIT 2 6-8 Amendment No

y * '

. , ' ADMINISTRATION ~ CONTROLS

'{ % , .

V Onsite Review and' Investigative Function (Continued)

-3) Review of~a11' proposed changes to the Technical Speci -

fications. '

4)- Review of a11' proposed changes or modifications to. plant systems or equipment that' affect nuclear safety.

5) Investigation of a11' noncompliance with NRC requirements and shall prepare and forward a report covering evalua-tion and recommendations to prevent recurrence

^::it:ntVic:"r::id:nt:nd0:ncr:1M:n:g:rJ.;ee-Me

. ;10:r St.- y-

'en: and te th: Superint:nd:nt f th: Off:it: ".:vi:u :nd L./

- __. .. . . . . +4...

_ i_ n. u._ , + < m, _ + 4. u. e.m_ . ...

6) Review of facility operations to detect potential safety-hazards. 1 i

7) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review and Investigative Function. j N

eqf, I 8) Review of the Station Security Plan and shall submit A d of([o -

gp \, ' recommended changes to the Ace 4=+ea+ V4-= D-^ 4d- + -'

M lcQueb M N'ty h y o n s

C:n:r:1 "an ; r u u:!e:r St:ti:::. //,d'fjfd4 d/

4 g ggs j jyu 9) Review of the Emergency Plan station implementing' procedures and :h:11 :2.it Ad%.W. m a norde m

a. n..s...., ut . e...<a. . . ecommended, changes;4e ,...

a e..... u......_u...

w MA sp u t % 4 - iG+f['"' ' ~ ~ '"' '"' - "' "'"~ " "'

f

(\ 4. 4 4. 2. c (d. 3 10) gayjew of riportable' events and actions taken to prevent recurrence.

11) Review of every unplanned onsite release of radioactive material to the environs _ including the preparation and -

forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recur-

";:1:;:r St:ti:n:rence:nd te the t th; ^':!:+:nt Vic: " ::id:nt :nd Sup;rint:nd:nt f thC:n:r:1 M:n:;;r- d Off:it:

. ,1

- P.:v der and Investigative r"nctim #

12) Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems,

b. Authority L The Technical Staff Supervisor is responsible to the Station l Manager and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases f j of plant maintenance, operation, and administrative procedures relating to facility operations and shall have the authority to I request the action necessary to ensure compliance with rules, l regulations, and procedures when in his opinion such action is l necessary. The Station Manager shall follow such recommendations f j

l. of" select a course of action that is more conservative regarding safe operation of the facility. All such disagreements shall gf fpgg } be reported immediately to the A.::ictant "!:e nr ::id:nt and

=

l VQ. E OP80*W^ # 'm C:ncr:1 M:n:;;r-M; 10:r St:ti::: and the Superintendent of the # A Offsite Review and Investigative Function.

LA SALLE - UNIT 2 6-9 Amendment ho. [

1 1

__ _ ___ _ _ _ - - _ - _ _ - _ _ _ . _ _ _- _ - - - - - - - - - - - - - ]

ADMINISTRATION CONTROLS O Onsite Review and Investigative Function (Continued)

c. Records fP P "I ad * #' h

' 0** M

1) Reports, reviews, investigations, and recommendations shall be documented with copies to the M :ict:nt " ice I V5 flesidM6, j

/

. . - ._... ...d-GeneraH4anager-hc4 ear St;tiens, the l swe opu.6dr Superintendent of the Offsite Review and Investigative v

! Function, the Station Manager and the Manager of Quality

! Assurance.

2) Copies of all records and documentation shall be kept on file at the station.

d. Procedures Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative Function.

These procedures shall include the following: ;

1) Content and method of submission and presentation to the Station Manager, Asistent " ice Pres-ident and Cencr:1 -p N -Manageeduchar-Stat 4 ens, and the Superintendent of the Offsite Review and Investigative Function.

2) Use of committees. ,

3) Review and approval.

4) Detailed listing of items to be reviewed.

O s) erecedures for eomie4stretiee of 18e geel4ty contro, activities..

6) Assignment of responsibilities.

e. Personnel ,

1) The personnel performing the Onsite Review and Investiga-tive Function, in addition to the Station Manager, shall y consist of persons having expertise in:

a) nuclear power plant technology, b) reactor operations, c) reactor engineering, d) radiological safety and chemist, e) Instrumentation and control, and f) mechanical and electric systems.

2) Personnel performing the Onsite Review and Investigative Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.

H. Fire Protection Program An independent fire protection and loss prevention program inspection and ,J#

audit shall be performed at least once per 12 months utilizing either qualified of_fsite licensee personnel or an outside fire protection firm.

An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

O LA SALLE - UNIT 2 6-10 Amendment No.

e ,,-

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""E s LA SALLE - UNIT 2 6-11 Amendment No. 2 s

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LA SALLE - UNIT 2 6-12 - X Amendment N

-j ~'} -

Figure 6.1-3 MINIMUM SHIFT CREW COMPOSITION WITH UNIT 1 IN CONDITION 1, 2, OR 3 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITIONS 1, 2 and 3 CCNDITIONS 4 and 5 a ya SE l a

SF l None D

R0 2 1 b y A0 2 a

SCRE l None or, whenever a SCRE (SR0/STA) is not included in the shift crew composition, the minimum shift crew composition shall be as follows:

WITH UNIT 1 IN CONDITION 1, 2, OR 3 Q POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITIONS 1, 2 and 3 CONDITIONS 4 and 5 SE l a ya a

SF l None !

b y R0 2 b

A0 2 1 a

STA l None WITH UNIT 1 IN CONDITION 4 OR S OR DEFUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITIONS 1, 2 and 3 CONDITIONS 4 and 5 a a SE l l SF 1 None R0 2 1 b

A0 2 2

( STA 1 None LA SALLE - UNIT 2 6-13

l 9

.j

/ jy i Al Figure 6.1-3 (Continued)

MINIMUM SHIFT CREW COMPOSITION NOTES 'l a/ Individual may' fill the same position on Unit 1.

W0ne of the.two required' individuals may fill the same. position on Unit 1.

SE - Shift . Supervisor (Shift Engineer) with a Senior Reactor Operators License on Unit 2.

SF - Shift Foreman with a Senior Reactor Operators License on Unit 2.

RO .' -Individual with a Reactor Operators License on Unit 2. .l AO - Auxiliary Operator.

~SCRE - Station Control Room Engineer with a Senior Reactor Operators License.

Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Figure 6.1-3 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements'of Figure 6.1-3. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

While the unit is in OPERATIONAL CONDITION 1, 2, or 3, an individual with a valid SR0 license shall be designated to assume the Control Room direction function. While the unit is in OPERATIONAL CONDITION 4 or 5, an individual with a valid SR0 or R0 license shall be designated to assume the Control Room direction function.

l l

O LA SALLE - UNIT 2 6-14

. - _ - - _ - - . - _= _ - _ _ _ _ _ _ _ . -_

a s '

. ADMINISTRATION CONTROLS 6.1.1 HIGH RADIATION AREAS 6.11.1- Pursuant to Paragraph 20.203(c)(5) of 10 CFR 20, in lieu of the "c'on-trol device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, f.

each high radiation area in which the intensity of radiation is greater than 100 mrem /hr* but less than 1000 mrem /hr* shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by p.

requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures, 4.e., e Ded/ N = +echnic4"n , or personnel con-tinuously escorted by such individuals, may be exempt from the RWP issuance requirement during the performance of their assigned duties.in high radiation /

areas in which the intensity of radiation is greater than 100 mrem /hr* but less than 1000 mrem /hr*, provided they are otherwise following plant radiation pro-tection procedures for entry into such high radiation areas. 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 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 knowledgeable of them,

c. A health physics qualified individual, i.e., qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physicist in the Radiation Work Permit (RWP). L' 6.1.1. 2 In addition to the requirements of 6.1.1.1, above, for areas accessible >

to personnel with radiation levels such that a major portion of the body could !!

receive in one hour a dose greater than 1000 mrem *, the computer shall be programmed to permit entry through locked doors for any individual requiring [i access to any such High-High Radiation Areas for the time that access is required.

l 6.1.1. 3 Keys to manually open computer controlled High Radiation Area doors '

and High-High Radiation Area doors shall be maintained under the Administra-tion control of the Shift Supervisor on duty and/or the Health Physicist.

6.1.1.4 High-High Radiation areas, as defined in 6.1.1.2 above, not equipped with the computerized card readers shall be maintained in accordance with g

10 CFR 20.203 c.2 (iii), locked except during periods when access to the area is required with positive control over each individual entry, or 10 CFR 20.203.c.4.

In the case of a High Radiation Area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted. 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 area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a

Measurement made at 18" from source of radioactivity.

LA SALLE - UNIT 2 6-15 Amendment No.

L M. .

i

'e a .

ADMINISTRATION CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) l B. Radiation control procedures shall be maintained, made available to all station personnel, and adhered to. These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. This radiation protection program shall be organized to meet the requirements of 10 CFR 20. Qg C. 1.

ProceduresforitemsidentifiedinSpecification6.2.Aandanychanges'k to such procedures shall be reviewed and approved by the Operating Engineer and the Technical Staff Supervisor in the areas of operation, I fuel handling, or instrument maintenance, and by the* Assistant Super- p intendent M:inten:n : and Technical Staff Supervisor in the areas of /

plant maintenance and plant inspection. Procedures for items identi-fied in Specification 6.2.8 and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor and the

//ea#4 Pqs,e,s Atadiation Chemictry Supervisor. At least one person approving eacb. .['1l of the above procedures shall hold a valid senior operator's license.

In addition, these procedures and changes thereto, must have authori-zation by the Station Manager before being implemented. f.

. 2. Work and instruction type procedures which implement approved main-4 y, nonce 7 tenance or modification procedures shall be approved and authorized by thetAssistant Superintendent 4:inten:nce where the written author- A ity has been provided by the Station Manager. The "MainterMace/

Modification Procedure" utilized for safety-related work shall be so approved only if procedures referenced in the " Maintenance /

Modification Procedure" have been approved as required by 6.2.A.

Procedures which do not fall within the requirements of 6.2. A or 6.2.8 may be approved by the Department Heads.

D. Temporary changes to procedures 6.2. A and 6.2.B above may lie made provided:

1. The intent of the original procedure is not altered.

2. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's Licese on the unit affected.

3. The change is documented, reviewed by the Onsite Review and Investigative Function and approved by the Station Manager within 14 days of implementation.

g E. Drills of the emergency procedures described in Specification 6.2. A.4 shall be conducted at frequencies as specified in the Generating Stations Emergency Plan (GSEP). These drills will be planned so that during the course of the year, communication links are tested and outside agencies i are contacted.

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l LA SALLE - UNIT 2 6-17 Amendment No. 29 !

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ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued)

F. The following progrcms shall be established, implemented, an maintained:

f 1.' Primary Coolant Sources Outside Primary Containment

.i program.to reduce leakage from those portions of systems outside ,

primary containment that' could contain highly radioactive fluids !

during a serious transient or accident to as low as practical levels.

The systems-include LPCS, HPCS, RHR/LPCI, RCIC, hydrogen recombiner, process sampling, containment monitoring, and standby gas treatment systems. The program shall include the following:

a. Preventive maintenance and periodic visual inspection require- l ments, and

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

2. In-Plant Radiation Monitoring A program which will ensure the capabilitu to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

a. Training of personnel,

b. Procedures for monitoring, and

c. Provisions for maintenance of sampling and analysis equipment.

3. Post-accident Sampling N

A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulate in plant gaseous ef fluents, and containment atmosphere samples under accident conditions. The program shall include the following:

a. Training of personnel,

b. Procedures for sampling and analysis,

c. Provisions for maintenance of sampling and analysis equipment.

6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:

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a. The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed pursuant to Specifica-ti on 6.1. G. 2..a454.-

. C id. 1 LA SALLE - UNIT 2 6-18 AmendmentNo.[

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ADMINISTRATION CONTROLS 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED b b3 btdeOperwhan.s If a safety limit is exceeded, the reactor shall be shut down immediately pursuant to Specification 2.1.1, 2.1.2 and 2.1.3, and critical reactor operation shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to the Ass 4+ tant- Vice Pre:ident-end Cener:1 Manage /,

Lciear Stati:n: or his designated alternate. The incident shall be reviewed f pursuant to Specifications 6.1.G.I.a and-6.I G.2.0-and a separate Licensee Event Report for each occurrence shall be prepared in accordance with Section 50.73 to 10 CFR Part 50. The NRC Operations Cente shall be notified by telephone g as soon as possible and in all cases within o e hour. The A ufttent4 ice Irv sident :nd Central M:n ger-Nucle:r St:ti:n: a theManagerefficclearSafe}y c

1 shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . fd pg.ge gje ms rm4p&ndon, 6.5 PLANT OPERATING RECORDS [ 4, /. 6, 2. o ] l A. Records and/or logs relative to the following items shall be kept in a menner convenient for review and shall be retained for at least 5 years:

1. Records of normal plant operation, including power levels and periods -

of operation at each power level;

2. Records of principal maintenance and activities, including inspection and repair, regard.in.g. principal items of equipment pertaining to nuclear safety;

3. Records and reports of reportable events;

4. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met. All equipment failing to meet surveil-lance requirements and the corrective action taken shall be recorded;

5. Records of changes to operating procedures;

6. Shift engineers' logs; and

7. Byproduct material inventory records and source leak test results.

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LA SALLE - UNIT 2 6-19 AmendmentNo.2k

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g" ADMINI.5TRATIVE CONTROLS l

.. . . . - Semiannual Radioactive Effluent Release Report (Continued)

The' radioactive ' effluent release report shall include th following 3 L

information for each type of solid waste shipped offsit during the i report period: k

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined.by measurement. or e' timate),

d. Type of waste (e.g. , spent resin, compacted ' dry waste, evaporator bottoms),

e. Type of container (e.g. , LSA, Type A, Type B, Large Quantity),

and

f. Solidification agent (e.g. , cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned -

releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

5. Monthly Operating Report Routine reports of operating statistics and shutdown 4xperience, including documentation of all challenges to safety / relief valves,

/, gmd, shall be submitted on a monthly basis to the Director, Office of "saegr rat Irfer-etier and Dregrr Ocr,trel, US Nuclear Regulatory f ;

h Commission, Washington, DC 20555, with a copy of the appropriate staA*n Pl"G~I Regional Office, to arrive no later than the 15th of each month i

, following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in,which the change (s) was made effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by Onsite Review and Investigative Function.

B. Deleted.

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LA SALLE - UNIT 2 6-24 AmendmentNo[

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,' ATIACIMENT_B

[- . .

DETAlLEQ_RESEEIPTION AND_ SUM?iAEX I

l The proposed amendment requests several changes to the Administrative Controls Section 6.0 of the Technical Specifications which includes (1)

Removal of Organizational Figures 6.1-1 and 6.1-2, (2) a position change from Radiation Chemistry Technician to Radiation Protection Technician, (3) several position title changes due to reorganization, (4) a clarification to the distribution requirement for Onsite Reviews, and (5) typographical or editorial changes. Following is a description of each of the changes.

1) In accordance with Generic Letter 88-06, we propose replacing the Organizational Figures 6.1-1 and 6.1-2 in Technical Specifications with more general organizational requirements. These general requirements capture the essence of those organizational features depicted on the figures that are necessary for ensuring safe operation.

The proposed revision to the Technical Specifications will require that lines of authority, responsibility and communication be established and defined for the highest management levels through intermediate levels and including all operating organization positions. These relationships shall be documented at.d updated, ac appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personne] positione, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Relationships.

The Technical Specifications are not specifically required to contain organizational figures by 10 CFR 50.36. Organizational figures in themselves do not have a significant safety relevance. However, specific operational requirements that beer more directly on safety matters of concern, than organizational figures, are required elsewhere in the Technical Specifications (TS). For example, the organizational element responsible for the control room command function is identified in TS ;

6.1.D, and the requirements for minimum staffing under various operating conditions is identified in Table 6.1-3. The organizational mana'gement functions for review investigations and audits, and onsite and offsite review and investigative groups, and shift technical advisors are also specified in other TS.

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The important features identified on the organizational figures, but not currently included in the Technical Specifications as identified by Generic Letter 88-06, have been proposed to be added to TS 6.1.A. The addition of TS 6.1.C only specifies the Assistant Superintendent Operating since the other positions required to hold a license are discussed on ,

Table 6.1-3. The organizational figures in the Cuality Assurance Manual or Management Plan are of a level of detail consistent with tnat shown on the organizational figures in TS.

The proposed change will permit changes to the onsite and offsite organizational structures to be implemented without first obtaining NRC approval through issuance of a license snendment to update the TS. We believe changes to these figures have resulted in processing unnecessary amendments by both Commonwealth Edison Company and the NRC and, therefore, deletion will eliminate needless expenditure of resources for both organizations without affecting safe operation of the plant.

2) This change involves revising the position title of " Radiation Chemistry Technicien" to " Radiation Protection Technician". A reorganization is in progress which will result in separate positions for a Radiation Protection Technician and a Chemistry Technician in lieu of a single Radiation Chemistry Technician. The individual fulfilling the Radiation Protection Technician position would be qualified in radiation protection procedures. NUREG-0123 " Standard Technical Specifications for General Electric Boiling Water Reactors (BWR/5)", Revision 3, requires a Health Physics Technician to be onsite when fuel is in the reactor. The Radiation Protection Technician will satisfy the requirements for a Health Physics Technician specified in the Standard Technical Specification.

Therefore, this change is to address a position title change.

Also, the reference to Rad / Chem Technician was deleted on page 6-15. This particular reference is unnecessary and its deletion will prevent the need to amend the Technical Specifications in the future for a position title change.

3) Several places in the Administrative Section 6.0 of TS, position title changes are required due to reorganization. The title revisions include changing " Assistant Vice President and General Manager - Nuclear Stations" to "Vice President BWR Operations", and "Vice President - Nuclear Operations" to " Senior Vice President - Nuclear Operations", and " Chairman and President" to " Chief Executive Officer" and the addition of the

" Assistant Vice President Quality Prograns and Assessment". These changes are required to accurately reflect current organizational titles and j functional responsibilities. !

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4) Changes are proposed to TS 6.1.G.2 to clarify the distribution requirements of reports, reviews, investigations and recommendations that have been prepared and performed as part of the Onsite Review and Investigative Function. Currently TS 6.1.G.2a lists the responsibility of )

the Onsite Review and Investigative Function. Of the list of 12 items, several specify that recommendations should be submitted and reports forwarded to specific groups or individuals. However, TS 6.1.G.2c(1) also requires that reports, reviews, investigations and recommendations be documented and sent to several individuals. TS 6.1.G.2c(1) requires distribution to more people than TS 6.1.G.2a. Therefore, to remove any ambiguity, we propose deleting the distribution listings from TS 6.1.G.2a and therrby allowing TS 6.1.G.2c(1) to address the distribution requirements.

5) These changes are editorial or typographical in nature. They include a format correction on page 6-8, specification number corrections in specifications 6.3 and 6.4, and the mailing address correction for the Monthly Operating Report on page 6-24.

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EVALUATION OF SIGNIFICANT HAZARD COBEIDERATIONS I

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a Commonwealth Edison has evaluated this proposed snendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no )

significant hazards considerations if operation of the facility in accordance with the proposed snendment would not' l

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or i

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety.

The proposed Technical Specification amendment requests r?<eral changes. The first change involves the removal of organization 1 .1gures 6.1-1 and 6.1-2 and the revision of TS 6.1.A, 6.1.B, and 6.1.C in accordance with the guidance provided in Generic Letter 88-06. The second proposed f revision involves a position change from Radiation Chemistry Technician to l Radiation Protection Technician in TS 6.1.C and 6.1.1.1. The third proposed !

revision corrects several position titles that changed due to corporate reorganization. The fourth change clarifies the distribution requirements for onsite review documentation discussed in TS 6.2. The fifth and last corrections are editorial or typographical in nature.

None of the proposed changes are initiating events for an accident, therefore, the probability of an occurrence of an accident is not affected. 1 Even though the organizational figures are being removed, TS 6.1.A is being revised to require the organizational figures, functional descriptions of departmental responsibilities and relationships and job descriptions for key personnel positions be maintained for the Quality Assurance manual or the Management Plan for Operations, Sections 3 and 6. Therefore, safe plant operation is not affected and the consequence of any accidents presented in the UFSAR are not imparted by the first change. The revision proposed with change 2 does not alter the Station's adherence with regulatory guidance currently existing in NUREG-0123, 10 CFR 50.71 requirements for the UFSAR, ANSI Standards and Regulatory Guides. The remaining changes address organizational changes, clarification for documentation distribution, i

editorial and typographical changes. All these changes are administrative in l nature and the consequences of an accident as described in the UFSAR are not affected.

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The proposed changes do not revise any functional or design-parameters used at the Station. These changes do'not modify any equipment'or systems or cause the unit to be operated.in a different manner. .Therefore, the possibility of a new or different kind of accident is not created.

All the proposed changes are administrative or editorial and, as

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such, do not affect any margins of safety. The proposed organization changes do not affect safe operation of the plant. Creation of a Radiation Protection Technician position in lieu of.a hadiation Chemistry Technician adequately meets the requirements for IIealth" Physics coverage identified in NUREG 0123. -

Updating position titles, clarifying documentation distribution requirements, editorial and typographical changes, facilitate plant operations but do not affect safe operations.

For.the preceding. reasons, Commonwealth Edison believes all the changes proposed for the Technical Specification'anendment do not involve any significant hazards considerations.

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SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT l l Typically onsite and offsite organizations are defined by l organization charts includen under administrative control requirements of the Technical Specification (TS). This requires the processing of a license amen &nent to change an organization chart before implementing a change in i organizational structure. The guidance provided in Generic Letter 88-06 addresses mnendments that may be proposed for removing organization charts from the a&ninistrative control requirements of the TS.

The staff has previously determined that with appropriate changes to these administrative control requirements, the onsite and offsite organization charts may be removed. The changes involve the addition of general requirements that capture the essential aspects of the organizational structure that are defined by existing onsite and offsite organization charts. Enclosure 1 to Generic Letter 88-06 provides guidance for license amendment requests to remove organization charts from TS.

Enclosure 2 to Generic Letter 88-06 provides an example of this change that was made to the administrative control requirements of the existing Westinghouse Standard Technical Specifications (STS). The staff has found that this change will not reduce plant safety and it is generically applicable to all powe.; reactors.

The removal of organization charts is a line item improvement that was proposed on a lead-plant basis for the Shearon Harris plant and was endorsed by the Westinghouse Owners Group. This change was reviewed as part of the NRC's program for improvements in TS. The objectives of that program were established by the Commission's Interim Policy Statement on Technical Specification Improvements. The staff concludes that the removal of organization charts from TS will provide greater flexibility for licenses to implement changes in both the onsite and offsite organizational structure, -

consistent with Commission policy.

Commonwealth Edison has evaluated the proposed amendment against the criteria for and identification of licensing and regulatory actions requiring environment assessment in accordance with 10 CFR 51.21. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided for under 10 CFR 1.22(c)(9). This determination was based on the fact that changes are being proposed as an amendment to a license issued pursuant to 10 CFR 50. The changes are of an administrative nature only. The changes jnvolve no significant hazards, there are no significant changes in the types or amounts of off-site effluents, and there are no significant increases in individual or cumulative occupational exposure.

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