ML20245J730

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Corrected Amends 66 & 47 to Licenses NPF-11 & NPF-18, Respectively Re Administrative Controls for Offsite Dose Calculation Manual,Radwaste Treatment Sys,Audit Functions, & Min Shift Crew Composition
ML20245J730
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/26/1989
From:
NRC
To:
Shared Package
ML20245J677 List:
References
NUDOCS 8907030138
Download: ML20245J730 (26)
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Text

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. ENCLOSURE TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. NPF-11 l.

DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with

the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT XVIII XVIII XIXa XIXa 6-1 6-1 6-2 6-2

~6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10

--- 6-10a 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 6-17' 6-17 6-18 6 -18 . -

6-19 6-19 6-20 6-20 6-21 6-21 6-21a 6-21a 6-22 6-22 6-23 6-23 6-24 6-24 6-25 6-25 6-26 6-26 6-27 6-27 6-28 6-28 6-29 6-29 6-30 6-30 p$703013889c626ADOCK CDOoo373 PDC

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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 quality during facility operations shall be constituted and  !

have the responsibilities and authorities outlined below: 1

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- i sibility of.the Manager of QA/NS and shall be independent  !

of operations. '

s 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 p.eriodic audits of each nuclear station and corporate departments to determine that QA/NS policy is being carried out.

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 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 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 Manager, Vice President BWR Operations, Manager of QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment, and the Senior Vice President - Nuclear Operations. During periods when the Superintendent of Offsite Review and Investigative Function i:

unavailable, he shall designate.this responsibility to an established alternate, who satisfies the forme' training and i 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) 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 QA/NS.
2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in l

10 CFR 50.59.

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

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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 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.
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-tion Manager, Vice President BWR Operations, and AVP Quality Programs and Assessment.

ti. Station Audit Function The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of the BWR Operations. Such responsibility is' delegated to the Nuclear Quality Programs Manager.

The Nuclear Quality Programs Manager, or designated Corporate Staff or Supervisor approved by the AVP 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 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.

l

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 l at least once per 6 months. .
l. 4) Audit of the performance of activities required by the l Quality Assurance Program to meet the Criteria of  ;

l Appendix "B" 10 CFR 50.

LA SALLE UNIT 1 6-5 Amendment No. 66 L________-____________

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ADMINISTRATIVE CONTROLS-

"' 2 Station Audit Function'(Continued)

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 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, AVP-Quality Programs and Assessment, the Senior Vice President-Nuclear Operations, and the Chief Operations Officer.

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.

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 Operation Officer.

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
2) Copies of documentation, reports, and correspondence shall i be kept on file at the station.
e. Procedures Written administrative procedures shall be prepared and maintained i 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.I.b. Those procedures shall cover the following:

LA SALLE UNIT 1 6-6 Amendment No. 66

ADMINISTRATIVE CONTROLS

.e.

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

f. Personnel
1) ~The persons, including consultants, performing the review-and investigative function, in addition to the Superin-tendent of the Offsite Review and Investigative Function shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a) nuclear pows.r plant-technology, b) reactor operations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safety, g) reactor safety analysis, h) instrumentation and control, i) metallurgy, and-j) any other appropriate disciplines required by unique characteristics of the facility.

2) Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as  ;

listed below for each discipline. 1 a) Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operation. l b) Reactor Operations )

Engineering graduate or equivalent with 5 years i experience in nuclear power plant operations.

c) -Utility Operations j 8

Engineering graduate or equivalent with at least 5 1 years of experience in utility operation and/or engineering.  ;

LA SALLE UNIT 1 6-7 Amendment No. 66 l

ADIMINSTRATIVE CONTROLS d) Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation.

e) Reactor Engineering Engineering graduate or equivalent. In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.

f) Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.

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 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 The Station Manager shall: (1) provide direction for the Review 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 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 with NRC requirements, and provide recommendations; and (6) sub-mit to the Offsite Review and Investigative Function for con-currence in a timely manner, those items described in Specifica-tion 6.1.G.I.a which have been approved by the Onsite Review and Investigative Function.

LA SALLE UNIT 1 6-8 Amendment No. 66 t

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ADMINISTRATIVE CONTROLS t

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 th'e Offsite Review and' Investigative' Function.

c. ' Records
1) Reports, reviews, investigations,'and recommendations o -prepared and performed for_ Specification 6.1.G.2a shall

. .be documented with copies to the.Vice President BWR.

Operations, the Superintendent of the 0ffsite. Review and Investigative Function, the Station Manager,'and the AVP.

L Quality 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 include the following:

1) '

Content'and method of submission and presentation to the Station Manager, Vice President EWR 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 6-10 Amendment No. 66

ADMINISTRATIVE CONTROLS H. Fire Protection Program 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.

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LA SALLE UNIT 1 6-10a Amendment No. 66

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Figure 6.1-3

' MINIMUM SHIFT CREW COMPOSITION WITH UNIT 2 IN_ CONDITION 1, 2, OR 3-POSITION- NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2:and 3 CONDITION 4 and 5 a

SE l ya a

SF l None-b R0 2 1 b

A0- 2 y 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 2 IN CONDITION 1, 2, OR.3 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2 and 3 CONDITION 4 and 5 a a

. SE l _. y a

SF l None b

R0 2 y b

A0 2 7 a

STA l None.

WITH UNIT 2 IN CONDITION 4 or 5 OR DEFUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITION 1, 2 and 3 CONDITION 4 and 5 a

SE l ya SF 1 None R0 2 1 b

A0 2 2 STA 1 None LA SALLE UNIT 1 13 Amendment No. 66

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, ADNINTSTRATIVECONTROLS

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6.1.1 HIGH RADIATION AREAS 6.111.1 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 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, 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 /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 j permitted to enter such areas shall be provided with or accompanied by one or I more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose in the area. i
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).

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 access to any such High-High Radiation Areas 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 within

" Measurement made at 18" from source of radioactivity.

LA SALLE UNIT 1 6-13 Amendment No. 66

i o . . y l

1 ADMINISTRATIVE CONTROLS PLANT OPERATING RECORDS (Continued)

B. Records and/or logs relative to the following items shall be recorded in I a manner convenient for review and shall be retained for the life of the plant:

1. Substitution or replacement of principal items'of equipment pertain-ing to nuclear safety;-
2. ' Changes made to_the plant as it is described in the SAR;
3. Records of new and' spent fuel inventory and assembly histories; {
4. Updated, corrected, and as-built drawings of the plant;
5. Records of plant radiation and contamination surveys;
6. Records of offsite environmental monitoring surveys;
7. Records of radiation. exposure for all plant personnel, including all contractors and visitors to the plant, in accordance with 10 CFR Part 20;
8. Records of radioactivity in liquid and gaseous wastes released to the environment;
9. . Records of transient or operational cycling for those components that have been designed to operate safety for a limited number of transient or operational cycles (identified in Table 5.7.1-1);
10. -Records of individual staff members indicating qualifications, experience, training, and retraining;
11. Inservice inspections of the reactor coolant system; I
12. Minutes of meetings and results of reviews and audits performed by the offsite and onsite review and audit functions;
13. Records of reactor tests and experiments; j 8
14. Records of Quality Assurance activities required by the QA Manual, '

except for those items specified in Section 6.5.A;

15. Records of reviews performed for changes made to procedures on i equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; and
16. Records of the service lives of all hydraulic and mechanical snubbers required by specification 3.7.9 including the date at which the service life commences and associated installation and maintenance records.
17. Records of analyses required by the radiological environmental l- monitoring program.

l LA SALLE UNIT 1 6-20 Amendment No. 66

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ADMINISTRATIVE CONTROLS C. ' Unique. Reporting Requirements
1. Special Reports shall;be submitted to the Director of the Office of Inspection and Enforcement (Region III) within the time period specified for each report.

6.7 PROCESS CONTROL' PROGRAM (PCP)*

6.7.1 The PCP shall be approved by the Commission prior to implementation.

6.7.2 Licensee initiated changes to.the PCP:

a. Shall be submitted to the Commission in the semi annual Radioactive '

Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;
2. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and
3. Documentation of the fact that the change has been reviewed and found acceptable'by the Onsite Review and Investigative Function.

1 . b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.

LA SALLE UNIT 1 6-28 Amendment No. 66

' - ADMINISTRATIVE CONTROLS

.4

6. 8 0FFSITE DOSE CALCULATION MANUAL (0DCM)*

6.8.1 The ODCM shall be approved by. the Commission prior 1.0 implementation.

6.8.2 Licensee initiated changes.to'the ODCM:

a. Shall be submitted to the Commission within 90 days of the date the-change (s) was made effective. This submittal shall contain:
1. Sufficiently detailed information to totally. support the rationale for the. change without benefit of additional or supplemental information.- Information suomitted should consist

[

of.a package of those pages of the ODCM'to be changed with each i page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying-the change (s);

2. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and
3. Documentation of the fact that the' change has been reviewed and found acceptable by the Onsite Review and Investigative Function.
b. Shall become effective upon review and acceptance by the Onsite Review .

and Investigative Function.

6.9 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATEMENT SYSTEMS-6.9.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

a. Shall be reported to the Commission in the Monthly Operating Report for the period'in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain:
1. A summary of the evaluation that led to the determination.that the change could be made in accordance with 10 CFR 50.59;
2. Sufficient detailed information to totally support the reason for the change without benefit or additional or supplemental information;
3. A detailed description of the equipment, components end processes involved and the interfaces with other plant systems; i

^The OFFSITE DOSE CALCULATION MANUAL (0DCM) is common to La Salle Unit 1 and La Salle Unit 2.

l LA SALLE UNIT 1 6-29 Amendment No. 66

m ADMINISTRATIVE CONTROLS' 4 .- An evaluation of the change which shows the predicted releases

.of! radioactive materials in liquid and. gaseous effluents _and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;-

5. An evaluation of the change which shows the expected maximum:

~ exposures to individual.in the unrestricted area and to the

.y general-population that' differ-from those previously_ estimated in-the license application ~and amendments <thereto;

6. A' comparison of the predicted-releases of radioactive materials, in liquid and gaseoas effluents.and in solid waste, to the

- actual releases for the period to when thel chariges are to-be made;

7. An estimate of.the exposure to plant operating personnel as a result of the change; and
8. Documentation of the fact that the change was reviewed and-found. acceptable by the Onsite Review and Investigative Function.
b. Shall become_ effective upon review and' acceptance by the Onsite Review and Investigative Function.

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LA SALLE UNIT 1 6-30 Amendment No. 66

i/ .

s 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 Handling who has no other concurrent responsibilities during this operation. l

4. A site Fire Brigade of at leas't 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 tha unit and any personnel required for other essential functions during a fire emergency.

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, l which may indicate areas for improving unit safety. The ONSG shall j be' composed of at least three, dedicated, full-time engineers of 1 multi-disciplines located on site and shall be augmented on a part- {

time basis by personnel from other parts of the Commonwealth Edison i

Company organization to provide expertise not represented in the  !

group. TheDNSGshallberesponsibleformaintaininggurveillance j of unit activities to provide independent verification that these '

activities are performed correuly and that human errors are reduced as much as practical. The 0NSG 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 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 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.

1 x

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 cbsence provided immediate action is taken to l fill the required positions. l 1

  1. Not responsible for sign-off feature.

LA SALLE - UNIT 2 6-2 Amendment No. 47 1

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ADMINISTRATION CONTROLS Administrative procedures shall be developed and implemented to limit

7.'
l. 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 <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
b. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
c. A break of.at least eight hours should be allowed b'etween 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.

.Any deviation from the above guidelines shall be authorized by the Production or Technical Superintendents for their individual departments, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the pro-

.cedures such that individual overtime shall be reviewed monthly by the Produc-tion or Technical Superintendents to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

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

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 Health Physics Supervisor shall meet the requirements of radiation pro-tection manager of Regulatory Guide 1.8, September 1975. The ANSI N18.1-1971 qualification requirements for Radiation Protection Technician may also be met by either of the following alternatives:

1. Individuals who have completed the Radiation Protection Technician training program and have accrued 1 year of working experience in the specialty, or '
2. Individuals who have completed the Radiation Protection Technician training program, but have not yet accrued 1 year of working experience ,

in the specialty, who are supervised by on-shift health physics super- '

vision 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 0NSG.

I LA SALLE - UNIT 2 6-3 Amendment No. 47 1 I

_ _ _ _ _ _ ---- _ - - - - --- I

1 b ;,. - .

L ADMINISTRATION 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 quality during' facility' operations shall be-constituted and-hav'e 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 4 Safety (QA/NS). The Corporate Audit Function shallibe the respon-sibility of the Manager of QA/NS and shall be independent of operations.

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 policyLcommittee directed by the . J Manager of QA/NS. The Manager of QA/NS ha's 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.

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 appoint a senior participant to provide appropriate direction, (2) select each participant for this function,-(3) select a complement of more than one participant who collectively possess background and qualifications lin 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

'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 Operations, Manager of QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment, and the Senior Vice President - Nuclear Operations. During periods when the Superintendent of Offsite Review and Investigative 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:

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 i 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 QA/NS.

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

.LA SALLE - UNIT 2 6-4 Amendment No. 47

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Station A'dit-Function u (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). -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 i results thereof at least once per 12 months.
10) The 0FFSITE DOSE CALCULATION MANUAL and implementing 1 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 i 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, AVP Quality Programs and Assessment, the Senior Vice President-Nuclear Operations, and the Chief Operations Officer.

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.

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 l reported immediately to the Manager of QA/NS and the Chief Operating Officer.

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

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ADMINISTRATION CONTROLS

2) Copies of documentation, reports, and correspondence shall-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.I.b. Those procedures shall cover the following:
1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative 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.

f. ' Personnel
1) The persons, including consultants, performing the review-and investigative function, in addition to the Superintend-ent of the Offsite Review and Investigative Function shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a) nuclear power plant technology, b) reactor operations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safety, g) reactor safety analysis, h) instrumentation and control, i) metallurgy, and j) any other appropriate disciplines required by unique characteristics of the facility.

2) Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.

a) Nuclear Power Plant Technology, Engineering graduate or equivalent with 5 years  ;

experience in the nuclear power field design and/or '

operation.

LA SALLE - UNIT 2 6-7 Amendment No. 47

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' ADMINISTRATION CONTROLS' -i b) Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear _ power plant operations.

c) Utility Operations 1 Engineering graduate'or equivalent with at least 5 years of, experience in utility operation and/or

- engineering. q d) Power Plant Design li Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation, e) Reactor Engineering Engineering graduate or equivalent. In addition, at.

least 5 years of experience in nuclear plant engineeH ng, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.

f) Radiological Safety Engineering graduate or equivalent with at least' 5 years of experience in radiation control and safety.

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 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 The Station Manager shall: (1) provide direction for the Review 1 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 L one participant who collectively possess background and qualifica-tions in the subject matter under review are selected to provide LA SALLE - UNIT 2 6-8 Amendment No. 47

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. t u 4 ADMINISTRATION CONTROLS

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, and quality control phases of plant maintenan'e, c operation, and administrative procedures 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. 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, the Superintendent of the Offsite Review and Investigative 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, 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 i 1) The personnel performing the Onsite Review and Investiga-tive Function, in addition to the Station Manager, shall consist of persons having expertise in:
p. a) nuclear power plant technology, b) reactor operations, I

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 L

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2) Personnel performing the Onsite Review and Investigative Function shall meet minimum acceptable levels as described i in ANSI N18.1-1971, Sections 4.2 and 4.4. l H. Fire Protection Program 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 1 be performed by a qualified outside fire consultant at least once per 36 months. j

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l LA SALLE - UNIT 2 6-10a Amendment No.47 j

23 -

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 CONDITIONS 4 and 5 a

SE- l ya a

SF l None b

R0 2 y b

.A0 2 y 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 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION CONDITIONS 1, 2 and 3 CONDITIONS 4 and 5 a

SE l ya a

SF l None b

R0 2 y b

A0 2 y a

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

ya SE l SF 1 None R0 2 1 A0 D 2 2 STA 1 None 1

LA SALLE - UNIT 2 6-13 Amendment No. 47 l  !

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ADMINISTRATIONICONTROLS 6.4 ACTION TO BE ls lN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately pursuant to Specification 2.1.1, , 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 Vice President BWR Operations or his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.I.a-and~6.1.G.2.a 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 Center shall'be notified by telephone as soon.as possible and in all cases within one hour. 'The Vice Presicant BWR Operations and the Manager of Off.-site' Review and Investigative Function shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.5 PLANT OPERATING RECORDS A. . Records and/or logs relative ~to~ the following items shall be kept in a manner 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, regarding 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 y
7. Byproduct material inventory recores and source leak test results.

I LA SALLE - UNIT 2 6-19 Amendment No. 47

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ADMINISTRATION CONTROLS C. Unique Reporting Requirements

1. Special Reports shall be submitted to the Director of.the Office of Inspection and Enforcement (Region III) within the time period specified for each report.

6.7 PROCESS CONTROL PROGRAM (PCP)*

6.7.1 The PCP shall be approved by the Commission prior.to implementation.

6.7.2 Licensee-initiated changes to the PCP:

a. Shall be submitted to the Commission in the semiannual Radioactive Effluent Release Report for the period in which the' change (s) was made. This submittal shall contain:
1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;
2. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and
3. Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and Investigative Function.
b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.

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l ^The Process Control Program (PCP) is common to La Salle Unit 1 and La Salle ~

Unit 2.

LA SALLE - UNIT 2 6-28 Amendment No. 47 ,

Q _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - - - - - - - - -

June 26,1989 D eket Nos. 50-373 DISTRIBUTION and 50-374 Docket file TMeek (8)-

NRC & Local PDRs WJones PDIII-2 r/f EButcher

-Mr. Thomas J. Kovach MVirgilio ACRS(10)

Nuclear Licensing Manager LLuther GPA/PA Commonwealth Edison Company PShemanski ARM /LFMB Post Office Box 767 OGC Plant file Chicago, Illinois 60690 DHagan EJordan

Dear Mr. Kovach:

BGrimes

SUBJECT:

CORRECTION TO AMENDMENT NOS. 66 AND 47 - LASALLE COUNTY STATION Amendment No. 66 to Facility Operating License No. NPF-11 for LaSalle County Station Unit I and Amendment No. 47 to Facility Operating License No.

NPF-18 for LaSalle County Station Unit 2 were issued April 27, 1989. Various pages of these amendments had typographical and/or editorial errors. Enclosed l-I are corrected copies of there pages to be incorporated into the LaSalle Units 1 and 2 Technical Specifications (TS).

Sincerely, 04 C EM Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects

Enclosure:

As stated ]

cc w/ enclosure:

See next page l

p. r. f. r.

PDIII-2:PM PDIII-2:Lfs PDIII-2:(A)PD PShemanski:dmj LLuthery PShemanski 6/2.{,/89 6/ M /89 6/2(,/89 l

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