ML20245G451
| ML20245G451 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 04/24/1989 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20245G456 | List: |
| References | |
| NPF-37-A-027, NPF-66-A-027, NPF-72-A-016, NPF-77-A-016 NUDOCS 8905030150 | |
| Download: ML20245G451 (42) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
- E WASHINGTON, D. C. 20555 4
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COMMONWEALTH EDISON COMPANY i
DOCKET N0. 50-454 BYRON STATION. UNIT 1 t
AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 27 License No. NPF-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated February 17, 1989, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct) and the Comission's rules and regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; i
C.
There is reasonable assurance (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 in compliance with the Comission s regulations; i
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
L 2.
Accordingly, the license is amended by changes to the Technical Specifica-l tion as indicated in the attachment to this license amendment, and 1
I paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 27 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 24, 1989 1
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g NUCLEAR REGULATORY COMMISSION 5
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-455 BYRON STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated February 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) l and the Comission's rules and 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 rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withuut endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'.s regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
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1 (2) Technical Specifications lhe Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 27 and revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR. REGULATORY COMMISSION Daniel R. Muller, Director
' Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 1989 l
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ATTACHMENT TO LICENSE AMENDMENT NOS. 27 AND 27 L
FACILITY OPERATING LICENSE NOS NPF-37 AND NPF-66 i
DOCKET NOS. 50-454 AND 50-455-
' Revise Appendix A as follows:
Renove Pages.
Insert Pages XX XX l
f 6-1 6-1 6-2 6-2 6-2a 6-3 6-3 6-4 6-4 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-24 6-24 6-25 6-25
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i ADMINISTRATIVE CONTROLS i
SECTION PAGE l
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I 6.1 RESPONSIBILITY................................................
6-1 i
6.2 ORGANIZATION..................................................
6-1 FIGURE 6.2-1 (THIS FIGURE NOT USED)...............................
6-3 FIGURE 6.2-2 (THIS FIGURE NOT USED)...............................
6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION........................
6-5 6.3 UNIT STAFF QUALIFICATIONS.....................................
6-6 6.4 TRAINING.................................................
6-6 l
6.5 REVIEW INVESTIGATION AND AUDIT................................
6-6 6.5.1 0FFSITE.....................................................
6-6 Offsite Review and Investigative Function...................
6-6 Station Audit Function......................................
6-8 Authority...................................................
6-9 Records.....................................................
6-10 Procedures..................................................
G-10 Personne1...................................................
6-10 6.5.2 0NSITE...........
6-12 Onsite Review and Investigative Functions...................
6-12 Responsibility..............................................
6-12 Authority...................................................
6-13 Records..................................................
6-14 Procedures..................................................
6-14 Personne1...................................................
6-14 6.6 REPORTABLE EVENT ACTI0N.......................................
6-15 BYRON - UNITS 1 & 2 XX AMENDMENT NO. 27
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ADMINISTRATIVE CONTROLS 6.1 -RESPONSIBILITY 6.1.1_ The Station Manager, Byron Station, shall be responsible for overall unit operation and shall delegate in writing the succession to this respon-sibility during his absence.
6.1.2.The Shift Engineer (or during his absence from the control room, a designated individual) shall be responsible for the control room command function.
A management directive to this effect, signed by the Vice President PWR Operations shall be reissued to all station personnel on an annual basis.
- 6. 2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS 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.
a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.-
These requirements shall be documented in the Quality Assun nce Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Relationships.
b.
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.
4 c.
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.
d.
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 j
pressures.
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1 BYRON - UNITS 1 & 2 6-1 AMENDMENT NO. 27 E_
ADMINISTRATIVE CONTROLS I
6.2.2 UNIT STAFF The unit staff shall be subject to the following:
I a.
Each on duty shift shall be composed of at least the minimum ch -
crew composition shown in Table 6.2-1; and i
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
In addition, while the unit is in MODE 1, i
2, 3, or 4, at least one licensed Senior Operator shall be in the control room;
{
A Radiation Protection Technician,* qualified in radiation protection l
c.
procedures, shall be on site when fuel is in the reactor; d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; Administrative procedures shall be developed and implemented to e.
limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance j
personnel.
The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12);
f.
The Assistant Superintendent Operating shall hold a Senior Reactor Operator License.
6.2.3 ONSITE NUCLEAR SAFETY GROUP (0NSG) g, i
FUNCTION s
6.2.3.1 The ONSG serves as an independent safety engineering group and shlll function to examine plant operating characteristics, NRC issuances, industry advisories, REPORTABLE EVENTS and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
The 0NSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, opera-tions activities or other means of improving plant safety to the Safety Assessment Manager, and the Station Mareger, Byron Station.
COMPOSITION 6.2.3.2 The 0NSG shall be composed of at least three, dedicated, full-time engineers located on site.
- The Radiation Protection Technician may be less than the minimum requirements l
for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
BYRON - UNITS '. & 2 6-2 AMENDMENT NO. 27
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'y ADMINISTRATIVE CONTR0'LS 6.2.3 ONSITE-NUCLEAR' SAFETY oROUP (0NSG) (Continued)
I RESPONSIBILITIES
-l 6.2.3.3 The 0NSG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 1
6.2.3.4 Records of activities performed by the 0NSG shall be prepared, main-tained, and forwarded each calendar month to the Safety Assessment Manager, and the Station Manager, Byron Station.
6.2.4 SHIFT TECHNICAL ADVISOR The Station Control Room Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal operating or accident conditions.
During these conditions the SCRE or other on duty STA 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.
To assure capability.for performance of all STA functions:
(1) The shift foreman (SRO) shall participate in the SCRE shift relief turnover.
(2) During the shift,.the shift engineer and the Sift foreman (SRO) shall be made aware of any significant changes in plant status in a timely manner by the SCRE.
l (3) During the' shift, the shift engineer and the shift foreman (SRO) shall remain abreast 'of the current plant status.
The shift foreman (SRO) shall return to the control room two or three times per shift, where practicable, to confer with the SCRE regarding plant status.
Where not practicable to return to the control room, the shift foreman (SRO) shall periodically check with the SCRE for a plant status update.
The shift foreman (SRO) shall not abandon duties original to reactor operation, unless specifically ordered by the shift engineer.
- Not responsible for sign-off function.
BYRON-- UNITS 1 & 2 6-2a AMENDMENT N0. 27
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ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971, except for the Health Physics Supervisor or Lead l
Health Physicist, who shall meet or exceed the qualifications of Regulatory.
Guide 1.8, September 1975,'for a Radiation Protection Manager.
The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifica-tions of the supplemental requirements specified in Sections A and C of of the March 28, 1980 NRC letter to all licensees.
l 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Production Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /'
ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter i
to all licensees, and shall include familiarization with relevant industry i
l operational experience from the program managed by Quality Programs and l
Assessment.
6.5 REVIEW INVESTIGATION AND AUDIT i
The Review ano Investigative Function and the Audit Function of activities I
affecting quality during facility operations shall 1.9 constituted and have the responsibilities and authorities outlined below.
0FFSITE 6.5.1 The Superintendent of the Offsite Review and Investigative Function i
shall be appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS)-
responsible for nuclear activities.
The corporate audit function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Eu cutive Officer and eas the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS.
The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.
-a.
Offsite Review and-Investigative Function The Superintendent of the Offsite Review and Investigative Function shall:
(1) provide directions for the review and investigative 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 interdisciplinary review coverage under l
this function, (4) independently review and approve the findings l
and recommendations developed by personnel performing the review BYRON - UNITS 1 & 2 6-6 AMENDMENT NO. 27 l
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' ADMINISTRATIVE CONTROLS
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4 0FFSITE-(Continued) 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 PWR 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 Offr.ite Review and Investigative' Function is unavailable, he shall'desigr; ate this responsibility to an established alternate, who satisfies the formal training and experience for the i
Superintendent of the'0ffsite Review and Investigative Function.
The responsibilities of the personnel performing this function are stated below.
The Offsite Review and Investigative Function shall review:
1)
The safety evaluations for:
(1) changes to procedures, equip-ment, or systems as described in the safety analysis report, i
and (2) tests or experiments completed under the provision of l
10 CFR 50.b9 to verify that such actions did not constitute an,unreviewed safety question.
Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS; 2)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; 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 this Operating License; 5)- Noncompliance with Codes, regulations, orders, Technical Speci-fications, license requirements, or of internal procedures, or instructions having nuclear safety significance; 6)
Significant operating abnormalities or devietion from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function; l
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; l
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change; and j
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BYRON - UNITS 1 & 2 6-7 AMENDMENT NO. 27 L--_--_--
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ADMINISTRATIVE CONTROLS OFFSITE (Continued)
- 10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President PWR Operations and AVP Quality Programs and Assessment.
b.
Station Audit Function The station audit function shall be the responsibility of the AVP Quality Programs and Assessment independent of PWR operations.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
The Nuclear Quality Programs Manager, or designated corporate staff or supervision approved by the AVP Quality Programs and Assessment shall approve the audit agenda and checklists, the findings and the l
report of each audit.
Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure t5at safety-related functions are covered within the period designated below:
1)
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; 2)
The adherence to procedure, training, and qualification of the station staff at least once per 12 months; 3)
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months; 4)
The performance of activities required by the Operational Quality Assurance Program to meet the cr.iteria of Appendix B, 10 CFR Part 50, at least once per 24 months; 5)
The Facility Emergency Plan and implementing procedures at least once per 12 months; f
l 6)
The Facility Security Plan and iniplementing proc +eres at least once per 12 months; 7)
Onsite and offsite reviews; 8)
The Facility Fire Protection programmatic controls including the implementing procedures at least once per 24 months by qualified QA personnel; 9)
The fire protection equipment and program implementation at l
least once per 12 months utilizing either a qualified offsite l
licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire pro-tection consultant shall be used at least every third year; l
BYRON - UNITS 1 & 2 6-8 AMENDMENT NO. 27
.f ADMINISTRATIVE CONTROLS' 0FFSITE (Continued)
- 10) The Radiological Environmental Monitoring Program and the results-thereof at least once per 12 months;
- 11) The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; 1
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- 12) The PROCESS CONTROL' PROGRAM and implementing procedures for
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solidification of radioactive wastes at least once per 24 months; and
- 13) The performance of activities required by the Company Quality
~ Assurance Program for effluent and environmental monitoring 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, the Vice President PWR Operations, AVP Quality Programs-and Assessment, the Senior Vice President - Nuclear Operations, and the Chief Operating Of ficer.
c.
Authority j
)
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 Oper&tions.
The AVP Quality Programs and
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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.
1 BYRON - UNITS 1 & 2 6-9 AMENDMENT NO. 27
__.m._. _ _ _ __ _ _ _ _ _ _ _ _. _ _ _. _ _ _ _ - - _ =. -
ADMINISTRATIVE CONTROLS OFFSITE (Continued) h)
Instrumentation an'd Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.
i)
Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.
3)
The Superintendent of the Offsite Review and Investigative Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.
)
ONSITti 6.5.2 The Onsite Review and Investigative Function shill be supervised by the Station Manager.
d.
Onsite Review and Investigative Function The Station Manager shall:
(1) provide directions for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as the senior participant to provide appropriate directions; (2) approve participants for this function; (3) assure that at least two participants who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommendations l
and (6) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Speci-fication 6.5.la which have been approved by the Onsite Review and Investigative Function.
b.
Responsibility l
The responsibilities of the personnel performing this function tre:
l l
1)
Review of:
(1) station specific portions of all procedures required by Specification 6.8.1 and changes thereto, (2) all programs required by Specification 6.8.4 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 tests and experiments that affect nuclear safety; BYRON - UNITS 1 & 2 6-12 AMENDMENT N0. 27
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' ADMINISTRATIVE CONTROLS ONSITE (Continued) 3)
Review of all.. proposed changes to the Technical Specifications; L4)
Revi=w of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; 5)
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence; l
6)
Review of all REPORTABLE EVENTS; 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 implementing procedures and submittal of recommended changes'to the Station Security Plan to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with Specification 6.5.2d.1; 9)
Review-of the Emergency Plan and station implementing procedures and identification of recommended changes; l
- 10) Review of Unit operations to detect potential hazards to nuclear safety;
- 11) Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation and forwarding of reports I
covering evaluation, recommendations and disposition of the corrective action to prevent recurrence;
.I
- 12) Review of changes to the PROCESS CONTROL PROGRAM, the 0FFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems; and
- 13) Review of the Fire Protection Program and implementing instruc-tions and identification of recommended changes.
l c.
Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant 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 necessary.
The Station Manager shall follow such recommendations or select a course 1'
l BYRON - UNITS 1 & 2 6-13 AMENDMENT N0. 27 l
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ADMINISTRATIVE CONTROLS ONSITE (Continued) of action that is more conservative regarding saf~ operation of the facility.
All such disagreements shall be reportad immediately to the Vice President PWR Operations and the Superintendent of the l
l Offsite Review and Investigative Function.
d.
Records
]
1)
Reports, reviews, investigations, and recommendations prepared i
and performed for Specification 6.5.2b shall be documented with copies to the Vice President PWR Cperations, the Superintendent of the Offsite Review and Investigative Function, and the AVP Quality Programs and Assessment, unless otherwise specified.
2)
Copies of all records and documentation shall be kept on file i
at the station.
e.
Proce6 res Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative Function.
These procedures shall include the following:
1)
Content and method of submission and presentation to the Station Manager, Vice President PWR Operations, and the Superintendent l
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, and 6)
Assignment of responsibilities.
f.
Personnel 1)
The personnel performing the Onsite Review and Investigative i
Function, in addition to the Station Manager, shall consist of l
persons having expertise in:
a)
Nuclear power plant technology, b)
Reactor operations, c)
Reactor engineering, d)
Chemistry e)
Radiological controls, f)
Instrumentation and control, and g)
Mechanical and electrical systems.
BYRON - UNITS 1 & 2 6-14 AMENDMENT N0. 27
ADMINISTRATIVE CONTROLS ONSITE (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.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Onsite Review and Investigative Function and the results of this review shall be submitted to the Offsite Review and Investigative Function and the Vice President PWR Operations.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President PWR Operations and the Offsite Review and Investigative Function shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the Onsite Review and Investigative Function.
This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence; c.
The Safety Limit Violation Report shall be submitted to the Commission, the Offsite Review and Investigative Function and the Vice President PWR Operations within 14 days of the violation; and d.
Critical operation of the Unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written p1ocedures shall be established, implemented, and maintained covering the activities referenced below:
I a.
The applicable procedures recommended in Appendix A, of Regulatory l
Guide 1.33, Revision 2, February 1978, 1
i BYRON - UNITS 1 & 2 6-15 AMEN 0 MENT NO. 27
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ADMINISTRATIVE CONTROLS
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HIGH RADIATION ARFA_ (Continued) f source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures or personnel continuously escorted l
by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, 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 bc provided with or accompanied by one or more of the following:
i a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area; or I
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dcse is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the Radiation Work Permit.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible j
to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiction source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
During emergency situations which involve personnel injury or actions taken tc l
prevent major equipment damage, continuous surveillance and radiation monitoring of the work area by a qualified individual may be substituted for the routine RWP procedure.
For individual high radiation areas accessible to personnel with radiation l
levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded (by a more substantial obstacle than rope),
conspicuously posted, and a flashing light shall be activated as a warning device.
l BYRON - UNITS 1 & 2 6-24 AMENDriENT N0. 27 I
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 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 l
supplemental information; 2)
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3)
Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and Investigative Function.
b.
Shall become effective upon review and acceptance by the Onsite Review and Investigative Function in accordance with Specification 6.5.2.
6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
a.
Shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.9.1.8 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, dated and containing the revision number, 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 j
found acceptable by the Onsite Review and Investigative Function.
j b.
Shall become effective upon review and acceptance by the Onsite Review and.'1vestigative f' unction in accordance with Specification 6.5.2.
i BYRON - UNITS 1 & 2 6-25 AMENDMENT NO. 27
o UNITED STATES
.[
g NUCLEAR REGULATORY COMMISSION o
, r;
- E WASHINGTON, D. C. 20555
\\..... p COMMONWEALTH EDISON COMPANY DOCKET NO. 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 i
License No. NPF-72 1.
The Nuclear Reguletory Consnission (the Coinmission) has found that:
A..
The application for amendment by Commonwealth Edison Company (the licensee) dated February 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Consnission's rules and regulations set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 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 compliance with the Comn'ission'.s regulations; i
D.
The issuance of this amendment will not be inimical to the common l
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of tas Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-72 is hereby amended to read as follows:
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_m._ _ _ _ _ _.. _ _ _. _ _ _ _ _. _ _
m' 4
v;.,
2 l
(2).TechnicalSpecifications The Technical Specifications contained in Appendix A as revised through Amendment No.16 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are
{
~hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This. license amendment-is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k $l Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects Attachnent:
Changes to.the Technical Specifications Date of Issuance: April 24, 1989 i
l 1
1
E:1 a nooy c[
.-g NUCLEAR REGULATORY COMMISSION
- s
' 7..
- j WASHINGTON, D. C. 20656
' %g....,/
1 1
COMMONWEALTH EDISON COMPANY DOCKET N0. 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment.110.16 License No. NPF-77 i
1.
The Nuclear Regulatory Comission (the Counission) has' found that:
1 A.
The application for amendment by Commonwealth Edison Company (the licensee) dated Februa y 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)'
and-the Comission's rules and 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 rules and regulations of the Comission; 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' compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment.is in accordar.ce with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i
been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
l u
' f.
r l:.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 16 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No.
NPF-72, dated July 2, 1987, are hereby incorporated into'this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel.R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24,1989.
ATTACHMENT TO LICENSE AllENDNENT NOS.16 AND 16 1
FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 1
(
DOCKET NOS. 50-456 AND 50-457
]
i Revise Appendix A as follows-I Remove Pages Insert Pages XX XX 6-1 6-1 6-2 6-2 6-2a 6-3 6-3
.6-4 6-4 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-24 6-24 6-25 6-25 i
l
J s
I ADMINISTRATIVE CONTROLS 1
'SECTION PAGE 6.1 RESPONSIBILITY................................................
6-1 6.2 ORGANIZATION..................................................
6-1 FIGURE 6.2-1 (THIS FIGURE NOT USE0)...............................
'6-3 FIGURE 6.2-2 (THIS' FIGURE NOT USED)...............................
6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION........................
6-5 TABLE 6.2-la MINIMUM SHIFT CREW COMPOSITION.......................
6-Sa 6.3 UNIT STAFF QUALIFICATIONS.....................................
6-6 6.4 TRAINING......................................................
6-6 6.5. REVIEW INVESTIGATION AND AUDIT................................
6-6 1
6.5.1 0FFSITE.....................................................
6-7 Offsite Review and Investigative Function...................
6-7 Station Audit Function......................................
6-8
.l A u t h o r i ty...................................................
6-9 q
Records.....................................................
6-10 j
Procedures.........................
6-10 Personnel...................................................
6-10 6.5.2 0NSITE......................................................
6-12 Onsite Review and Investigative Functions...................
6-12 Responsibility..............................................
6-12 Authority...................................................
6-13 Records....................................................
6-14 Procedures..................................................
6-14 Personnel...................................................
6-14 6.6 REPORTABLE EVENT ACTI0N.......................................
6-15 I
I
.BRAIDWOOD - UNITS 1 & 2 XX Amendment No. 16 1
ADMINISTRATIVE CONTROLS
-6.1 RESPONSIBILITY 6.1.1 The Station Manager, Braidwood Station, shall be responsible for overall unit operation and shall delegate in writing the succession to this responsi-bility during his absence.
6.1. 2 The Shift Engineer (or during his absence from the control room, a designated individual) shall be responsible for the control room command function.
A management directive.to this effect, signed by the Vice President l
PWR Operations shall be reissued to all station personnel on an annual basis.
l I
6.2 ORGANIZATION I
6.2.1 ONSITE AND 0FFSITE ORGANIZATIONS Onsite and offsi_te organizations shall be established for unit operation and corporate management, 'respectively.
The onsite and offsite organizations t
shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear i
Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Relationships.
b.
The Station Manager shall be responsible for overall unit safe i
operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Senior Vice President-Nuclear Operations shall have corporate responsibility for overall plant nuclear safety ar.
..J 1 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.
l l
d.
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.
6.2.2 UNIT STAFF The unit staff shall be subject to the following:
l a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; and BRAIDWOOD - UNITS 1 & 2 6-1 AMENDMENT NO. 16
ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; c.
A Radiation Protection Technician,* qualified in radiation protection l
procedures, shall be on site when fuel is in the reactor; d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; e.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.
The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter Nc. 82-12);
f.
The Assistant Superintendent Operating shall hold a Senior Reactor Operator License.
6.2.3 ONSITE NUCLEAR SAFETY GROUP (0NSG)
FUNCTION 6.2.3.1 The 0NSG serves as an independent safety engineering group and shall function to examine plant operating characteristics, hRC issuances, industry advisories, REPORTABLE EVENTS and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
The 0NSG shall make detailed recommendations l
for revised procedures, equipment modifications, maintenance activities, opera-i tions activities or other means of improving plant safety to the Safety Assessment Manager, and the Station Manager, Braidwood Station.
COMPOSITION 6.2.3.2 The 0NSG shall be composed of at least four, dedicated, full-time engineers located on site.
l 1
- The Radiation Protection Technician may be less than the minimum requirements l
for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
BRAIDWOOD - UNITS 1 & 2 6-2 A!iEN0 MENT N0. 16 l
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ADMINISTRATIVE CONTROLS 6.2.3 ONSITE NUCLEAR SAFETY GROUP (0NSG) (Continued)
RESPONSIBILITIES 6.2.3.3 The 0NSG shall be responsible for maintaining surveillance of plant l
activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the 0NSG shall be prepared, main-tained, and forwarded each calendar month to the Safety Assessment Manager, and the Station Manager, Braidwood Station.
6.2.4 SHIFT TECHNICAL ADVISOR The Station Control Room Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal operating or accident conditions.
During these conditions the SCRE or other on duty STA 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.
- Not responsible for sign off function.
BRAIDWOOD - UNITS 1 & ?
6-2a AMENDMENT N0.16
__x_..___
0 9
r FIGURE 6.2-1 (THIS FIGURE NOT USED)
BRAIDWOOD - UNITS 1 & 2 6-3 AMENDMENTNO.i6
I
?
'4 e
FIGURE 6.2-2 h
h, (THIS FIGURE NOT USED) i I
BRAIDWOOD - UNITS 1 & 2 6-4 AMENDMENT NO.16
[
J ADMINISTRATIVE CONTROLS 1
l 6.2.4 SHIFT TECHNICAL ADVISOR (Continued)
To assure capability for performance of all STA functions:
(1) The shift foreman (SR0) shall participate in the SCRE shift relief turnover.
(2) During the shift, the shift engineer and the shift foreman (SRO) shall be made aware of any significant changes in plant status in a timely manner by the SCRE.
(3) During the shift, the shift engineer and the shift foreman (SR0) shall remain abreast of the current plant status.
The shift foreman (SRO) shall return to the control room two or three times per shift, where practicable, to confer with the SCRE regarding plant status.
Where not practicable to return to the control room, the shift foreman (SRO) shall periodically check with the SCRE for a plant status update.
The shift foreman (SRO) shall not abandon duties original to reactor operation, unless specifically ordered by the shift engineer.
6.3 UNIT STAFF QUALIFICATIONS o.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971, except for the Health Physics Supervisor or Lead l
Health Physicist, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager.
The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifi-cations of the supplemental requirements specified in Sections A and C of of the March 28, 1980 NRC letter to all licensees.
J 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Production Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /
ANS 3.1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements spr ified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience from the program managed by Quality Progrems and Assessment.
6.5 REVIEW INVESTIGATION AND AUDIT 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.
BRAIDWOOD - UNITS 1 & 2 6-6 AMENDMENT NO. 16
{
ADMINISTRATIVE CONTROLS 6.5 REVIEW INVESTIGATION AND AUDIT (Continued) 0FFSITE l
6.5.1 The Superintendent of the Offsite Review and Investigative Function l
shall be appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS) i responsible for nuclear activities.
The corporate audit function shall be the
)
responsibility of the Manager of QA/NS and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS.
The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.
a.
Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Function shall:
(1) provide directions for the review and investigative 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 subj'sct matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings and rec-commendations developed by personnel performing the review and inves-tigative function, (5) approve and report in a timely manner all findings of non-compliance with NRC requirements to the Station Mcnager, Vice President PWR Operations, Manager of QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment, and the Senior Vice Presi-dent - Nuclear Operations.
During periods when the Superintendent of the 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 Investigative Function.
The responsibilities of the personnel performing this function are stated below.
The Offsite Review and Investigative Function shall review:
1)
The safety evaluations for:
(1) changes to procedures, equip-ment, or systems as described in the safety analysis report, and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS; l
2)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; 3)
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; 4)
Proposed changes in Technical Specifications or this Operating License; BRAIDWOOD - UNITS 1 & 2 6-7 AMENDMENT N0.16
(-
1 L
l
?.
i ADMINISTRATIVE CONTROLS OFFSITE(Continued]
l 1
i 5)
Noncompliance with Codes, regulations, orders, Technical Speci-j fications, license requirements, or of internal procedures, or l
instructions having nuclear safety significance; 6)
Significant operating abnormalities or deviation from normal I
and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative i
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; and
- 10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President PWR Operations, and AVP Quality Programs and Assessment.
b.
Station Audit Function The station audit function shall be the responsibility of the AVP Quality Programs and Assessment independent of the PWR Operations.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
The Nuclear Quality Programs Manager or designated Corporate Staff or Supervision 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 ba performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure that safety-related functions are covered within the period designated below:
l 1)
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; 2)
The adherence to procedure, training, and qualification of the station staff at least once per 12 months; 3)
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months; 4)
The performance of activities required by the Operatiorial Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; BRAIDWOOD - UNITS 1 & 2 6-8 AMENDMENT NO.16
s
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- l. 7 ;
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' ADMINISTRATIVE CONTROLS
'0FFSITE (Continued)-
5)
The; Facility Emergency Plan and implementing pro;edures at least once per 12 months; 6)
The Facility Security Plan and implementing procedures at least once per 12 months; l;
7)
Onsite and offsite reviews; I
8)
The Facility Fire Protection programmatic controls including the implementing procedures at least once per 24 months by qualified QA personnel; 9)
The fire protection equipment and program implementation at I
least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent
~ fire protection consultant.
An outside independent fire pro-tection consultant shall be used at least every third year;
- 10) The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months;
- 11) The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months;
- 12) The PROCESS CONTROL PROGRAM and implementing procedures for I
solidification of radioactive wastes at least once per 24 months; and
- 13) The performance of activities required by the Company Quality Assurance Program for effluent and environmental monitoring at-least once per 12 months.
f Report all findings of noncompliance with NRC requirements and recom-mendations and results of each audit to the Station. Manager, Manager of QA/NS, the Vice Presidr-i. PWR Operations, AVP Quality Programs and Assessment, the Senior W.e President - Nuclear Operations, and the Chief Operating 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 u.
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.
BRAIDV30D - UNITS 1 & 2 6-9 AMENDMENT NO.I6 i
ADMINISTRATIVE CONTROLS OFFSITE (Continued) 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 4
of experience in the metallurgical field.
3)
Ti.e Superintendent of the Offsite Review and Investigative Func-i tion shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.
ONSITE 6.5.2 The Onsite Review and Investigative Function shall be supervised by the Station Manager.
j a.
Onsite Review and Investigative Tunction d
The Station Manager shall:
(1) provide directions for the Review l
and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as the senior participant to provide appropriate directions; (2) approve participants, for this function; (3) assure that at least two participants who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve i
the findings and recommendations developed by personnel performing the Review and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommendations; l
and (6) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Specifi-cation 6.5.la which have been approved by the Onsite Review and Investigative Function.
b.
Responsibility The responsibilities of the personnel performing this function are:
1)
Review of:
(1) stction specific portions of all procedures required by Specification 6.8.1 and changes thereto, (2) all programs required by Specification 6.8.4 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear i
safety; 2)
Review of all proposed tests and experiments that affect nuclear safety; BRAIDWOOD - UNITS 1 & 2 6-12 AMENDMENT N0.16 j
~
ADMINISTRATIVE CONTROLS ONSITE (Continued) 3)-
Review of all proposed changes to the Technical Specifications; 4)
Review of all proposed changes or modifications to plant systems or equipment that affect n' clear safety; u
5)'
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prev at recurrence; l
6)
Review of all REPORTABLE EVENTS; 7)
Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review and Investi ative Function; 0
8)
Review of the Station Security Plan and implementing procedures
' and submittal of recommended Security Plan changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with Specification 6.5.2d.1; 9)
Review of the Emergency Plan and station implementing procedures and identification of recommended changes;
'l
- 10) Review of Unit operations to detect potential hazards to nuclear.
safety;
- 11) Review of any accidental, unplanned, or uncontrolled radioactive I
release including the preparation and forwarding of reports I
covering evaluation, recommendations and disposition of the corrective action to prevent recurrence; l
- 12) Review of~ changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems;
- 13) Review of the Fire Protection Program and implementing instruc-tions and identification of recommended changes.
l c.
Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant mainte-nance, operation, and administrative procedures relating to facility operations and shall have the authority to request the action neces-sary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.
The Station Manager shall follow such recommendations or select a course of action that i
(
BRAIDWOOD - UNITS 1 & 2 6-13 AMENDMENT N0.16
ADMINISTRATIVE CONTROLS I
1 v..
.'ONSITE (Continued)
J d
o is more' conservative regarding ' safe operation of the facility.
All such disagreements shall be reported iramediately to the Vice President 4
PWR Operations and the Superintendent of the Offsite Review and Investigative Function.
d.
Records 1)
Reports, reviews, investigations, and recommendations prepared I
and performed for Specification 6.b.2b shall be do:umented with copies to the Vice President PWR Operations, the Superintendent of the Offsite Review and Investigative Function, and the AVP i
Quality Programs and Assessment, unless otherwise specified.
2)
Copies of all records and documentation shall be kept on. file I
at the station.
e.
Procedures i
Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Invest *,'gative Function.
These.
procedures shall include the following:
l 1)
Content and method of submission and presentation to the Station Manager, Vice President PWR Operations and the Superintendent of l
the Offsite Review and Investigative Function, l
2)
Use of committees, l
j 3)
Review and approval, l
4)
Detailed listing of items to be reviewed, l
5)-
Procedures for administration of the quality control activities, and 6)
Assignment of responsibilities.
f.
Personnel 1)
The personnel performing the Onsite Review and Investigative Function, in addition to the Station Manager, shall consist of persons having expertise in:
i, a)
Nuclear power plant technology, b)
Reactor operations, l
c)
Reactor engineering, d)
Chemistry l
e)
Radiological controls, L
f)
Instrumentation and control, and L
g)
Mechanical'and electrical systems.
BRAIDWOOD - UNITS 1 & 2 6-14 AMENDMENT N0.16 L
4 s
ADMINISTRATIVE CONTROLS ONSITE (Continued) 2)
Personnel performi.
he Onsite Review and Investigative Function shall meet minimum a.ceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.
6.6 REPORTABLE EVENT ACTION 6.6.1 The-following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTA3LE EVENT shall be reviewed by the Onsite Review and Investigative Function and the results of this review shall be subruitted to the Offsite Review and Investigative Function and the i
Vice President 9WR Operations.
I 6.7 SAF6TY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
l a.
The.NRC Operations Center shall be notified by telephone a.: soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President 3WR Operations and the Offsite Review and Investigative Function shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.
A Safety Limit Violation Report shall be prepned.
The report shall be reviewed by the Onsite Review and Investigative Function.
This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,.
systems or structures, and (3) corrective action taken to pievent recurrence; c.
The Safety Limit Violation Report shall be submitted to the Commission, the Offsite Review and Investigative Function and the Vice President PWR Operations within 14 days of the violation; and l
l d.
Critical operation of the Unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activitie: referenced below:
a.
The applicable procedures recommended in Appendix A, of Regulatory Guide 1.33, Revision 2, February 1978, BRAIDWOOD - UNITS 1 & 2 6-15 AMENDMENT NO. 16 1
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ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Perniit (RWP).
Individuals qualified in radiation protection procedures or personnel continuously escorted l
by,uch individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, 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 followir.g:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area; o" b.
A raajation 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 levels in the area have been established and personnel have been made knowledgeable of them;.or c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who :s responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the Radiation Work Permit.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from
.the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
During emergency situations which involve personnel injury or actions taken to prevent major equipment damage, continuous surveillance and radin'on monitoring of the work area by a qualified individual may be substituted for 1he routine RWP procedure.
For individual high radiation areas accessible to personnel with radiation sevels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded (by a more substantial obstacle than rope),
conspicuously posted, and a flashing light shall be activated as a warning device.
BRAIDWOOD - UNITS 1 & 2 6-24 AMENDMENT N0.16
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' ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
1 6.13.2 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 j
made.
This submittal shall contain:
j 1)
Sufficiently dotailed information to totally support the rationale for the change without benefit of additionai or l
supplemental information; 2)
A determination that the chalige did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3)
Documentation of the fact that the change has been reviewed and found acceptable.by the Onsite Review and Investigative Function, b.
Shall become effective upon review and acceptance by the Onsite Review and' Investigative Function -in accordance with Specification 6.5.2.
bl4 0FFSITE 00SE CALCULATION MANUAL (00CM) 6.14.1 The ODCM shall be approved by tne Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
a.
Shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.9.1.8 within 90 days of the date the change (s) was made effective.
This submittal shall contain:
1).
Sufficiently detailed infomation to totally support the rationale for the change without benefit of additional or l
supplemental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered, dated and containing the revision number, 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 L
3)
Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and Investigative Function, j
b.
Shall become effective upon review and acceptance by the Onsite Review and Investigative Function in accordance with Specification 6.5.2.
BRAIDWOOD - UNITS 1 & 2 6-25 AMENDMENT NO.16