ML20066G084

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Proposed Tech Spec Section 6.0 Re Station Control Room Engineer & Offsite Review & Investigative Function
ML20066G084
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/18/1991
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20066G076 List:
References
NUDOCS 9101240359
Download: ML20066G084 (16)
v • d • e


Text

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ATTACHMENLB PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES NPF 18 AND NPF 11 REVISED PAGES i

.URLLL(NPF 11) UNIT 2_{NPF 18) 62 62 6 2a* 6 2a*

64 64 65 65 60 66 69 69 6 10 6 10

  • This is a new page added due to the Tech Spec Change Request

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$bg12gggg{gggggg73 p PDR ZNLD654/12

AM':NISTRATIVE CONTROLS

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 assume the control room direction responsibility shall be in the Control Room.
2. A radiation protection technician
  • shall be on site when fuel is in the reactor.
3. ' All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handlin during this operation. g who has no other concurrent responsibilities 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.

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 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.

TheONSGshallberesponsibleformaintaininggurveillance 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 safet to the Safety Assessment Manager and the Station Manager. _ nay segg

6. The Station Control Room Engineer (SCREj ,h rv::  :: the !e d ::ntre r DW NG % E5K c:c; CR0 cr%g nn = 1 0;:r: tion:-2nd fas the Shift Technical Advisor (STA) during abnormal o ,

conctTio45 ghg -: vent of em :! cper:perating and accident conditions. In er ting-cr-ascident-cenditten:, the SCRE will -

bcRE og oTER el'an"4 5 'f: job as centrel re : SPO to th: Chift Per:::n :nd ut'l -

=r: th:

od NTY STA S'e Of ST^ . dea hejshall provide technical support to tne Shift Supervisor in tne areas of thermal hydraulics, reactor i engineering the unit. and plant analysis with regard to the safe operation of The radiation protection 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 accommodate unexpected absence provided immediate action is taken to fill the required positions.

  1. N ot responsible for sign off feature.

LA SALLE - UNIT 1 6-2 Amendment No. 66

l

,

  • ADMINISTRATIVE CONTROLS '

F.

Retraining shall be conducted at intervals not exceeding 2 years.

G. {

The Review and Investigative Function and the Audit Function of activities affecting qua'lity during facility operations shall be constituted and 1' have the responsibilities and authorities outlined below:

1.

The Superintendent of the Offsite Review and Investigative Function shall be appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS). The Corporate Audit Function shall be the respon-sibility of the Manager of QA/NS and shall be independent of operations. {

1 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 i

promulgated through a central policy committee directed by the- t manager of QA/NS. The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and carried out,departments to determine that QA/NS policy is being corporate

a. Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Func-tion shall: (1) provide directions for the review and investi-gative function and ap appro tion,priate direction, point (2) select a senior each participant participant for this func-to prov (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 review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of non-compliance with NRC requirements to the Station Mana Vice President BWR Operations, Manager of QA/NS, " '"-"ger""

Gumt. "r

" Vice President - Nuclear Operations.c't During(f"") Quality periods when Programs the and MA#AGER Superintendent of Offsite Review and Investigative Function is unavailable, he shall designate this responsibility to an j established alternate, who satisfies the formal training and experience for the Superintendent of the Offsite Review and Investigate Function. The responsibilities of the personnel performing this function are stated below. The Offsite Review and Investigative Function shall review: ,

1) The safety evaluations for (1) chan es to procedures,  !

equipment, or systems as described n the safety analysis I report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such action! did l not constitute an unreviewed safety question. Proposed i l

changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS.

(

2) Proposed changes to procedures, equipment or systems which )

j involve an unreviewed safety question as defined in 10 CFR 50.59. l LA SALLE - UNIT 1 6-4 Amendment No. 66-I

ADMINISTRATIVE CONTROLS

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.
5) Noncompliance with NRC requirements, or of internal procedures, or instructions having nuclear safety significance.
6) Significant operating abnormalities or deviation from normal ano expected performance of plant equipment that ,

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

7) All REPORTABLE EVENTS.
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, Sta-CGENEMAL MAWAGa4Quality tion Manager, Vice President BWR Operations, and MP .  ;

Programs and Assessment,

b. Station Audit Function The Station Audit function shall be the responsibility of the M 4 Quality Programs and Assessment independent of the BWR Operations. Such responsibility is delegated to the Nuclear Oj!ality Programs Manager.

The Nuclear Quality Programs Manager,l or designated Corporate Staff or Supervisor approved by the M 9 Quality Programs and Assessment, shall approve the audit agenda and checklists, the findings and the report of each' audit. Audits shall be per-formed in accordance with the Company Quality Assurance Program and Procedures. Audits shall be performed 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 andl 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 facility equipment, structures, sys-tems, or methods of operation that affect nuclear safety at least once per 6 months. -

4) Audit of the performance of activities required by the '

Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50.

LA SALLE UNIT 1 6-5 Amendment No. 66

, ADMINISTRATIVE CONTROLS

' Station Audit Function (Continued)

5) Audit of the Facility Emergency Plan and implementing procedures at least once per 12 nonths.
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 environmutal monitoring program and the results thereof at least once per 12 months.
10) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.
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 criteria of Regulatory Guide 4.15, December 1977, at least o".e per 12 months.

Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Manager, Manager of QA/NS, Vice President BWR Operations,.J.VJ Quality Operations, and the Chief Operations Officer,ProgramsandAs

c. Authority hNMh The Manager of QA/NS reports to the Chief Executive Officer.
  • The Manager of QA/NS has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.

TheM Quality Programs and Assessmentfreports to the Senior Vice President-Nuclear Operations. The W 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 immediatel Operation Officer, y to the Menager of QA/NS and the Chief

d. Records
1) Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1.G.1.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 mair.tained for the offsite reviews and investigative functions described in Specification 6.1.G.I.a. and for the audit functions described in Specification 6.1.G.1.b. Those procedures shall cover the following:

LA SA..E UNIT 1 6-6 Amendment No. 66

_ m '

, y OMIN!!TRATIVE CONTROLS OWteReviewandInvesticativeFunctjog(Continued)

The statedresponsibilities below: of the personnel performing this function are j

1) 4 Review of (1)' procedures required-by Specification 6.2 and changes thereto, (2) a11 programs required by-$pecifica-tion 6.2 and changes thereto, and (3) any_other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety, 2)

Review of all proposed test and experiments that affect nuclear safety, l

3)  !

Review of all_ proposed changes to the~ Technical-Speci-fications. I

4) .

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

5)

Investigation of all noncompliance with NRC requirements ,

and shall prepare and forward a report covering evalua-

  • tion and recommendations-to prevent recurrence; 6)

Review hazards. of facility operations to detect potential safety '

7)

Performance of special reviews and' investigations and Offsite Review and Investigative Function. reports thereon as r 8)

Review of the 56ation Socority Plan and shall submit

( recommended changes to the Director of Corporate Security

' h" MAN and theWP Quality Programs and Assessment in lieu of distribution in accordance with Specification 6.1.G,2c(1).

9)

Review of the Emergency Plan and station implementing pro-cedures and identification of recommended changes;

10) Review of re recurrence, portable events and actions taken to prevent.

11)

Review of every_ unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and rence; disposition of the corrective action to' prevent recur-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 Manager and shall make recommendations in a timely manner in all areas of review, investigation plant maintenance,. operatics a,nd administrative proceduresand quality c relating to facility operatwns and shall have the authority to request the at 'a necessary. to ensure compliance.with rules, regulations, and orocedures when in his opinion such action is.

LA SALLE UNIT'1 6-9 Amendment No.66 4

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^

, , ' ADMINISTRATIVE CONTROLS necessary. The Station Manager shall follow such recommendations or select a course of action that is note conservative regarding safe operation of the facility. All such disagreements shall be reported immediately to the Vice President BWR Operations and the Superintendent of the Offsite Review and Investigative Function.

c. Records
1) Reports, reviews, investigations, and recommendations prepared and performed for Specification 6.1.G 2a shall be documented with copies to the Vice President BWR Operations the Superintendent of the Offsite Review and InvestigatIveFunction,theStationManager,andthe**

GusuL MugQuality Programs and Assessment.

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 incluoe the following:

1) Content and method of submission and presentation to the Station Manager, Vice President BWR Operations, 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.
5) Procedures for administration of the quality control 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 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.

LA SALLE UNIT 1 6 Amendment No. 66

- _ _ _ . _ __ _ -_ . - - ~ . . ,

p .

Y ADMINISTRATION CONTROLS

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 assume the control room direction responsibility shall be in the Control Room.
2. A radiation protection technician
  • shall be on site when fuel is in the reactor.

3.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handlin during this operation. g who has no other concurrent responsibilities 4.

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

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 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.

TheONSGshallberesponsibleformaintaininggurveillance 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 Safety Assessment Manager and the Station Manager.

6. The Statiot, antrol Room En ,

ne 2 0 h ing ner.T.el ;;;r:gineer ti:n:

n +he 1eed (SCRE V:erve:nd Ys_ the

e. Shift Tech D4RIN0 % esc (STA) during abnormal operating and accident conditions. Ir the event
  1. ener"1 e l

' coHolii*N.8; fhe %i Jei ;;perat4ng er eccident cond!tiene, +ha V RE v4'i re14nqu4* L '

ntr0I "^" * +^ th0 tit Ie' ~ and !"I ;;;i i l sg og y c,g

! rm of STk. tr h:fshall provide technical support to the Shift l

%Y UA Supervisor in the areas of thermal hydraulics reactor engineering and plantanalysiswithregardtothesafeoperatIonoftheunit.

R The radiation protection technician and Fire Brigade composition may be itss than the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence provided immedlate action is taken to

(

fill the required positions. .,

  1. N ot responsible for sign-off feature.

LA SALLE - UNIT 2 6-2 Amendment No. 47 l

l

j . l l ,

[ , , hDMINISTRATIONCONTROLS F.

Retraining shall be conducted at intervals not exceeding 2 years.  ;

! G.

i The Review and Investigative Function and the Audit Function of activities  ;

affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below: (

J

1. The Superintendent of the Offsite Review and Investigative Function '

4 shall be appointed by the Manager of Quality Assurance / Nuclear Safet (QA/NS). The Corporate Audit Function shall be the respon-

! s sibil ty of the Manager of QA/NS and shall be independent of

[ operations. .

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

F and has the responsibility to set Corporate Policy-for both the

' areas of Quality Assurance and Nuclear Safety. Policy is promulgated throu Manager of QA/NS.gh a central policy committee directed by the

-The Manager of-QA/NS has the responsibility for j

the performance of periodic audits of-each nuclear station and corporate departments-to determine that QA/NS policy-is being -

i carried out. .

a.- Offsite Review and. Investigative Function

-The Superintendent of the Offsite Review and Investigative'func-tion ~shall: (1 gative function)and approvide directions for the review and'investi-

, appropriate direction, point (2) select a senior participant-to each participant provide for this function, (3) select a complement of more than one participant- ,

who collectively possess background.and qualifications in the '

sub ect matter under review to provide comprehensive interdis- a' cip inary review coverage under this function, 4) independently review and approve the findings-and recommendat ons-developed by) personnel performing the review and investigative function, (5 approve and report in a timely manner all findings of non-compliance with NRC requirements-to the Station Manager, Vice -

President BWR O ggg s - N %t '"?)perations,Quality Manager of QA/NS, -4.i...a 7...

Programs and Assessment..and the Senior-MMAMR Vice President - Nuclear Operations. Durin periods when the Superintendent of Offsite Review and Invest gative Function-is unavailable,.he shall designate this responsibility to an established alternate, who satisfies the formal training and~

experience for- the Superintendent of the Offsite Review and ^

, Investigate Function. The responsibilities of the personnel

-performing this function are stated below. . The Offsite Review and Investigative Function shall review: <

4 1)-

The safety evaluations for (1) changes to procedures,. 1 equipment, or,s report and (2) ystems tests or as described completed experiments in the safety analysis under the .

t provision of 10 CFR 50.59.to verify that such actions did not constitute an unreviewed safety question. Proposed' 4 l

changes to-the Quality Assurance Program description shall-be. reviewed and approved by the Manager of QA/NS.

2) Proposed changes to procedures,( equipment or systems which involve an unreviewed safety-question as defined in-  !

'10 CFR 50.59.- I LA SALLE - LINIT 2 6 Amendment No. 47 L

ua.. . ~. _ . . _ _ .--- _ _ ._ _ _ _ _ _ - . _ . . _ _.- _.__.a_-

l

~

Rt' N !TRA?!CG CON?ROLS

,. 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.
5) Noncompliance with NRC requirements, or of internal procedures, or instructions having nuclear safety significance.
6) Significant operating abnormalities or_ deviation from l

normal and expected performance of plant equipment "

affect nuclear safety as-referred to it by the On {

Review and Investigative Function. l

7) All REPORTABLE EVENTS. '
8) All recognized indications of an unanticipated defic un.s i

in some aspect of design or operation of. safety-related l 1

structures, systems, or components. '

9) - Review and report findings and recommendations regardt'-

all changes to the Genreating Stations Emergency Plan prior to implementation of such change.  ;

10) Review and report findings and recommendations re items referred by the Technical Staff Su Si tion Manager, Vice President BWR Operations, and the AVP perv b,

Quality programs and Assessment. -

j  ;

)

Station Audit Function The Station Audit Function sha11 be the responsibility of the GENEML -MF Quality Programs and Assessment independent of the BWR Operations.

4ggg Such responsibility is delegated to the Nuclear Quality Programs Manager.

V The Nuclear Quality-Programs Mana or designated Corporate Staff or Supervisor approved by the AYP Quality Programs and 4 Assessment, shall approve the audit agenda and checklists, the findings and the report of each audit. Audits shall be per-formed in accordance with the Company Quality Assurance Program '

and Procedures. Audits shall be performed to assure that safety or less related functions as designated are covered within a period of 2 years below. i 6

1) i 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 qualification of the station staff at least once per year.

3)

Audit of the results of actions taken to correct I deficiencies occurring in facility _ equipment, structures, i systems, or met hods of operation that affect nuclear safety at least ance per 6 months.

1 LA SALLE - UNIT 2 65 Amendment No. 47

I i

'ADMINISTRATION CONTROLS 1

1.

Station Audh Function (Continued)

4) Audit of the performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50,
5) i Audit of the Facility Emergency Plan and implementing J procedures at least once per 12 months. 4
6) Audit of the racility 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 procedures.
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 criteria of Regulatory Guide 4.15 December 1977, at least once per 12 months.

Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Manager, Manager of QA/NS, Vice President BWR Operations *tQuality Programs and Assessment, the Senior Vice President Nuclear Operations, and the Chief Operations Of ficer.

c. Authority The Manager of QA/NS reports to the Chief Executive Officer.

The Manager of QA/NS has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions..

gg The 4 Quality Programs and Assessment eports.to the Senior Vice President-Nuclear Operations. Thet and Assessment has the authority to recommen uality Programs unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions. All such disagreements shall be reported immediatel Operating Officer, y to the Manager of QA/NS and the Chief d.. Records

1) Reviews, audits, and recommendations shall be documented and distributed as-covered in 6.1.G 1.a and 6.1.G.1,b LA SALLE UNIT 2 6-6 Amendment No. 47

7_

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LOM!h!$iR M 10N CONTR0ts j

PsiteReviewandInvesticativeFunction(Continued) l comprehensive interdisciplinary review coverage under this function; (O independently review and approve the findings and recommendations t'eveloped by personnel performing the Review and Investfgative Function;  ;

(5) report all findings of noncompliance with NRC requirements and ,

provide recommendations; and (6) submit to the Offsite Review and l

Investigative Function for concurrence in a timely manner, those items described in Specification 6.1.G.I.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 thereto, (2) all programs required by Specifica-tion.6.2 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety,
2) Review of all proposed test and experiments that affect nuclear safety.
3) Review of all proposed changes to'the Technical Speci-fications.
4) Review of all proposed change:; or. modifications to plant systems or equipment that affect nuclear sefety.
5) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evalua-tion and recommendations'to prevent recurrence;
6) Review of facility operations to detect potential safety hazards.
7) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review and Investigative Function.
8) Review of the Station Security Plan and shall submit '

recommergfed changes to the Director of Corporate Security and the @ 8-Quality Programs and Assessment in lieu of g }/M AGE. distribution in accordance with Specification 6.1.G.2.c(1).

9)

Review of the Emergency Plan and station implementing procedures and identification of recommended changes;

10) Review of reportable 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 rence; disposition of the corrective action to prevent recur-

12) Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE 00SE CALCULATION MANUAL, and radwaste treatment systems.

LA SALLE - UNIT 2 6-9 Amendment No' 47 L

. . . _ . -s , _ , . _ . , , , . . . . _ _ . . . _ . ._

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y ,. - ..-.. . . . , . - - m. ..

a l

i ADMINISTRATION CONTROLS 4

b. Authority The Technical Staff Supervisor is responsible to the Station 4

Manager and shall make recommendations in a timely manner in l

all areas of review, investigation, and quality control phases i of plant maintenance, operation and administrative procedures l relating to facility operations,and shall have the authority to request the action necessary to ensure compliance with rules regulations,andprocedureswheninhisopinionsuchactionIs necessary. The Station Manager shall follow such recommendations '

or select a course of action that is more conservative regarding safe operation of the facility. All such disagreements shall be reported immediately to the Vice President BWR Operations and the Superintendent of the Offsite Review and Investigative Function,

c. Records
1) Reports, reviews, investigations, and recommendations prepared and performed for Specification 6.1.G.2a, shall be documented with copies to the Vice President BWR Operations, theSuperintendentoftheOffsiteReviewandInvestigative Function, the Station Manager and theMage Of ^a.itr h= 0-GrNRRAL. MANAotR Quuty ? goc, cams Mb A35E55MNT
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, Vice President BWR Operations 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.
5) Procedures for administration of the quality control 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 l 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. ,

LA SALLE - UNIT 2 6-10

, Amendment No. 47

- v---- p.%----- - - -,i w wm-rym -i

l

. 1 1

  • P ,

INSERT A j

1. Both channels of each tria system may be placed in an inoperable status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for requirec reactor building ventilation system corrective maintenance, filter changes, damper cycling and surveillance tests, other than Surveillance Requirement 4.6.5.1.c, without placing the trip system in the tripped condition..

J. Both channels of each trip system may be placed in an inoperable status for u a to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for performance of Survelilance Requirement 4.6.5.1.c without-p acing the trip system in the tripped condition.

INSERT B Both channels of each trip sys'em for the main steam tunnel ambient temperature and ventilation system d!tferential temperature ma:/ be placed in an inoperable status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for re-wred reactor building vonti ation system maintenance and testing and 12 ho44 foi the required secondar '

placin the tr p system in the tripped condition.y containment This will allow Leakthe for maintaining Rate test without '

reliabi ty of t e ventilation system and secondary contalnment.

ZNLD654/15 l

. p AIIACHMEHLG EVALUAIl010EElGNIElCANLHAZABRS_C. ONSIDE R ATION 2 The proposed Operating License / Technical Specification Amendment has been evalualed to determine whether or not there is a SiDnificant Hazards

! Consideration based on the questions provided by 10 CFR 50.92 requirements. In  ;

i addition, the evaluation was measured a limits, the limit!ng safety system and settings, gainst the limiting the criteria conditions used for operations. to establish s The results of the evaluation determined that the proposed amendment would not:

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

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 change does not result in a significant increano in the .

probability or consequences of accidents previously evaluated. The chan0es are administrative in nature, and as such are not considered in any FSAR Chalter 15 analysis. The changes do not effect any administrative-process which cou d impact the assumptions or results of the analyses.

The proposed change does not create the possibility for a new or different kind of accident from any accident previously eveluated. The proposed changes do not result in the introduction of any new or different equipment, and they w.ill not -

cause the operation of installed equipment in a new or different manner. The . -

changes will not result in the introduction of any r3ew procedure or process which could create a new or different kind of accident.

The proposed change does not involve a significant reduction in margin of safety. Because the changes are purely administrative in nature, no margin of safety is affected.

Conclusion Guidance has been provided in 51.44 FR 7744 for the application of .

standards to license change requests for determination of the existence of significant hazards considerations. This document provides examples of amendments which are and are not likely consideisd to involve significant hazards considerations.

This proposed amendment does not involve a significanf relaxation of the criteria used to establish safety limits, a significant rel6xation of the bases for the limiting safety system settinas or a s!gnificant relaxation of the bases for the limiting conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(s), the proposed change does t not constitute a significant hazards consideration.

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AIIACHMEtiI.R ENVlRONMENIALASSESSMENI_SIAIEMENIAP.ELICABILLI18EVIEW L Cornmonwealth Edison has evaluated the proposed amendment agalntt the criteria for the identification of Ilconsing and regulatory actions requirin0 environmental assessment in accordance with 10 CFR 51.21. It has been detennined that the proposed change meets the critena for a categorical exclusion as provided for under 10 CFR 51.22 (c)(10). This determination is based on the f act that this change is being proposed as an amendment to a license issued puntuant to -

10 CFR 50. This change is administrative in nature, involves no significant hazards considmation and results in no significant increase in indhtual or cumulative occupational radlation exposure.

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