Text

Amends 66 & 47 to Licenses NPF-11 & NPF-18,respectively, Changing Administrative Controls Section 6.0 to Include Removal of Organizational Figures
	ML20245H780
Person / Time
Site:	LaSalle
Issue date:	04/27/1989
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20245H784	List: ML20245H780; ML20245H787;
References
	NPF-11-A-066, NPF-18-A-047 NUDOCS 8905030530
	Download: ML20245H780 (73)
	v • d • e

{{#Wiki_filter:. N p Mc j,[( 'k UNITED STATES ') g NUCLEAR REGULATORY COMMISSION E j WASHINGTON, D. C. 20565 \\...../ COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendinent No. 66 License No. NPF-11 1. The Nuclear Regulatory Consission (the Commission or the NRC) has found that: A. T5 application for amendment iiled by the Commonwealth Edison Company 4 l'ne licensee), dated February 17, 1989 complies with the standards and t requirements of the Atomic Energy Act of 1954, as an,enced (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assbrance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted 1 in compliance with the Cor.misston's regulations set forth in 10 CFR 1 Chapter I; j 1 D. 1he issuance of this einenament will not be inimical to the common defense ano security or to the health and safety of the public; and i E. The issuance of this cmendment is in accordance with 10 CFR P6rt 51 of the Consission's regulations ana all applicable requirements have beer satisfied. 2. Accordingly, the license is amended by changes to the Technical Sptcifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendinent No.66, and the Environrnental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall l operate the facility in accordance with the Technical Specifications and l the Environmental Protection Plan. l 8905030530 890427 ADOCK0500g3 DR

] tt -i ' 3. This amendment is effective upon date of issuance. l FOR THE NUCLEAR REGULATORY COMMISS10tl Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects i d

Enclosure:

Changes to the Technical Specificat*ons Date of Issuance: April 27, 1989 i i I

4 .) ENCLOSURE TO LICENSE AMENDMENT N0. 66 FACILITY OPERATING LICENSE NO. NPF-11' q DOCKET N0. 60-373 Replace the following pages of the Appendix "A" Technical Specifications with. the enclosed pages.. The revised pages are' identified by anendment number and contain a vertical line indicating the area of change. REMOVE INSERT. XVIII XVIII XIXa XIXa 6-1 6-1 R 6-2 6-2 1 6-3 6-3 f 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 i 6-26 6-26 6-27 6-27 6-28 6-28 6-29 6-29 6-30

4 o INDEX ADMINI;TRATIVE CONTROLS SECTION PAGE 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND' AUDIT....................- '6-1 6.1.1 'High Radiation Areas........................... 6-15' 6.2 PLANT OPERATING PROCEDl'RES AND PR0 GRAMS............................ 6-16 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE IN PLANT 0PERATION..................................... '6-18 6.4 ACTION T0 BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED........ 6-19' 6.5 PLANT OPERATING REC 0RDS........................................... 6-19 6.6 REPORTING REQUIREMENTS............................................ 6-21 6.7 PROCESS CONTROL PR0 GRAM........................................... 6-28 6.8. OFFSITE DOSE CALCULATION MANUAL................................... 6-28 6.9 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS.............. 6-29 i j -i L I i i l LA SALLE - UNIT 1 XVIII Amendment No. 66

's \\ LIST OF FIGURES FIGURE PAGE i 3.1.5-1 S0DIUM PENTABORATE SOLUTION TEMPERATURE / j CONCENTRATION REQUIREMENTS........................ 3/4 1-21 l 1 3.1.5-2 S0DIUM PENTABORATE (Na 0 0 10 H 0) l 2 10 16 2 VOLUME / CONCENTRATION REQUIREMENTS................. 3/4 1-22 ] 3.2.1-1 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 l BP8CRB299L....................................... 3/4 2-2(a) 3.2.1-3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, FUEL TYPES BC300D AND BC320C.......... 3/4 2-2b 3.2.3-la MINIMUM CRITICAL POWER RATIO (MCPR) VERSUS l t AT RATED FLOW................................. 3/42-5 1 3.2.3-1b 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 K FACTOR........................................ 3/4 2-6 f 3.4.1.5-1 CORE THERMAL POWER (% OF RATED) VERSUS TOTAL CORE l FLOW (% OF RATED) 3/4 4-Sc l 3.4.6.1-1 MINIMUM REACTOR VESSEL METAL TEMPERATURE VS. REACTOR VESSEL PRESSURE.................... 3/4 4-19 l l 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST....... 3/4 7-33 l 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 B 3/4.6.2-1 SUPPRESSION P00L LEVEL SETPOINTS.................. B 3/4 6-3a 5.1.1-1 EXCLUSION AREA AND SITE BOUNDARY FOR GASE0US AND LIQUID EFFLUENTS............................. 5-2 5.1.2-1 LOW POPULATION ZONE.............................. 5-3 6.1-1 DELETED........................................ 6-11 6.1-2 DELETED........................................ 6-12 6.1-3 MINIMUM SHIFT CREW COMPOSITION........ 6-13 LA SALLE - UNIT 2 XiX Amendment No. 47 i

3 INDEX LIST OF FIGURES (Continued) FIGURE PAGE 6.1-1 DELETED................................................. 6-11 6.1-2 DELETED................................................. 6-12 6.1-3 MINIMUM SHIFT CREW COMPOSITION.......................... 6-13 l l l I 1 l l l l l l l l l l LA SALLE - UNIT 1 XIXa Amendment No. 66

1 3 l ~ f 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT 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 I 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 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 I 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 onsite manager; however, they shall have sufficient w organizational freedom to ensure their. independence from operating ? pressures. B. The Shift Supervisor shall be responsible for directing and commanding l -l the overall operation of the facility on his shift. The primary manage-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 Vice President BWR Operations 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. C. The' shift manning for'the station shall be as shown in Figure 6.1-3. The individual filling the position of Technical Staff Supervisor shall meet the minimum acceptable level for " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971. The individuals filling the positions of Production Superintendent and Technical Superintendent shall meet the minimum acceptable level for " Plant Manager" as described in Section 4.2.1 of_ ANSI N18.1-1971. LA SALLE - UNIT 1 6-1 Amendment No. 66

) r 1 ADMINISTRATIVE CONTROLS l 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 I assume the control room direction responsibility shall be in the Control Room. 1 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 Reactar Operator or Senior Reactor Operator. Limited to Fuel Handling who hts no other concurrent responsibilities during this operation. 4. A site Fire Brigade of at least 3 members shall be maintained onsite at all times *. The Fire Brigade shall not include the Shift Supervisor, the Station Control Room Engine;.c and the 2 other members of the mini-mum shift crew necessary for sa'e shutdown of.the 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, which may indicate areas for improving unit safety. The 0NSG shall 1 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 The 0NSG shall be responsible for maintaining surveillance group. 1 of unit activities to provide independent verification that these activities are performed correctly 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 SR0 during normal operations and as the Shift Technical Advisor 1 (STA) during abnormal operating and accident conditions. In the event of abnormal operating or accident conditions, the SCRE will I 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. l 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.

ot responsible for sign-off feature.

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

1 j .i i 5. I ADMINISTRATIVE CONTROLS 7. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; 1 e.g, senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel. Adequate shift coverage shall be maintained without routine heavy "i 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 hours straight, excluding shift turnover time, b. An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours 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. 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 4 procedures such that individual overtime shall be reviewed monthly by the Production 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 protec-tion manager of Regulatory Guide 1.8, September 1975. The ANSI N18.1-1971 qualification requirements for Radiation Protection Technician may also be l 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 experi-ence 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." l 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. LA SALLE - UNIT 1 6-3 Amendment'No. 66

~r ADMINISTRATIVE CONTROLS F. Retraining shall be conducted at intervals not exceeding 2 years. j 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. 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 Assurance and shall be independent of op3 rations. The Manager of QA/NS reports directly to the Chief Executive officer i 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 4 corporate departments to det' ermine that QA/NS policy is being carried out. y 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 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 l Investigate Function. The responsibilities of the personnel performing this function are stated below. The Offsite Review-and Investigative Function shall' review: l 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 A:surance Program description shall be reviewed and approved bj 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 1 6-4 Amendment No. 66.

s. -4 ADMINISTRATIVE CONTROLS j 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 l 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 1

all items referred by the Technical Staff Supervisor, Sta-tion Manager, Vice President'BWR Operations, and AVP Quality Programs and Assessment. b. Station Audit Function i The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of the BWR Operation. 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. 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. i j 4) Audit of the performance of activities required by the I Quality Assurance Program to meet the Criteria of ' Appendix "B" 10 CFR 50. LA SALLE UNIT 1 6-5 Amendment No. 66 - _ - - - --- - __ - - =

~ ADMINISTRATIVE CONTROLS Audit Function (Continued) I 5) Audit of the Facility Emergency Plan and implementing procedures at least once per 12 months. I 6) Audit of the Facility Security Plan and implementing procedures. 7) Audit onsite and offsite reviews. I 8) Audit the Facility Fire Protestion Program and implementing procedures. 9) The radiological environmental monitoring program and the results thereof at least once per 12 months.

10) The 0FFSITE POSE CALCULATION MANUAL and implementing procedures.

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

1

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

t 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 I;n the authority to recommend unit shutdown or request any oth. ution -nich 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 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: LA SALLE UNIT 1 6-6 Amendment No. 66

4 4

4 ADMINISTRATIVE CONTROLS Offsite Review and Investigative Function (Continued) 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. l 5) Method of-(1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations of reviews and investigations, (4) approving reports, and l (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 power plant technology, b) reactor operations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safety, i 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. l 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 experience in nuclear power plant operations. c) Utility Operations Engineering graduate or equivalent with at~least 5 years of experience in utility operation and/or engineering. LA SALLE UNIT 1 6-7 Amendment No. 66

ADIMINSTRATIVE CONTROLS Offsite Review and Investigative Function (Continued) 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 enginee_ ring 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) Reac'or Safety Analysis Engineering graduate or equivalent with at least I 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 I 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 s. hall: (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-l ticipant to provide appropriate directions; (2) approve partici-l 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 j i with NRC requirements, and provide recommendations; and (6) sub-l mit to the Offsite Review and Investigative Function for con-currence in a timely manner, those items described in Specifica-tion 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function. LA SALLE UNIT 1 6-8 Amendment'No. 66-1

ADMINISTRATIVE CONTROLS Onsite Review and Investigative Function (Continued) The responsibilities of the personnel performing this function are stated below: 4 1) Review of (1) procedures required by Specification 6.2 and { changes.thereto, (2) all programs required by Specifica-I 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 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 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 recommended changes to the Director of Corporate Security and the AVP 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 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 l

and disposition of the corrective action to prevent recur-rence;

12) Review of changes to the PROCESS CONTROL PROGRAM, 0FFSITE 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 of plant maintenance, 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 LA SALLE UNIT 1 6-9 Amendment No.66

.O ADMINISTRATIVE CONTROLS Onsite Review and Investigative Function (Continued) necessary. The Station Manager shall follow such recommendations or select a course of action that is more conservative regarding l safe operation of the facility. All such disagreements shall be reported immediately to the Vice President BWR.0perations and the l I 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 j be documented with copies to the Vice President BWR ,0perations the Superintendent of the Offsite Review and Investigative Function, the Station Manager, and the AVP Quality Programs and Assessment. 2) Copies of all records and documentation shall be kept on file at the station. d. Procedures 'f 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 Managar, 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,tems 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 j 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 Onsite Review and Investigative Function (Continued) 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. l 4 I I LA SALLE UNIT 1 6-10a Amendment No. 66

9 1 THIS PAGE INTENTIONALLY LEFT BLANK 1 i LA SALLE UNIT 1 6-11 Amendment No. 66

t THTS PAGE INTENTIONALLY LEFT BLANK I LA SALLE UNIT 1 6-12 Amendment No. 66

c Figure-6.1-3 MINIMUM SHIFT CREW COMPOSITION-I 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 i b R0 2 1 b A0 2 y a SCRE l None I or, whenever a.SCRE (SR0/STA) is not included in the shift crew j composition, the minimum shift crew composition shall be as i follows: I 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 4 b R0 2 y b A0 2 3 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 a SE l y SF 1 None R0 2 1 b A0 2 2 a STA l None .LA SALLE UNIT 1 6-13 Amendment No. 66

Figure 6.1-3 (Continued)' MINIMUM SHIFT CREW COMPOSITION NOTES a/ Individual may fill the same position on Unit 2. 5/ One of the two required individuals may fill the same position on Unit 2. 3E - Shift Supervisor (Shift Engineer) 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 exceed 2 hours 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. LA SALLE UNIT 1 6-14 Amendment No. 66 (.

1 1 ADMlNTSTRATIVE 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 l 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 j 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 thn 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 permitted to enter such areas shall be provided with or' accompanied by one or more of the following: A radiation monitoring device which continuously indicates the a. y' 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 I 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 topersonnelwithradiationlevelssuchthatamajorportionofthebodycould 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 6-15 Amendment No. 66

ADMINISTRATIVE CONTROLS HIGH RADIATION AREAS (Continued) l large areas, such as the containment, where no enclosure _ exists for purposes of locking, and no enclosure can be reasonably constructed around the indivi-dual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote, such as use of closed circuit TV cameras, continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area. I

6. 2 PLANT OPERATING PROCEDURES AND PROGRAMS A.

Detailed written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to: 1. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978. 2. Refueling operations. 3. Actions to be taken to correct specific and fo'eseen potential malfunctions of systems or components including responses to alarms, suspected primary system leaks, and abnormal reactivity changes. 4. Emergency conditions involving potential or actual release of radioactivity " Generating Stations Emergency Plan" and station emergency and abnormal procedures. 5. Instrumentation operation which could have an effect on the safety of the facility. 6. Preventive and corrective maintenance operations which could have an effect on the safety of the facility. 7. Surveillance and testing requirements. 8. Tests and experiments. 9. Procedure to ensure safe shutdown of the plant. 10. Station Security Plan and implementation procedures. 11. Fire Protection Program implementation. 12. Process Control Program implementation. 13. OFFSITE DOSE CALCULATION MANUAL implementation. 14. Company Quality Assurance Program and Procedures for effluent and environmental monitoring, using the guidance in. Regulatory Guide 4.15, December 1977. LA SALLE UNIT 1 6-16 Amendment No. 66

1. s ADMINISTRATIVE CONTROLS j i PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) 8. 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 j i requirements of 10 CFR 20. This radiation protection program shall be organized to meet the requirements of 10 CFR 20. j l C. 1. Procedures for. items identified in Specification 6.2.A and any changes to such procedures shall be reviewed and approved by the l Operating Engineer and the Technical Staff Supervisor in the areas of operation, fuel handling, or instrument maintenance, and by the Maintenance Assistant Superintendent and Technical Staff Supervisor in the areas of plant maintenance and plant inspection. Procedures l for items identified in Specification 6.2.B and any. changes to such I procedures shall be reviewed and approved by the Technical Staff Supervisor and the Health Physics Supervisor. At least one person I approving each of the above procedures shall hold a valid senior operator's license. In addition, these procedures and changes thereto, must have authorization by the Station Manager before being implemented. 2. Work and instruction type procedures which implement approved main-tenance or modification procedures shall be approved and authorized by the Maintenance Assistant Superintendent where the written authority hasbeenp'rovidedbytheStationManager. The " Maintenance / 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.B may be approved by the Department Heads. D. Temporary changes to procedures 6.2. A and 6.2.B above may be 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 License 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 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. LA SALLE UNIT 1 6-17 Amendment No. 66

l j j ADMINISTRATIVE CONTROLS l 9 PLANT OPERATING PROCEDURES AND PROGRAMS-(Continued) l F. The following programs shall be established, implemented, and maintained: 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 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: Preventive maintenance and periodic visual inspection require-a. ments, and l 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 capability to accurately determine the airborne iodine concentration in vital areas under accident i l conditions. This program shall include the following: l l a. Training of personnel, b. Procedures for monitoring, and Provisions for maintenance of sampling and analysis equipment. c. 1 1 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, Provisions for maintenance of sampling and analysis equipment. c. 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken fer REPORTABLE EVENTS: l The Commission shall be notified and a Licensee Event Report a. 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.c(1). LA SALLE UNIT 1 6-18 Amendment No. 66

..g ADMINISTRATIVE CONTROLS i I 6.4 ACTION TO BE TAKEN 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, 2.1.2 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.1.a and 6.1.G.2.a and a separate License Event Report for each occurrence'shall be. l' 1 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 President BWR Operations and the Offsite Review and Investigative Function shall be notified within 24 hours. q q

6. 5 PLANT OPERATING RECORDS A.

Records and/or_ logs relative to the following items shall be kept in a -{ l manner convenient for review and shall be retained for at least 5 years: -l l 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 prir.cipal 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 l 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 operatirig procedures; 5. Shift engineers' logs; and 7. Byproduct material inventory records and source leak test results. f LA SALLE UNIT 1 6-19 Amendment No, 66

a ADMINISTRATIVE CONTROLS PLANT OPERATING' RECORDS (Continued) 8. Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the i 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 I transient or operational cycles (identified in Table 5.7.1-1); i 10. Records of individual staff members indicating qualifications, j experience, training, and retraining; 11. Inservice inspections of the reactor coolant system; l 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; 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 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. LA SALLE UNIT 1 6-20 Amendment No. 66

ADMINISTRATIVE CONTROLS 6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the director of the appropriate Regional Office of Inspection and Enforce-ment unless otherwise noted. A. Routine Reports 1. Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall in general include a description of the measured values of the a i operating conditions or characteristics obtained during the test l program and a comparison of these values with design predictions and f_ specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. l Startup reports shall be submitted within (1) 90 days following i completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supple-I mentary reports shall be submitted at least every 3 months until all l three events have been completed. 2. Annual Report A tabulation shall be submitted on an annual basis prior to March 1 of each year of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions (Note: this tabulation supplements the requirements of Section 20.407 of 10 CFR 20), e.g., reactor operations and surveil-lance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions. LA SALLE UNIT 1 6-21 Amendment No. 66

ADMINISTRATIVE CONTROLS Annual Report (continued) The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5 shall be included. l in the Annual Report along with.the following information:.(1) Reac-i tor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analy-sis for radiciodine performed prior to exceeding the limit, results-of analysis while limit was' exceeded and results of one analysis after the radiciodine' activity was reduced to less than limit. Leach ) result should include date and time of' sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours-prior-to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concen-tration in microcuries per gram as a function of. time for the dura-tion of the specific activity above the steady-state level; and (5) The time duration when the specific activity.of the primary coolant exceeded the radiciodine limit. l ? 1 l 1 F l LA SALLE UNIT 1 6-21(a) Amendment No. '66

i 1 + j 1 ADMINISTRATIVE CONTROLS i I 3. Annual Environmental Radiological Operating ReportM Routine environmental radiological operating reports covering a. the operation of the unit during the previous calendar year J shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality. ] b. The annual environmental radiological operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period,. including a comparison with u preoperational studies, as appropriate,' operational controls, as appropriate, and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation j on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. The annual environmental radiological operating reports shall include summarized and tubulated results in the format of Regulatory Guide 4.8, December 1975, of all radiological environ-mental sanples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. i The reports shall also include the following: a summary description of the environmental radichgical monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison. Program, required by Specification 3.12.3. The report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during i the previous calendar year. The assessment of radiation doses i shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). The report shall also include an assessment of radiation doses-to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including LA SALLE UNIT 1 6-22 Amendment No. 66

l ADMINISTRATIVE CONTROLS Annual Environmental Radiological Operating Report (Continued) doses from primary effluent pathways and direct "adiation) for the previous 12 consecutive months to show conformance with-l 40 CFR 190, Environmental. Radiation Protection Standards for l. Nuclear Power Operation. The assessment of radiation doses l shall be performed in accordance with the ODCM. 4. Semiannual Radioactive Effluent Release Report 2! a. Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality, b. The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. 1 i l l I I l S/ single submittal may be made for a multiple unit station. The submittal A should combine those sections that are common to all units at the station; i l however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. l t 1 LA SALLE UNIT 1 6-23 Amendment No. 66 I 1

?.

ADMINISTRATIVE 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: l 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),. Type of container (e.g., LSA, Type'A, Type B, Large Quantity), e. 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. 1 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, shall be submitted on a monthly basis to the Director, Office of Nuclear Reactor Regulation, Mail Station P1-137, US Nuclear Regulatory Commission, Washington, DC 20555, with a copy of the appropriate Regional Office, to arrive no later than the 15th of each month 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 4 LA SALLE UNIT 1 6-24 Amendment No. 66

l } This page intentionally left blank l i l l LA SALLE UNIT 1 6-25 Amendment No. 66

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1 l l t 1 This page intentionally left blank 1 1 1 1 1 l l 1 I l l t l l l 1 l I i 1 LA SALLE UNIT 1 6-27 Amendment No. 66 l l I

o o ADMINISTRATIVE CONTROLS L C. Unique Reporting Requirements 1. Special Reports shall be st.:bmitted 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 i Effluent Release Report for the period in which the change (s) was made. This submittal shall contain: j 1. Sufficiently detailed informat' ion to totally support the rationale for the change without benefit of additional 'or supplemental I 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. i b. Shall become effective upon review and acceptence by'the Onsite Review and Investigative Function. 6.8 0FFSITE DOSE CALCULATION MANUAL (ODCM)* 6.8.1 The ODCM shall be approved by the Commission prior to implementation. 6.8.2 Licensee initiated changes to the ODCM: Shall be submitted to the Commission within 90 days of the date the a. 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 submitted should consist of a package of those pages of the ODCM to be changed with each 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 (PCP)* Common to LaSalle Unit I and LaSalle Unit 2

(0DCM) Common to LaSalle Unit I and LaSalle Unit 2 LA SALLE UNIT 1 6-28 Amendment No. 66

3 ADMINISTRATIVE CONTROLS s Licensee initiated changes to the ODCM: (Continued) 3. Documentation of the fact'that the change has been reviewed and-found acceptable by the Onsite Review and Investigative Function. i b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function. l 6.9 MAJOR CHANCES TO RADI0 ACTIVE WASTE TREATEMENT SYSTEMS 6.9.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid). a. Stall 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 1. A summary of the evaluation that led to the determination that { the change could be made in accordance with 10 CFR 50.59; j 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 and processes involved and the interfaces with other plant systems; 4. An evaluation of the change which shows the predit;ted releases of radioactive materials.in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously I i 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 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 gaseous effluents and in solid waste, to the actual releases for the period to when the changes 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. I b. Shall become effective upon review and acceptance by the Onsite Review l and Investigative Function. l LA SALLE UNIT 1 6-29 Amendment No.' 66 1 --______-___a

~*. a ucy f A UNITED STATES - { } )73 g NUCLEAR REGULATORY COMMISSION r,, ij WASHINGTON, D. C. 20555 \\.v, / COMMONWEALTH EDISON COMPANY DOCKET N0. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENTTOFACILITYOPERATINGLICENg Amendment No. 47 License No. NPF-18 l 1. The Nuclear Regulatory Comission (the Comission or the NRC) has found that: 5 A. The application for amendn;ent filed by the Commonwealth Edison Company (thelicensee),dateoFebruary 17, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmiission's regulations set forth in 10 CFR Chapter I; i B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of ths Commission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in coropliance with the Commission's regulations sr.1 forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common i defense and security or to the health and safety of the public; and { 1 E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfico. 2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in.the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows: (2) Technical $ specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Ar.endr.ent No.47, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. i i )

~$c j 1 .2 I 3. This emendment is effective upon date of issuance. J FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects

Enclosure:

Changes to the Technical Specifications Date of Issuance: April 27, 1989 l I i l

d ENCLOSURE TO LICENSE AMENDMENT N0. 47 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The reviseo pages are identified by amendment number and contain a vertical line indicating tne area of change. REMOVE INSERT XIX XIX 6-1 6-1 6-2 6-2 6-3 6-3 6-4 .6-4 6-5 6-5 6-6 6-6 a. 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 6-1F 6-15 6-16 6-16 i 6 17 6-17 l 6-18 6-18 6-19 6-19 l 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

6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION. REVIEW, INVESTIGATION, AND AUDIT 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 olant. 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 I 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 l Operations, Section 3 Organizational Authority, Activities, 3 Section 6 Interdepartmental Relationships. j 2. The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities j necessary for safe operation and maintenance of the plant. j 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 onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures. B. The Shift Supervisor shall be responsible for directing and commanding the overall operation of the facility on his shift. The primary manage-ment responsibility of the Shift Supervisor shall be for safe operation of the nuclear facility on his shift under al1~ conditions. A management directive signed by Vice President BWR Operations emphasizing this prim::ry l management responsibility and that clearly establishes the command duties of the Shift Supervisor shall be reissued to all station personnel on an annual basis. C. The shift manning for the station shall be as shown in Figure 6.1-3. The individual filling the position of Technical Staff Supervisor shall meet the minimum acceptable level for " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971. The individuals filling the positions of Production Superintendent and Technical Superintendent shall meet the minimum acceptable level for " Plant Manager" as'Jescribed in Section 4.2.1 of ANSI N18.1-1971. LA SALLE - UNIT 2 6-1 Amendment No. 47

1 y-1O ADMINISTRATION CONTROLS 1 ADMINISTRATION CONTROLS 1.- At least one licensed Reactor Operator shall be. in the control room: 4 when fuel is in the reactor. In addition, while the reactor is in J OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior- 'i Reactor Operator who has been designated by the. Shift Supervisor to ] assume the control room direction responsibility shall be in the Control Room.

f 2.

A radiation protection technician

shall be on site when fuel is in i

the reactor. 3. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator J Limited to Fuel Handling who has no other concurrent responsibilities during this operation. j 4. A site Fire Brigade of at least 5 members shall be maintained onsite I 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 l required for other essential functions during a fire emergency. J 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.0NSG shall J be composed of at least three, dedicated, full-time engineers of l 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 l group. TheONSGshallberesponsibleformaintairinggurveillance j of unit activities to provide independent verification that these activities are performed correctly aad 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 j to the Safety Assessment Manager and the Station Manager. 1 6. The Station Control Room Engineer (SCRE) serves as the lead control. l 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 l Supervisor in the areas of thermal hydraulics, reactor engineering and I plant analysis with regard to; the safe oneration of the unit. n 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.

ot re:,ponsible for sign-of f feature.

N LA SALLE - UNIT 2 6-2 Amendment No.' 47 i ..._____._.._.__________o

ADMINISTRATION CONTROLS 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 I 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 hours straight, excluding shift turnover time. b. An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any seven day period, all' excluding shift turnover time. 1 c. A break of at least eight hours should be allowed between work l periods, including shift turnover time. d. The use of overtime should be considered on an individual basis i and not for the entire staff on a shift. i 1 l l Any deviation from the above guidelines shall be authorized by the Production l or Technical Superintendents for their individual departments, or higher levels of management, it. accordance with established procedures and with documentation l 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 gu'delines is not authorized. a 8. The Assistant Superintendent Operating shall hold a Senior Reactor ? Operator License. I 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-l tection maaager of Regulatory Guide 1.8, September 1975. The ANSI i N18.1-1971 qualification requirements for Radiation Protection Technician j 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-l vision who meet the requirements of ANSI N18.1-1971 Section 4.3.2, 1 " 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 j experience identified by the 0NSG. j LA SALLE - UNIT 2 6-3 Amendment No. 47 l

ADMINISTRATION CONTROLS Offsite Review and Investigative Function (Continued) F. Retraining shall be conducted at intervals not exceeding 2 years. G. The Review and Investigative Function and the Audit Function of e.ctivities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined belcw: 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. 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 Assuranca 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 corporats departments to determine that QA/NS policy is being carried out. a. Offsite Review and Investigative Function J 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 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 developeii q by personnel performing the review and investigative function, l (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 - Nucleat 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 e.nd 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 i 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/HS. 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 N 47

) .a I .0-ADMINISTRATION CONTROLS 3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59, i 4) Proposed changes in Technical Specifications or NRC operating l 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-that j affect nuclear safety as referred to it by the Onsite Review and Investigative Function. 7) All REPORTABLE EVENTS. l 8) All recognized indicatior.s of an unanticipated deficiency j in some aspect of design or operation of safety-related structures, systems, or components. 9) Review and report findings and recommendations regarding j all changes to the Generating Stations Emergency Plan l prior to implementation of such change. 1 i

10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station i

Manager, Vice President BWR Operations, and the AVP Quality Programs and Assessment. b. Station Audit Function The Station Audit Fur.ction 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 Deriod of 2 years or less as designated below. 1) Audit of the conformance of fucility 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, t 3) Audit of the results of actions taken to correct l deficiencies occurring in facility equipment, structures, L systems, or methods of operation that affect nuclear safety at least once per 6 months. LA SALLE - UNIT 2 6-5 Amendment No. 47 _ A

o ADMINISTRATION CONTROLS Audit 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. j l 5) Audit of the Facility Emergenc! Plan and implementing l procedures at least once per 12 months. I 6) Audit of the Facility Security Plan and implementing procedures. 7) Audit onsite and offsite reviews. l I 8) Audit the Facility Fire Protection Program and implementing l procedures. l 9) The radiological environmental monitoring program and the I results tnereof at least once per 12 months.

10) The 0FFSITE DOSE CALCULATION MANUAL and implementing l

procedures.

11) The PROCESS CONTROL PROGRAM and implementing procedures I

for solidification of radioactive wastes. J

12) The performance of activities required by.ae 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 o^ 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 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

e 4 ADMINISTRATION CONTROLS Offsite Review and Investigative Function (Continued) 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 Office 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 completipn 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 invest.igative function, in addition to the Superintend-ent of the Offsite Review and Investigative "inction shall have expertise in one or more of the follow 4g disciplines as appropriate for the subject or subjects,b ;?g reviewed c 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 LA SALLE - UNIT 2 6-7 Amendment No. 47-

) l i ADMINISTRATION CONTROLS Offsite Review and Investigative Function (Continued) b) Reactor Operations Engineering graduate.or equivalent with 5 years experience in nuclear power plant operations, c) Utility Operations Engineering graduate or equivalent with at'least 5 years of experience in utility operation and/or engineering. 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 l Engineering graduate or equivalent. In addition, at-I 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 eauivalent 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 s118.1-1971-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 Stacion Manager shall: (1) provide direction for the Review and Investigative Fonction 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 LA SALLE - UNIT 2 6-8 Amendment No. 47

g-4 ADMINISTRATION CONTROLS 0nsite Review and Investigative Function (Continued) comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations. I developed by personnel performing tLe Review and Investigative. Function;- (5) report all findings of noncompliance with NRC, requirements, and provide recommendations; 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 thereto, (2) all programs required.by Specifica-l 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. 1 3). Review of all proposed changes to the Technical Speci- ] fications. I 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 and shall prepare and forward a report covering evalua-tion and recommendations to prevent' recurrence; 6) Review of fac lity 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 recommended changes to the Director.of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with' Specification 6.1.G.2.c(1). l 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 disposition of the corrective -action to prevent recur-rence;

12) Review of changes to the PROCESS CONTROL PROGRAM, 0FFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

LA SALLE - UNIT 2 6-9 Amendment No. 47

e ADMINISTRATION CONTROLS

] Onsite Review and Investigative Function (Continued) 1 i b. Authority The Technical Staff Supervisor is responsible to the Station I Manager and shall make recommendations in a timely manner in j all areas of review, investigation, and quality control phases-of plant maintenance, 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 l necessary. The Station Manager shall follow such' recommendations i or select a course of action that is more conservative regarding l safe operation of the facility. All such disagreements shall be reported immediately to the Vice President BWR Operations and i the Superintendent of the Offsite Review and Investigative Function. c. Records ) 1) Reports, reviews, investigations, and recommendations shall be documented with copies to the Vice President BWR Operations prepared and performed for Specification 6.1.G.2a, 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 i for conduct of the Onsite Review and Investigative Function. ) These procedures shall include the following: 1 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: i' 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

l f l ADMINISTRATION CONTROLS 1 Onsite Review and Investigative Function (Continued) 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 l audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm. l 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. 1 l l l l l l l LA SALLE - UNIT 2 6-10a Amendment No. 47 .i

4 1 THIS PAGE INT?NTIONALLY LEFT BLANK a 1 ( J o LA SALLE - UNIT 2 6-11 Amendment No. 47

9 1 I l l, 1 1 i THIS PAGE INTENTIONALLY LEFT DLANK l LA SALLE - UNIT 2 6-12 Amendment No.- 47

a l 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 I a a SE l y 3 a SF l None-b R0 2 y l b A0 2 1 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: I 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 a SE l y a SF l None b R0 2 y l b A0 2 7 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 a SE l l SF 1 None R0 2 1 b A0 2 2 STA 1 None LA SALLE - UNIT 2 6-13 Amendment No. 47

Figure 6.1-3 (Continued) MINIMUM SHIFT CREW COMPOSITION NOTES ^IIndividual may fill the same position-on Unit 1. W ne of the two required individuals may fill the same position on Unit 1. 0 1 i 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. R0 - Individual with a Reactor Operators License on Unit 2. 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. exceed 2 hours in order to accommodate unexpected absence of on duty shift I crew members provided immediate action is taken to restore-the shift crew I 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 1 change due to an oncoming shift crewman being late or absent. I While he unit is in OPERATIONAL CONDITION 1, 2, or 3, an individual with a valid LR0 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. i t LA SALLE - UNIT 2 6-14 Amendment No. 47

~ p. e ADMINISTRATION 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 " con-trol device" or " alarm signal" required by paragraph 20.203(c)(2) 'of 10 CFR 20, each hig/hr* but less than 1000 mrem /hr* shall be barricaded and conspicuous h radiation area in which the intensity of radiation is greater than 100 mrem 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 personne1' continuously escorted by such . individuals, may be' exempt from the RWP issuance requirement during the per-formance 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 permitted to enter such areas shall be provided with or accompanied by one or more of the following: A radiation monitoring device which co..tinuously indicates the a. 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. A health physics qualified individual, i.e., qualified in radiation c. 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 l Work Permit (RWP). 6.1.1. 2 In addition to the requirements of 6.1.1.1, above, for areas accessible i topersonnelwithradiationlevelssuchthatamajorportionofthebodycould l 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 R~WP which shall specify the dose rate levels in the immediate work i area and the maximum allowable stay time for individuals in that area. For-i

Measurement made at 18" from source of radioactivity.

LA SALLE - UNIT 2 6-15 Amendment No. 47

ADMINISTRATION CONTROLS i l HIGH RADIATION AREAS (Continued) 1 individual areas accessible to personnel with radiation levels such that a ) major [ortion of the body could receive in one hour a dose in excess of -) 1000 mr:m* that are located within large areas, such as the containment, where no enclesure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, con-spicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote, such as use of closed circuit TV cameras, continuous surveillance may be made by per-sonnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area. 6.2 PLANT OPERATING PROCEDURES AND PROGRAMS A. Detailed written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to: 1. The applicable procedures recommended in Appendix "A" of Regulatory j Cuide 1.33, Revision 2, February 1978. J 2. Refueling operations. \\ 3. Actions to be taken to correct specific and foreseen potential 1 malfunctions of systems or components including responses to alarms, suspected primary system leaks, and abnormal reactivity changes. 4. Emergency conditions involving potential or actual release of radioactivity " Generating Stations Emergency Plan" and station emergency and abnormal procedures. 5. Instrumentation operation which could have an effect on the safety of the facility. 6. Preventive and corrective maintenance operations which could have an effect on the safety of the facility. 7. Surveillance and testing requirements. 8. Tests and experiments. 9. Procedure to ensure safe shutdown of the plant. 10. Station Security Plan and implementation procedures. 11. Firu Protection Program implementation. l 12. Process Control Program implementation. 13. OFFSITE DOSE CALCULATION MANUAL implementation. 14. Company Quality Assurance Program and Procedures for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, December 1977.

Measurement made at 18" from source of radioactivity.

LA'SALLE - UNIT 2 6-16 Amendment No. 47

l ADMINISTRATION 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. l C. 1. Procedures for items identified in Specification 6.2.A and any. changes l l 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 Maintenance l Assistant S nerintendent and Technical Staff Supervisor in the areas i of plant maintenance and plant inspection. Procedures for' items l idencified in Specification 6.2..B and any changes to such procedures i shall be reviewed and approved by the Technical Staff Supervisor and l the Health Physics Supervisor. At least one person approving each of the above procedures shall hold a valid senior operatnr's license. In addition, these procedures and changes thereto, must have authori-zation by the Station Manager before being implemented. 2. Work and instruction type procedures which implement approved main-tenance or modification procedures shall be approved and authorized l by the Maintenance Assistant Superintendent where the written author-ity has been provided by the Station Manager. The " Maintenance / 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 be made provided: 1 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 whon holds a Senior Reactor Operator's License 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. l E. Drills of the emergency procedut ec Oscribcd in Specification 6.2. A.4 shall be conducted at frequencies as m cified in the Generating Stations Emergency Plan (GSEP). These acills w!!' be planned se that during the course of the year, communication ! inks ai

tested and outside agencies are contacted.

LA SALLE - UNIT 2 6-17 Amendment No. 47 lu______

". e ADMINISTRATION CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) F. The following programs shall be established, implemented, and maintained: 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 as low as practical levels. The systems include LPCS, HPCS, RHR/LPCI, RCIC, hydrogen recombiner, process sampling, containment monicoring, and standby gas treatment systems. The program shall include the following: Preventive maintenance and periodic visual inspection require-a. 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 capability to accurately determine the airborne iodine concentra?ic1 in vital areas under accident conditions. This program shall include the following: a. Training of personnel, b. Procedures for monitoring, and Provisions for maintenance of sampling and analysis equipment. c. 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: l a. Training of personnel, b. Procedures for sampling and analysis, Provisions for maintenance of sampling and analysis equipment. c.

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:

The Commission shall be notified and a Licensee Event Report submitted a. pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b. Each REPORTABLE EVENT shall be reviewed pursuant to Specifica-tion 6.1.G.2.c(1). LA SALLE - UNIT 2 6-18 Amendment No. 47

~. '. ADMINISTRATION CONTROLS 6.4 ACTION TO BE TAKEN 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, 2.1.2 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 purruant to Specifications 6.1.G.1.a and 6.1.G.2.a and a separate Licensee Event Report for each occurrence shall be l 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 President BWR Operations and the Off-site Review and Inves-tigative Function shall be notified within 24 hours.

6. 5 PLANT OPERATING RECORDS A.

Records and/or logs relative to the following items shall be kept in a l 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 pcwer level; 2. Records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to i l nuclear safety; 1 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 l specifications) are being met. All equipment failing to meet surveil-l 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. LA SALLE - UNIT 2 6-19 Amendment No. 47

ADMINISTRATION CONTROLS PLANT OPERATING RECORDS (Continued) B. Records and/or logs relative to the following items shall be recorded in 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; 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; 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 equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59; 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; and 17. Records of analyses required by the radiological environmental monitoring program. LA SALLE - UNIT 2 6-20 Amendment No. 47

1 e ADMINISTRATION CONTROLS 6.6 REPORTING REQUIREMENTS I l .In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the director of the appropriate Regional Office of Inspection and Enforce-ment unless otherwise noted. A. Routine Reports l 1. Startup Report A summary report of plant startup and power escaletion testing shall be submitted following (1) receipt of an operating license, l (2) amendment to the license involving a planned increase in i power level, (3) installation of fuel that has a different design l or has been manufactured by a different fuel supplier, and (4) i modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other I commitments shall be included in this report. Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startu'p report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supple-mentary reports shall be submitted at least every 3 months until all three events have been completed. 2. Annual Report A tabulation shall be submitted on an annual basis prior to March 1 of each year of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions (Note: this tabulation supplements the requirer ts of Section 20.407 of 10 CFR 20), e.g., reactor operations anc ourveil-lance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific majorworkfunctions. LA SALLE - UNIT 2 6-21 Amendment No. 47

) j l i ADMINISTRATION CONTROLS Annual Report (continued) The results of specific activity analysis in which the primary l coolant exceeded the limits of Specification 3.4.5 shall be included in the Annual Report along with the following information: (1) Reac - tor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analy-sis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine 1 concentrations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concen-tration in microcuries per gram as a function of time for the dura-tion of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit. l l l l l l \\ l l LA SALLE - UNIT 2 6-21(a) Amendment No. 47 i

4 ADMINISTRATION CONTROLS 3/ 3. Annual Environmental Radiological Operating Report a. Routine environmental radiological operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality. b. The annual environmental radiological operati.ng reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, as appropriate, operational controls, as appropriate, and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2. The annual environmental radiological operating reports shall include summarized and tubulated results in the format of Regulatory Guide 4.8, December 1975, of all radiological environ-I mental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the environmental radiological monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3. The report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall-include an assessment.of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). The report shal! also include an essessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including LA SALLE'- UNIT 2 6-22 Amendment No. 47

, f. ) l ADMINISTRATION CONTROLS Annual Environmental Radiological Operating Report (Continued) doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. The assessment of radiation doses shall be performed in accordance with the ODCM. 4. Semiannual Radioactive Effluent Release ReportW a. Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of' operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality. b. The radioactive effluent release reports shai. include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. i i E single submittel may be made for a multiple unit station. The submittal A should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. LA SALLE - UNIT 2 6-23 Amendment No. 47

4 ADMINISTRATION 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), Principal radionuclides (specify whether determined by c. measurement or estimate), d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), Type af container (e.g., LSA, Type A, Type B, Large Quantity), e. and t. 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, shall be submitted on a monthly basis to the Director, Office of Nuclear Reactor Regulation, Mail Station P1-137, US Nuclear Regulatory Commission, Washington, DC 20555, with a copy of the appropriate Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report. Any changes to the 0FFSITE 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. LA SALLE - UNIT 2 6-24 Amendment No. 47

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e l ADMINISTRATION CONTROLS Semiannual Radioactive Effluent Release Report (Continued) 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)* l 6.7.1 The PCP shall be approved by the Commission prior to implementation. l 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 effactive upon review and acceptance by the Onsite Review and Investigative Function. t I ii i i

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 l

9 ADMINISTRATION CONTROLS 6.8 0FFSITEDOSECALCULATIONMANUAL(0DCM)* 6.8.1 The ODCM shall be approved by the Commission prior to 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 submitted should consist of a package of those pages of the ODCM to be changed with each 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 TREATMENT SYSTEMS 6.9.1 Licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous, and solid): Shall be reported to the Commission in the Monthly Operating Report a. 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 and processes involved and the interfaces with other plant systems;

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

LA SALLE - UNIT 2 6-29 Amendment No. 47 N

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) r l 1 l 1 ADMINISTRATION CONTROLS l MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Continued) I i 4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or c,uantity of solid waste that differ from those previously predicted in the license application and amendments thereto; i 5. 'An evaluation of the change which shows the expected maximum i exposures to individual in the unrestricted area ar.d to the caneral population that differ from those previously ostimated in the license application and amendments thereto; 6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period to when the changes are to be made; 7. An estimate of the exposure to plant operating personnel as a result of the change; and j l 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. i l t LA SALLE - UNIT 2 6-30 Amendment No. 47 . _____ _ -_-___-__ _}}

ML20245H780

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